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Yamagata, Ichiro; Hayashi, Takehiro; Mashiko, Shinichi*; Sasaki, Shinji; Inoue, Masaki; Yamashita, Shinichiro; Maeda, Koji
JAEA-Testing 2013-004, 23 Pages, 2013/11
JAEA-Testing-2013-004.pdf:8.59MB
In the accident of the Fukushima Daiichi Nuclear Power Plant of Tokyo Electric Power Co. accompanying the Great East Japan Earthquake, fuel assemblies kept in the spent fuel pool of reactor units 1-4, were exposed to the inconceivable environment such as falling and mixing of rubble, especially seawater were injected into unit 2-4. In order to evaluate the integrity of the fuel assemblies in spent fuel pools, and in the long-term storage after transported to the common storage pool, the immersion tests were performed using zircaloy-2 fuel cladding tubes irradiated in the advanced thermal reactor Fugen. The immersion liquid was prepared with doubling dilution of artificial seawater, which temperature was 80 
C and immersion time was about 336 hours, as assuming the situation of the pool. The results indicated zircaloy-2 cladding tubes had no significant corrosion and no influence on mechanical property by immersion tests with artificial seawater conditions of this work.
Nakano, Masanao; Watanabe, Hitoshi; Sumiya, Shuichi
JAEA-Testing 2013-003, 29 Pages, 2013/11
JAEA-Testing-2013-003.pdf:11.89MB
Since the remote sensing technique for the meteorological observation has been developing these years, the Doppler Lidar is available in the commercial market. Although some investigation organization carried out the examination on the method and application of Doppler Lidars and had generally good results, the duration of the examination was limited in a short period. So it is unknown that the Doppler Lidar can be applicable to the long-term meteorological observation in the nuclear facilities to assess the public dose around nuclear facilities. In order to examine the long-term performance requested by the Japanese guideline for meteorological observation (i.e., the annual and the sequential 30-days missing rate should be less than 10% and 30%, respectively.) and the consistency with the data measured by conventional type, the wind direction and speed was measured by the Doppler Lidar (Windcube WLS7 made by Leosphere Co Ltd.) for one year, then compared with those by the propeller type installed at the top of the meteorological observation tower. As the result, the missing rate of the Doppler Lidar was satisfied with the guideline at the height less than 180 m, and the data at 68 m above the ground level (100 m above sea level) had a good relationship with the propeller data. From this fact, the Doppler Lidar used in this examination is considered to have a practicability for the dose assessment of the public.
Sakamoto, Kensaku; Hoshi, Yoshiyuki*
JAEA-Testing 2013-002, 80 Pages, 2013/11
JAEA-Testing-2013-002.pdf:8.37MB
On research and development of various fields of nuclear energy, visualization of calculated data is especially useful to understand the result of simulation in an intuitive way. Many researchers who run simulations on the supercomputer in Japan Atomic Energy Agency (JAEA) are used to transfer calculated data files from the supercomputer to their local PCs for visualization. In recent years, as the size of calculated data has gotten larger with improvement of supercomputer performance, reduction of visualization processing time as well as efficient use of JAEA network is being required. As a solution, we introduced a remote visualization system which has abilities to utilize parallel processors on the supercomputer and to reduce the usage of network resources by transferring data of intermediate visualization process. This paper reports a study on the performance of image processing with the remote visualization system. The visualization processing time is measured and the influence of network speed is evaluated by varying the drawing mode, the size of visualization data and the number of processors. Based on this study, a guideline for using the remote visualization system is provided to show how the system can be used effectively. An upgrade policy of the next system is also shown.
Takebe, Shinichi; Sasaki, Toshihisa; Saito, Tatsuo; Yamaguchi, Naoko
JAEA-Technology 2013-033, 87 Pages, 2013/11
JAEA-Technology-2013-033.pdf:2.49MB
Materials, etc. in a non-controlled area is, if the criteria (10 microsieverts per year) listed below that in "A guideline regarding treatment of materials in nuclear facilities considering the influence of fallout released from the accident of TEPCO's Fukushima Dai-ichi Nuclear Power Station" (March 30, 2012), that in accordance with relevant laws and regulations, such as "Waste Disposal and Cleaning Act" (Act No. 137 of 1970), effective use as a resource or be properly disposed of is required. In this paper, in order to effectively use as resources or properly disposed of the materials, etc. in a non-controlled area, radioactivity concentration of materials, etc. in you see " For clearance level specified in Radiation Hazards Prevention Law" and "Radionuclide Concentrations for Materials not Requiring Treatment as Radioactive Wastes Generated from Dismantling etc. of Reactor Facilities and Nuclear Fuel Use Facilities (in Japanese), NSC Japan, 2005." corresponds to the dose of the above criteria the presented results have been estimated as an example.
Okano, Fuminori; Masaki, Kei; Yagyu, Junichi; Shibama, Yusuke; Sakasai, Akira; Miyo, Yasuhiko; Kaminaga, Atsushi; Nishiyama, Tomokazu; Suzuki, Sadaaki; Nakamura, Shigetoshi; et al.
JAEA-Technology 2013-032, 32 Pages, 2013/11
JAEA-Technology-2013-032.pdf:8.86MB
Japan Atomic Energy Agency started to construct a fully superconducting tokamak experiment device, JT-60SA, to support the ITER since January, 2013 at the Fusion Research and Development Directorate in Naka, Japan. The JT-60SA will be constructed with enhancing the previous JT-60 infrastructures, in the JT-60 torus hall, where the ex-JT-60 machine was disassembled. The JT-60SA Cryostat Base, for base of the entire tokamak structure, were assembly as first step of this construction. The Cryostat Base (CB, 250 tons) is consists of 7 main made of stainless steel, 12m diameter and 3m height. It was built in the Spain and transported to the Naka site with the seven major parts split, via Hitachi port. The assembly work of these steps, preliminary measurements, sole plate adjustments of its height and flatness, and assembly of the CB. Introduces the concrete result of assembly work and transport of JT-60SA cryostat base.
Okano, Fuminori; Ikeda, Yoshitaka; Sakasai, Akira; Hanada, Masaya; Ichige, Hisashi; Miyo, Yasuhiko; Kaminaga, Atsushi; Sasajima, Tadayuki; Nishiyama, Tomokazu; Yagyu, Junichi; et al.
JAEA-Technology 2013-031, 42 Pages, 2013/11
JAEA-Technology-2013-031.pdf:18.1MB
The disassembly of JT-60 tokamak device and its peripheral equipments, where the total weight was about 6200 tons, started in 2009 and accomplished in October 2012. This disassembly was required process for JT-60SA project, which is the Satellite Tokamak project under Japan-EU international corroboration to modify the JT-60 to the superconducting tokamak. This work was the first experience of disassembling a large radioactive fusion device based on Radiation Hazard Prevention Act in Japan. The cutting was one of the main problems in this disassembly, such as to cut the wielded parts together with toroidal field coils, and to cut the vacuum vessel into two. After solving these problems, the disassembly completed without disaster and accident. This report presents the outline of the JT-60 disassembly, especially tokamak device.
Watanabe, Akihiko; Sakai, Kenji; Oi, Motoki; Meigo, Shinichiro; Takada, Hiroshi
JAEA-Technology 2013-028, 21 Pages, 2013/11
JAEA-Technology-2013-028.pdf:2.46MB
The General Control System (GCS) of the MLF of J-PARC has a problem that it costs very much in the maintenance because of its poor flexibility on OS, etc. For resolving the problem, we have re-examined framework and application softwares for the MLF-GCS, in considering functions that PLCs in many local control panels are controlled by the plural exclusive PCs, and operating data over 7000 are acquired, stored and distributed with suitable data format by shared servers. Furthermore, we have made a prototype of an upgraded GCS and evaluated its concrete performances with true data such as communication speed between the PLCs and PCs, control functions from operating windows, storage capability of data server, and long-term stability of the system. In conclusion, we decided to adopt following softwares for the upgraded GCS: EPICS as framework software, Takebishi OPC server as data input/output module, CSS as user interface window and PostgreSQL for the data storage server.
Department of Decommissioning and Waste Management
JAEA-Review 2013-029, 105 Pages, 2013/11
JAEA-Review-2013-029.pdf:10.51MB
This report describes the activities of Department of Decommissioning and Waste Management (DDWM) in Nuclear Science Research Institute (NSRI) in the period from April 1, 2010 to March 31, 2011. The report covers organization and missions of DDWM, operation and maintenance of facilities which belong to DDWM, treatment and management of radioactive wastes, decommissioning activities, and related research and development activities which were conducted by DDWM.
Research Cooperation Section
JAEA-Review 2013-024, 100 Pages, 2013/11
JAEA-Review-2013-024.pdf:71.13MB
This report includes a summary of the results of the research carried out in fiscal year 2012 on 20 research collaboration subjects for preceding basic engineering research related to fast breeder reactors, the nuclear fuel cycle, radiation safety and geological disposal/geoscience.
Nakayama, Masashi
JAEA-Review 2013-022, 27 Pages, 2013/11
JAEA-Review-2013-022.pdf:5.97MB
As part of the research and development program on geological disposal of high-level radioactive waste (HLW), the Horonobe Underground Research Center, a division of the Japan Atomic Energy Agency (JAEA), is implementing the Horonobe Underground Research Laboratory Project (Horonobe URL Project) with the aim at investigating sedimentary rock formations. According to the research plan described in the 2nd Midterm Plan of JAEA, geological investigations are to be carried out during the drilling of a shaft down to around 350m depth, while research and development in the areas of engineering technology and safety assessment are to be promoted by collaboration with other research organizations. The results of the R&D activities will be systematized as a "knowledge base" that supports a wide range of arguments related to the safety of geological disposal. The Horonobe URL Project is planned to extend over a period of about 20 years. The investigations will be conducted in three phases, namely "Phase 1: Surface-based investigations", "Phase 2: Construction phase" (investigations during construction of the underground facilities) and "Phase 3: Operation phase" (research in the underground facilities). This report summarizes the investigation program for the 2013 fiscal year (2013/2014). In the 2013 fiscal year, investigations in "geoscientific research", including "development of techniques for investigating the geological environment", "development of engineering techniques for use in the deep underground environment" and "studies on the long-term stability of the geological environment", are continuously carried out. Investigations in "research and development on geological disposal technology", including "improving the reliability of disposal technologies" and "enhancement of safety assessment methodologies", are also continuously carried out.
Nuclear Human Resource Development Center
JAEA-Review 2013-021, 77 Pages, 2013/11
JAEA-Review-2013-021.pdf:4.05MB
This annual report summarizes the activities of Nuclear Human Resource Development Center (NuHRDeC) of Japan Atomic Energy Agency (JAEA) in the fiscal year 2011. In this fiscal year, we flexibly designed and conducted training courses corresponding with the needs from outside, while conducting the annually scheduled training programs, and also actively addressed the challenge of human resource development, such as to enhance the collaboration with academia and to organize international training for Asian countries.
Kojima, Keiji*; Onishi, Yuzo*; Aoki, Kenji*; Tochiyama, Osamu*; Nishigaki, Makoto*; Tosaka, Hiroyuki*; Yoshida, Hidekazu*; Ogata, Nobuhisa
JAEA-Research 2013-015, 21 Pages, 2013/11
JAEA-Research-2013-015.pdf:10.41MB
This report is concerned with research to reconstruct more realistic near-field concept for the geological disposal. In chapter, we examined the realistic concept for near field, including rock around the tunnel, based on the nuclide migration scenario in particular. The time-series change of the field was divided into five stages of 0
IV through the process of geological disposal (Excavation, Operation and Post-closure). Then, for each stage respectively, we examined interaction between environmental factors and extraction of those factors changing the "field". The Goal of this year is to set up the state in the realistic "field" exhaustively, by focusing on the scale-time cross-section of each stage, especially post-closure stage, and to present the assignment of the next fiscal year.
Sakatani, Keiichi; Sugaya, Toshikatsu; Nakatani, Takayoshi; Funabashi, Hideyuki
JAEA-Data/Code 2013-015, 63 Pages, 2013/11
JAEA-Data-Code-2013-015.pdf:8.75MB
The safety assessment of the sub-surface disposal system should ensure that calculated dose will be lower than the dose assigned to the scenario in question during the period from now to future. In order to realize the safety disposal, we have developed several assessment tools on the GoldSim platform and calculated doses since 2008, and these assessment tools have been improved reflecting the last view of assessment. This report describes safety functions of the disposal system, idea of nuclide migration, formulas for nuclides migration, formulas of exposure dose and structure of assessment tool for groundwater scenario.
Tanaka, Kiwamu; Yasuda, Mari; Watanabe, Koichi; Hoshi, Akiko; Tsuji, Tomoyuki; Higuchi, Hidekazu
JAEA-Data/Code 2013-008, 16 Pages, 2013/11
JAEA-Data-Code-2013-008.pdf:2.41MB
Simple and rapid methods to evaluate the radioactivity concentrations are required to be established for the near surface disposal of radioactive wastes generated from research facilities at Japan Atomic Energy Agency. In order to establish the methods to evaluate the radioactivity concentrations of miscellaneous solid wastes generated from research and testing reactors, we collected and analyzed samples from miscellaneous solid wastes generated by the decommissioning of JPDR (Japan Power Demonstration Reactor). In the present paper, we summarized data about the radioactivity concentrations which accumulated by the analysis.
Tsuda, Shuichi; Yoshida, Tadayoshi; Nakahara, Yukio; Sato, Tetsuro; Seki, Akiyuki; Matsuda, Norihiro; Ando, Masaki; Takemiya, Hiroshi; Tanigaki, Minoru*; Takamiya, Koichi*; et al.
JAEA-Technology 2013-037, 54 Pages, 2013/10
JAEA-Technology-2013-037.pdf:4.94MB
JAEA has been performing dose rate mapping in air using a car-borne survey system KURAMA-II. The KURAMA system is a GPS-aided mobile radiation monitoring system that has been newly developed by Kyoto University Research Reactor Institute in response to the nuclear disaster. The KURAMA system is composed of an energy-compensated scintillation survey meter for measuring dose rate, electric device for controlling both the dose rates and the position data from a GPS module, a computer server for processing and analyzing data from KURAMA, and client PCs for providing for end users. The KURAMA-II has been improved in small-packaging, durability, and automated data transmission. In consequence, dose rate mapping in wide area has become possible in shorter period of time. This report describes the construction of KURAMA-II, its application and a suggestion of how to manage a large number of KURAMA-II.
Nakanishi, Chika; Sato, Takeshi; Sato, Sohei; Nagai, Haruyasu; Kakefuda, Toyokazu; Katata, Genki; Tsuzuki, Katsunori; Ikeda, Takeshi; Okuno, Hiroshi; Yamamoto, Kazuya; et al.
JAEA-Technology 2013-030, 105 Pages, 2013/10
JAEA-Technology-2013-030.pdf:29.0MB
North Korea carried out the third nuclear test in February 2013. Due to the request of the Ministry of Education, Culture, Sports, Science and Technology (MEXT), Nuclear Emergency Assistance and Training Center (NEAT) and Nuclear Science and Engineering Directorate (NSED) of JAEA predicted the atmospheric dispersion of radionuclide by WSPEEDI-II for the purpose of contributing to the environmental monitoring plan. From February 12 to 22, they provided daily reports on the prediction to the MEXT and the Ministry of Defense. MEXT has published these reports on the website. Since April 2012, NEAT and NSED had prepared to predict by the framework for the prediction around the clock during 10months until February 2013. This report described this experience and pointed issues out on this system.
Ishigami, Tsutomu; Sukegawa, Takenori*; Mukai, Masayuki
JAEA-Technology 2013-027, 124 Pages, 2013/10
JAEA-Technology-2013-027.pdf:5.9MB
In order to safely and efficiently implement decommissioning of nuclear installations, it is important to beforehand predict decommissioning project management data (PMD) and to develop a decommissioning plan based on the predicted results. The PMD prediction is made with PMD evaluation equations including model parameters such as unit work activity coefficients. Although model parameter values developed so far include uncertainties, little evaluation of the uncertainties and resulted uncertainties in predicted PMD has been made. However information on the uncertainties is valuable in flexibly studying and developing a decommissioning plan. We therefore studied and evaluated uncertainties in model parameters by analyzing the JPDR decommissioning experience data. This report describes an evaluation method of the model parameter uncertainties and their evaluated results.
Takato, Kiyoto; Murakami, Tatsutoshi; Suzuki, Kiichi; Shibanuma, Kimikazu; Hatanaka, Nobuhiro; Yamaguchi, Bungo; Tobita, Yoshimasa; Shinozaki, Masaru; Iimura, Naoto; Okita, Takatoshi; et al.
JAEA-Technology 2013-026, 42 Pages, 2013/10
JAEA-Technology-2013-026.pdf:3.17MB
In order to cope with making a commercial fast reactor fuel burn-up higher, oxygen-to-metal (O/M) ratio in the fuel specification is designed to 1.95. As the test for the fabrication of such low O/M ratio pellets, two kinds of O/M ratio preparation tests of different reduction mechanism were done. In the first test, we evaluated the technology to prepare the O/M ratio low by annealing the sintered pellets in production scale. In addition, we know from past experience that O/M ratio of the sintered pellets can be reduced by residual carbon when the de-waxed pellets with high carbon content are sintered. Thus, in another test, the green pellets containing a large amount of organic additives were sintered and we evaluated the technology to produce the low O/M ratio sintered pellets by the reduction due to residual carbon. From the first test results, we found a tendency that the higher annealing temperature or the longer annealing time resulted in the lower O/M ratio. However, the amount of O/M ratio reduction was small and it is estimated that a substantial annealing time is necessary to prepare the O/M ratio to 1.95. It is considered that reducing O/M ratio by annealing was difficult because atmosphere gas containing oxygen released from pellets remained and the O/M ratio was changed to the value equilibrated with the gas having high oxygen potential. From another test results, it was confirmed that O/M ratio was reduced by the reduction due to residual carbon. We found that it was important to manage an oxygen potential of atmosphere gas in a sintering furnace low to reduce the O/M ratio effectively.
Mo manufacturing process, 1; Reusability evaluation of Mo absorbent (Joint research)Kimura, Akihiro; Niizeki, Tomotake*; Kakei, Sadanori*; Chakrova, Y.*; Nishikata, Kaori; Hasegawa, Yoshio*; Yoshinaga, Hideo*; Chakrov, P.*; Tsuchiya, Kunihiko
JAEA-Technology 2013-025, 40 Pages, 2013/10
JAEA-Technology-2013-025.pdf:2.62MB
Neutron Irradiation and Testing Reactor Center has developed the production of a medical isotope of Mo, the parent nuclide of 
Tc by the (n,
) method using JMTR. The (n,) method has an advantage of easy manufacturing process and low radioactive wastes generation. However, the low radioactivity concentration of Tc is remaining as an issue. Therefore, PZC and PTC have been developed as adsorbent of molybdenum. Meanwhile, it is necessary to recycle the absorbent and Mo for the reduction of the radioactive waste of used-adsorbent and the effective use of limited resources, respectively. This report summarizes results of the synthesis of Mo adsorbents such as PZC and PTC, and the performance tests.
Shibata, Akira; Miura, Kuniaki*; Takeuchi, Tomoaki; Otsuka, Noriaki; Nakamura, Jinichi; Tsuchiya, Kunihiko
JAEA-Technology 2013-024, 21 Pages, 2013/10
JAEA-Technology-2013-024.pdf:12.62MB
In the Fukushima-Daiichi Nuclear Power Plant Accident, the measurements of water level in pressure vessel and spent fuel pool were impossible due to station blackout, and it resulted in difficulty for countermeasures against the accidents and for understanding of the situations of reactor core after accidents. Therefore, we started to develop a new water level sensor for l with high reliability, which works with small electric power. This report describes reviews of conventional water level sensor and design and production of new water level sensor. After production of the sensor, performance tests were performed between room temperature and about 95 C, and the it was confirmed that the sensor is able to measure water level with the accuracy of 
20 mm. As the results, a perspective to use the new water level sensor as water level indicator for spent fuel pools and reactor vessels after severe accident.
Suguro, Toshiyasu; Nishikawa, Yoshiaki*; Watahiki, Takashi*; Kagawa, Akio
JAEA-Technology 2013-023, 22 Pages, 2013/10
JAEA-Technology-2013-023.pdf:2.41MB
For safety assessment of TRU waste disposal, solubility of plutonium was investigated under hardened cement paste porewater condition. Polycarboxylic acid compound, which have the possibility to be used for the TRU waste disposal, was selected as the cement admixture for the experiment. Initial concentration of Pu was 10
M in the experiment. The porewater of hardened cement paste was obtained by squeezing out the kneading of ordinary portland cement and deionized water with the cement admixture. The porewater of hardened cement paste without cement admixture is also used for the experiment. The maximum experimental period was 154 days. The experiment was carried out at room temperature (298 5 K) under argon atmosphere, in which oxygen concentration was lower than 1 ppm. Pu concentration in the porewater of hardened cement paste with or without the cement admixture were in the order of 10
mol/dm
after 154 days. This value is comparable to the solubility of Pu(IV) under high pH condition, suggesting that the solubility of Pu was not affected by the cement admixture in hardened cement paste.
Kuji, Masayoshi*; Asai, Hideaki*; Hashizume, Shigeru; Horiuchi, Yasuharu; Sato, Toshinori; Matsui, Hiroya
JAEA-Technology 2013-022, 72 Pages, 2013/10
JAEA-Technology-2013-022.pdf:5.3MB
Rock mass classifications are used for design and construction of underground structures. However, the classification methods commonly used in Japan are qualitative and inadequate for estimating the actual mechanical properties of a rock mass based on site specific geological features. Considering the design, construction and safe operation of large underground facilities, an important requirement is to utilize a rock mass classification method that can estimate site specific rock mechanical properties based on surface-based investigations and geological observations during excavation. For this study, a new quantitative rock mass classification method based on JGS standard was proposed and applied to the sedimentary formations and the granite at MIU. The results were compared with the rock mass classification system developed by CRIEPI and commonly used in JAPAN. Then the applicability of the new rock mass classification could be evaluated.
Okada, Yuji; Magome, Hirokatsu; Hanawa, Hiroshi; Omi, Masao; Kanno, Masaru; Iida, Kazuhiro; Ando, Hitoshi; Shibata, Mitsunobu; Yonekawa, Akihisa; Ueda, Haruyasu
JAEA-Technology 2013-019, 236 Pages, 2013/10
JAEA-Technology-2013-019.pdf:45.07MB
In Japan Atomic Energy Agency, in order to solve the problem in the long-term operation of a light water reactor, preparation which does the irradiation experiment of light-water reactor fuel and material is advanced. JMTR stopped after the 165th operation cycle in August 2006, and is advancing renewal of the irradiation facility towards re-operation. This material irradiation test facility and power ramping test facility for doing the neutron irradiation test of the fuel and material for light water reactors is scheduled to be manufactured and installed between the 2008 fiscal year and the 2012 fiscal year. This report summarizes manufacture and installation of the material irradiation test facility for IASCC research carried out from the 2008 fiscal year to the 2010 fiscal year.
Engineering Services Department
JAEA-Review 2013-025, 114 Pages, 2013/10
JAEA-Review-2013-025.pdf:6.88MB
The Engineering Services Department is in charge of operation and maintenance of utility facilities (water distribution systems, electricity supply systems, steam generation systems and drain water systems etc.) in whole of the institute. And also is in charge of operation and maintenance of specific systems (a receive transmitted electricity system, an emergency electric power supply system, an air/liquid waste treatment system, a compressed air supply system) in nuclear reactor facilities, nuclear fuel treatment facilities and usual facilities or buildings. In addition, the department is in charge of maintenance of buildings, design and repair of electrical/mechanical/glass made experimental equipments and operation of the large scale experiment facilities. This annual report describes summary of activities, operation and maintenance data and technical developments of the department carried out in JFY 2011.
Yasue, Kenichi; Asamori, Koichi; Niwa, Masakazu; Hanamuro, Takahiro; Kokubu, Yoko; Makuuchi, Ayumu; Ikuta, Masafumi; Matsubara, Akihiro; Ishimaru, Tsuneari; Umeda, Koji
JAEA-Review 2013-023, 42 Pages, 2013/10
JAEA-Review-2013-023.pdf:2.82MB
The concept of geological disposal of HLW in Japan is based on a multi-barrier system which combines a stable geological environment with a robust barrier system. Potential geological host formations and their surroundings are chosen, in particular, for their long-term stability, taking into account the fact that Japan is located in a tectonically active zone. This report is a plan of research and development (R&D) on geosphere stability for long-term isolation of HLW in JAEA, in fiscal year 2013. The objectives and contents in fiscal year 2013 are described in detail based on the outline of 5 years plan (fiscal years 2010-2014). In addition, the planned framework is structured into the following categories: (1) Development and systematization of investigation techniques, (2) Development of models for long-term estimation and effective assessment, (3) Development of dating techniques.
Ito, Kimio; Ono, Takayuki; Ishimori, Yuu; Kawasaki, Satoru
JAEA-Review 2013-020, 44 Pages, 2013/10
JAEA-Review-2013-020.pdf:5.03MB
The Ningyo-toge Environmental Engineering Center of the Japan Atomic Energy Agency (JAEA Ningyo-toge) performs the environmental monitoring around the Ningyo-toge and the waste rock sites according to the agreements with local governments, Okayama and Tottori prefectures. Environmental monitoring of plutonium has been also performed around the Ningyo-toge regarding the practical application study on the reprocessed uranium conversion, which was carried out from 1994 to 1999 at the Ningyo-toge. Each prefectural committee on the environmental monitoring evaluates the monitoring data annually. This report summarized the results of the environmental monitoring in Okayama prefecture in the fiscal year 2011. The results show that the levels of the radiation doses and the radioactive concentrations in the environment were within natural variations, and the committee concluded that the environmental impacts from the sites were negligible. Therefore, the site of the JAEA Ningyo-toge has been well operated, and the waste rock sites have been well maintained.
Fukaya, Hiroyuki; Suyama, Kenya; Sonoda, Takashi; Okubo, Kiyoshi; Umeda, Miki; Uchiyama, Gunzo
JAEA-Research 2013-020, 81 Pages, 2013/10
JAEA-Research-2013-020.pdf:3.81MB
Japan Atomic Energy Agency conducted a project "Isotopic Composition measurement of Fission Products in Spent Fuel from FY2008 to FY2011" by the entrustment of Japan Nuclear Energy Safety Organization. In that project, we measured the isotopic composition of neodymium isotopes which are important to evaluate the burnup value of spent nuclear fuel by using two different methods and obtained different results. So that we carried out the follow-up measurement in order to investigate the reason of the difference between two neodymium measurements. It was found that we needed correction to the measurement results of neodymium for two samples and a part of other fission products for all samples in total five samples. This report summarizes the all works carried out in this follow-up measurement and obtained results.
Yoshida, Kazuo; Ishikawa, Jun
JAEA-Research 2013-013, 24 Pages, 2013/10
JAEA-Research-2013-013.pdf:2.13MB
Boiling accidents of liquid wastes are postulated to be occurred caused by the loss of cooling function for waste storage tanks at fuel reprocessing facilities. Some amounts of radioactive materials could be released from facilities caused by vapor flow. Aerosol behaviors in compartments of facility building are essential to be analyzed for assessing amount of released radioactive materials. The atmosphere in the compartments consists of not only air and water vapor, but also HNO
vapor and NOx gases. Properties of viscosities, diffusion coefficients of those gases are necessary to simulate aerosol transport behaviors. The major simulation models for aerosol transport behaviors programmed in the exciting computer codes for severe accidents analysis of nuclear power plants are reviewed in this report to clarify essential thermodynamic properties. Viscosities are estimated for HNO, NO
and NO
. Recommended values are discussed for applying those existing code to boiling accident.
Shimemoto, Hidenori; Yamaguchi, Masaaki; Wakasugi, Keiichiro; Shibata, Masahiro
JAEA-Research 2013-012, 35 Pages, 2013/10
JAEA-Research-2013-012.pdf:8.16MB
In this study, we focus on uplift and erosion and climatic and sea-level changes among natural phenomena and pick up fluvial erosion is main and means large velocity between different type of erosion in Japan, and developed conceptual modeling of geomorphic change due to fluvial erosion with respect to fluvial erosion and sedimentation system, to evaluate the potential impact of exposure case of high level radioactive waste to land surface. Conceptual modeling of geomorphic change caused by fluvial erosion is developed with riverhead and downriver, such catchment areas are not treated until now, by conceptualization of geomorphic change on river due to uplift and denudation and climatic and sea-level changes for about last hundred and twenty thousand years. Furthermore, we analysis the depth and width of deepening and lateral erosion around river channel using the data of alluvium and show an example of the setup method concerning dimension on conceptual model to estimate the erosion volume contribute to the evaluation as to high level radioactive waste exposure process to land surface. We illustrate by an example the dimension as to valley within the central Japanese mountains using DEM data on conceptual model at riverhead. We develop conceptual modeling of geomorphic change on the basis of the feature on fluvial erosion in Japan and set basic intelligence to evaluate the potential impact of repository exposure to land surface caused by fluvial erosion, based on above study.
Ebara, Shinji*; Yuki, Kazuhisa*; Hashizume, Hidetoshi*; Aizawa, Kosuke; Yamano, Hidemasa
JAEA-Research 2013-011, 72 Pages, 2013/10
JAEA-Research-2013-011.pdf:11.34MB
In Tohoku University, different scale model experiments were carried out in order to clarify unsteady flow fields and pressure fluctuation characteristics in the cold leg piping by means of visualization experiment and pressure measurement, respectively, and to investigate the scale effect. In JFY2008, the visualization experiment by PIV measurement for the 1/15 scale piping was carried out using a double elbow geometry. Besides, shakedown tests of the 1/7 scale model were conducted for the case of a single elbow. In JFY2009, visualization experiments for the 1/7 scale models with the single and a three-dimensionally connected double elbow geometries were carried out. From these obtained data, effects of the multiple elbows on the flow field were assessed. In addition, the pressure measurements for single elbow flows by using 1/15 and 1/7 scale models were performed. In JAEA, numerical analyses for the 1/7 scale double elbow experiments were performed using the commercial thermal-hydraulics code STAR-CD. The analyses showed that the calculated velocity distributions were in good agreement with the visualization experimental results. It was confirmed, from these analyses, that the URANS analysis method validated for the single elbow flow has applicability to the double elbow flow.
Nishihara, Kenji
JAEA-Research 2013-010, 26 Pages, 2013/10
JAEA-Research-2013-010.pdf:2.44MB
Attractiveness as a nuclear material was estimated for fresh and spent fuels in nuclear fuel cycles involving transmutation by fast reactor (FR) and accelerator-driven system (ADS) in equilibrium state. As the result, attractiveness of plutonium in FR and neptunium in FR and ADS was relatively high. Moreover, difference of the attractiveness was observed among fuel cycles, but all plutonium can not be exempted from safeguards, and it is important to introduce other factors of proliferation resistance such as legal framework.
Inoue, Masaki; Suto, Mitsuo; Koyama, Shinichi; Otsuka, Satoshi; Kaito, Takeji
JAEA-Research 2013-009, 78 Pages, 2013/10
JAEA-Research-2013-009.pdf:3.75MB
In order to exammine the applicability for advanced aqueous reprocessing system, the martensitic oxide dispersion strengthened ferritic steel (9Cr-ODS steel), which is the primary candidate material for high burnup fuel pin cladding tube in fast reactor cycle, was evaluated for the amount of corrosion products in the dissolution process. The quantity of corrosion products was calculated to investigate the influence of both various chemical processes and waste glass (vitrified high level radioactive wastes) by use of the results of a maximum cladding temperature fuel subassembly and the sum of all fuel subassemblies, respectively. The experimental results of immersion tests in flowing liquid sodium loops and fuel pin irradiation tests in fast reactors were reviewed to consider the effect of outer and inner corrosions in high burnup fuel pins on corrosion products. This work revealed that the sum of corrosion products depends largely on the mass transfer behavior in flowing liquid sodium.
Ito, Kei; Ohno, Shuji; Kamide, Hideki; Kogawa, Hiroyuki; Futakawa, Masatoshi; Kawamura, Takumi*; Imai, Yasutomo*
JAEA-Research 2013-008, 117 Pages, 2013/10
JAEA-Research-2013-008.pdf:6.55MB
The Japan Atomic Energy Agency has been developed a plant dynamics code VIBUL to simulate the concentration distributions of the dissolved gas and the bubbles in a fast reactor. In this study, the VIBUL code is improved to achieve accurate simulations, e.g. rigorous mole conservation of inert gas. Moreover, new modles are introduced to simulate the small bubble behaviors in the J-PARC mercury target system. To validate the improved models and the newly developed models, the inert gas behaviors in the large-scale sodium-cooled reactor and the small bubble behaviors are simulated. As a result, it is confirmed that the complicated bubble dynamics in each component, e.g. core, IHX or surge tank, can be simulated appropriately by the VIBUL code.
Ito, Kei; Ezure, Toshiki; Ohno, Shuji; Kamide, Hideki; Nakamine, Yoshiaki*; Imai, Yasutomo*
JAEA-Research 2013-007, 75 Pages, 2013/10
JAEA-Research-2013-007.pdf:5.21MB
In Japan Atomic Energy Agency (JAEA), various thermal hydraulics phenomena in an upper plenum region are evaluated in the study on the safety design criteria of the sodium-cooled fast reactor in Japan (JSFR). The gas entrainment (GE) from a free surface of coolant and the vortex cavitation (VC) at the H/L intake are important phenomena to be evaluated. Since these phenomena occur by the significant pressure drop in the vicinity of a vortex center, a technique to evaluate a vortex behavior is indispensable. The authors are developing a GE evaluation method using a numerical analysis and a vortex model. In this study, the evaluations are performed on the GE behavior in the 1/1.8 scaled water model test. In addition, a VC evaluation method is proposed on the basis of the GE evaluation method. As a basic validation of the VC evaluation method, the basic sub-surface vortex test in JAEA is evaluated.
Headquaters of Fukushima Friendship Operations
JAEA-Evaluation 2013-002, 153 Pages, 2013/10
JAEA-Evaluation-2013-002.pdf:12.82MB
Japan Atomic Energy Agency (JAEA) consulted an assessment committee, "Evaluation Committee of Research and Development Activities for Fukushima Environment" (Committee) for interim assessment of "Research and Development of the technologies for Fukushima Environment Recovery" in accordance with the guidelines for the evaluation of R&D activities by Cabinet Office and Ministry of Education, Culture, Sports, Science and Technology and "Regulation on Conduct for Evaluation of R&D Activities" by JAEA. In response to the JAEA's request, the Committee assessed the R&D programs and activities during the period of about two years from March 2011. The Committee evaluated the management and the research programs of JAEA based on the explanatory documents prepared by JAEA and the oral presentations with questions-and-answers by the Director and the research group leaders. This report summarizes the result of the assessment by the Committee with the Committee report.
Hama, Katsuhiro; Sato, Toshinori; Sasao, Eiji; Iwatsuki, Teruki; Kunimaru, Takanori; Matsuoka, Toshiyuki; Takeuchi, Ryuji; Onoe, Hironori; Mikake, Shinichiro
JAEA-Data/Code 2013-010, 58 Pages, 2013/10
JAEA-Data-Code-2013-010.pdf:14.94MB
JAEA at Tono Geoscience Center is pursuing a geoscientific research and development project namely the Mizunami Underground Research Laboratory (MIU) project in crystalline rock environment to construct scientific and technological basis for geological disposal of High-level Radioactive Waste. The MIU project is planned in three overlapping phases; Surface-based Investigation Phase (Phase I), Construction Phase (Phase II) and Operation Phase (Phase III). Currently, the project is under the Phase II and Phase III. In Phase II, adequacy of geological environment model is evaluated. Applicability and feasibility assessment of various elemental technologies adopted to characterize geological environment in Phase I will be evaluated. Furthermore, from a design, construction and safety assessment point of view, a series of evaluation procedures are organized and Geosynthesis Data Flow Diagram is established. This is the integrated data flow from investigation through modeling and analysis. It proposes the rational combinations of investigation items which make the investigation results reflect the safety assessment and designing. In this sense, Geosynthesis Data Flow Diagram indicates the rational framework, from investigation to modeling and analysis, for achieving individual goals and tasks. This report summarizes the Geosynthesis Data Flow Diagram optimized during Phase II investigation. The Geosynthesis Data Flow Diagram will be revised based on the research progress.
Suzuki, Motoe; Saito, Hiroaki*; Udagawa, Yutaka; Nagase, Fumihisa
JAEA-Data/Code 2013-009, 306 Pages, 2013/10
JAEA-Data-Code-2013-009.pdf:5.73MB
A light water reactor fuel analysis code FEMAXI-7 has been developed, as an extended version from the former version FEMAXI-6, for the purpose of analyzing the fuel behavior in normal conditions and in anticipated transient conditions. Numerous functional improvements and extensions have been incorporated in FEMAXI-7, which are fully disclosed in the code model description published in the form of another JAEA-Data/Code report. The present manual, which is the very counterpart of this description document, gives detailed explanations of files and operation method of FEMAXI-7 code and its related codes, methods of input/output, sample Input/output, methods of source code modification, subroutine structure, and internal variables in a specific manner in order to facilitate users to perform fuel analysis by FEMAXI-7.
Nakajima, Ken*; Iwamoto, Osamu; Hori, Junichi*; Iwamoto, Nobuyuki; Nakamura, Shoji; Koura, Hiroyuki
JAEA-Conf 2013-002, 202 Pages, 2013/10
The 2012 symposium on Nuclear Data organized by the Nuclear Data Division of Atomic Energy Society of Japan (AESJ) and Research Reactor Institute, Kyoto University (KURRI) was held at Kumatori, KURRI on Nov. 15th and 16th, 2012 in cooperation with Nuclear Science and Engineering Directorate of Japan Atomic Energy Agency. The symposium was devoted for presentations and discussions on the four topics: "Nuclear Power after Fukushima Nuclear Plant Accident", "Application of Nuclear Data", "How Should We Deal with Covariances of Nuclear Data?" and "Validation of JENDL-4.0 and Future", as well as poster sessions on various research fields. Tutorials on neutron resonance capture and transmission analysis, international trend of nuclear data research were also given in the symposium. Talks as well as posters presented at the symposium aroused lively discussions among approximately 83 participants. This report consists of total 35 papers including 13 oral presentations and 22 poster presentations.
Ohashi, Hirofumi; Sato, Hiroyuki; Yan, X.; Sumita, Junya; Nomoto, Yasunobu; Tazawa, Yujiro; Noguchi, Hiroki; Imai, Yoshiyuki; Tachibana, Yukio
JAEA-Technology 2013-016, 176 Pages, 2013/09
JAEA-Technology-2013-016.pdf:8.62MB
JAEA has started a conceptual design of a 50MWt small-sized high temperature gas cooled reactor for steam supply and electricity generation (HTR50S), which is a first-of-kind of the commercial plant or a demonstration plant of a small-sized HTGR system for steam supply to the industries and district heating and electricity generation by a steam turbine. The plant design of HTR50S for the steam supply and electricity generation was performed based on the plant specification and the requirements for each system taking into account for the increase of the reactor outlet coolant temperature from 750C to 900C and the installation of IHX. The technical feasibility of HTR50S was confirmed because the designed systems satisfies the design requirements. The conceptual plant layout was also determined. This paper provides the summary of the plan design and technical feasibility of HTR50S.
Fast Breeder Reactor Research and Development Center, Tsuruga Head Office
JAEA-Review 2013-032, 172 Pages, 2013/09
JAEA-Review-2013-032.pdf:13.49MB
The prototype fast breeder reactor Monju has accumulated technical achievements in order to establish the fast breeder reactor cycle technology in Japan using the operation and maintenance experience, etc. This annual report summarizes the primary achievements and the data related to the plant management in Monju during fiscal 2012.
Kutsuna, Hideki; Kadowaki, Haruhiko; Sakakibara, Yasuhide; Hirata, Tomohiro
JAEA-Review 2013-027, 40 Pages, 2013/09
JAEA-Review-2013-027.pdf:7.42MB
Fugen Decommissioning Engineering Center is establishing "Technical special committee on Fugen decommissioning" which consists of the members well-informed, aiming to make good use of Fugen as a place for technological development, as the central point in the energy research and development base making project of Fukui prefecture. This report compiles presentation materials "The Current Situation of Fugen Decommissioning", "Upgrading of a Removal Technique for a Heavy Water Withdraw and a Tritium Removal" and "Research of Ageing Management of Nuclear Power Plant for Safe Long Term Operating in Fukui", "The Work for Solution and Promotion on Technical Challenge (Public Offering Type)" which is related with the efforts of Fugen in the Fukui energy research and development centralization plan, presented in the 27th Technical special committee on Fugen decommissioning which was held on March 14, 2013.
Kunimaru, Takanori; Mikake, Shinichiro; Nishio, Kazuhisa; Tsuruta, Tadahiko; Matsuoka, Toshiyuki; Ishibashi, Masayuki; Sasao, Eiji; Hikima, Ryoichi; Tanno, Takeo; Sanada, Hiroyuki; et al.
JAEA-Review 2013-018, 169 Pages, 2013/09
JAEA-Review-2013-018.pdf:15.71MB
Japan Atomic Energy Agency (JAEA) at Tono Geoscience Center (TGC) is pursuing a geoscientific research and development project namely the Mizunami Underground Research Laboratory (MIU) Project in crystalline rock environment in order to construct scientific and technological basis for geological disposal of High-level Radioactive Waste (HLW). The MIU Project has three overlapping phases: Surface-based Investigation phase (Phase I), Construction phase (Phase II), and Operation phase (Phase III). The MIU Project has been ongoing the Phase II and the Phase III in 2011 fiscal year. This report shows the results of the investigation, construction and collaboration studies in fiscal year 2011, as a part of the Phase II and Phase III based on the MIU Master Plan updated in 2010.
Yamada, Satoshi*; Kita, Makoto*; Ishimori, Yuu
JAEA-Research 2013-016, 32 Pages, 2013/09
JAEA-Research-2013-016.pdf:3.01MB
Tottori University and Japan Atomic Energy Agency started a joint study to investigate the effect of hot spring water on the growth of vegetable plants in 2009. The aim of the study is to examine a feasibility of producing a regionally special vegetable with considering the characteristics of the Misasa district, where radon hot springs are historically famous. This report illustrates the intermediate results obtained from the study carried out from 2011 to 2012. [1] Plant physiological examination: Plant physiological examination revealed the effects of Misasa hot spring water on the growth and mineral contents of vegetable plants. [2] Middle scale test: Four tasks for the practical application study were specified; (1) Best mineral contents in hot spring water, (2) Treatment of pH of hot spring water, (3) Toxic substances in hot spring water, (4) A protocol and a system structure for water culture. Then, a middle scale system for water culture was developed.
Secretariat of Symposium on Advanced Photon Research
JAEA-Conf 2013-001, 154 Pages, 2013/09
JAEA-Conf-2013-001.pdf:11.08MB
The 13th Symposium on Advanced Photon Research was held at Kansai Photon Science Institute, Japan Atomic Energy Agency (JAEA-KPSI) in Kizugawa-city, Kyoto on November 15-16, 2012. This report consists of invited and contributed papers presented at the oral and poster sessions in the Symposium.
Muramatsu, Toshiharu; Yamada, Tomonori; Hanari, Toshihide; Takebe, Toshihiko; Matsunaga, Yukihiro
JAEA-Research 2013-024, 49 Pages, 2013/08
JAEA-Research-2013-024.pdf:6.63MB
In decommissioning works of the Fukushima Daiichi Nuclear Power Plants, it is required that fuel debris solidifying mixed materials of fuels and in-vessel structures should be removed. The fuel debris is considered to have characteristics, such as indefinite shapes, porous bodies, multi-compositions, higher hardness, etc. from the knowledge in the U.S. and the Three Mile Island nuclear power plant. Laser lights are characterized by higher power density, local processability, remote controllabilitiy, etc. and can be performed thermal cutting and crushing-up for various materials which does not depend on fracture toughness. This report describes a research program and research activities in FY2012 aiming at developing removal system of fuel debris by the use of laser lights.
Watahiki, Shunsuke; Hanakawa, Hiroki; Imaizumi, Tomomi; Nagata, Hiroshi; Ide, Hiroshi; Komukai, Bunsaku; Kimura, Nobuaki; Miyauchi, Masaru; Ito, Masayasu; Nishikata, Kaori; et al.
JAEA-Technology 2013-021, 43 Pages, 2013/07
JAEA-Technology-2013-021.pdf:5.12MB
The number of research reactors in the world is decreasing because of their aging. On the other hand, the necessity of research reactor, which is used for human resources development, progress of the science and technology, industrial use and safety research is increasing for the countries which are planning to introduce the nuclear power plants. From above background, the Neutron Irradiation and Testing Reactor Center began to discuss a basic concept of Multipurpose Compact Research Reactor (MCRR) for education and training, etc., on 2010 to 2012. This activity is also expected to contribute to design tool improvement and human resource development in the center. In 2011, design study of reactor core, irradiation facilities with high versatility and practicality, and hot laboratory equipment for the production of Mo-99 was carried out. As the result of design study of reactor core, subcriticality and operation time of the reactor in consideration of an irradiation capsule, and about the transient response of the reactor to the reactivity disturbance during automatic control operation, it was possible to do automatic operation of MCRR, was confirmed. As the result of design study of irradiation facilities, it was confirmed that the implementation of an efficient mass production radioisotope Mo-99 can be expected. As the result of design study with hot laboratory facilities, Mo-99 production, RI export devised considered cell and facilities for exporting the specimens quickly was designed.
Noguchi, Hiroki; Kubo, Shinji; Iwatsuki, Jin; Onuki, Kaoru
JAEA-Technology 2013-020, 38 Pages, 2013/07
JAEA-Technology-2013-020.pdf:3.24MB
Hazardous substances such as sulfuric acid, sulfur dioxide and hydrogen iodide acid are employed in thermochemical Iodine-sulfur (IS) process. It is necessary to take safety measure against workers and external environments to study experimentally on IS process. Presently we have been conducting to verify the soundness of main components made of engineering material in actual corrosive condition. An integrity test apparatus for the components of sulfuric acid decomposition was set up. We will use the hazardous substances such as sulfuric acid and sulfur dioxide and perform the experiment in pressurized condition in this integrity test. Safety measures for test apparatus, operation and abnormal situation were considered prior to starting the test. This report summarized the consideration results for the safety measures on the integrity test apparatus for the components of sulfuric acid decomposition.
Kato, Yuko; Yabuki, Kentaro*; Okawachi, Yasushi
JAEA-Technology 2013-018, 118 Pages, 2013/07
JAEA-Technology-2013-018.pdf:3.73MB
The prototype fast breeder reactor MONJU resumed the system startup test (SST) on May 6th 2010 after fourteen years and five months shutdown since the sodium leakage of the secondary heat transport system in December 1995 and reached criticality on May 8th. Core confirmation test (CCT) is the first step of SST which consists of three steps, and finished on July 22nd after 78 days test. Control rod reactivity worth measurements were carried out in order to calibrate the reactivity worth of control rods and back-up rods. In addition, we also aimed at a basic data acquisition for the control rod reactivity worth calibration.
Harigae, Hitoshi; Takagi, Tsuyohiko; Hamano, Tomoharu; Nakamura, Shoichi; Oba, Toshio; Ebashi, Masaaki; Okuda, Eiichi; Kinoshita, Tomonobu
JAEA-Technology 2013-014, 150 Pages, 2013/07
JAEA-Technology-2013-014.pdf:24.38MB
In-Vessel Transfer Machine (IVTM) came off from the gripper claw in the Auxiliary Handling Machine (AHM) and fell at a height of approximately two meters during a withdrawal work of the IVTM in the Fast Breeder Reactor (FBR) Monju. The withdrawal work of IVTM from the reactor vessel by AHM was performed. The work, however, was suspended due to the excessive load alarm. To grasp the situation of the IVTM fall, observation of the machine was necessary. An interior observation and an exterior observation of the dropped IVTM were performed. As a result of these observations, the radially deformed lower end of the upper guide tube was observed at the connection part, and it was jammed in the fuel throat sleeve when the dropped IVTM was withdrawn. Based on this information, the IVTM could be safely withdrawn from the reactor vessel with the fuel throat sleeve.
Ito, Kimio; Ono, Takayuki; Ishimori, Yuu; Kawasaki, Satoru
JAEA-Review 2013-019, 20 Pages, 2013/07
JAEA-Review-2013-019.pdf:1.93MB
The Ningyo-toge Environmental Engineering Center of the Japan Atomic Energy Agency performs the environmental monitoring around the Ningyo-toge and the waste rock sites according to the agreements with local governments, Okayama and Tottori prefectures. Each prefectural committee on the environmental monitoring evaluates the monitoring data annually. This report summarized the results of the environmental monitoring in Tottori prefecture in the fiscal year 2011. The results show that the levels of the radiation doses and the radioactive concentrations in the environment were within natural variations, and the waste rock sites have been well maintained. The committee concluded that the environmental impacts from the sites were negligible.
Hikima, Ryoichi; Tanno, Takeo; Sanada, Hiroyuki; Matsui, Hiroya; Sato, Toshinori
JAEA-Review 2013-017, 52 Pages, 2013/07
JAEA-Review-2013-017.pdf:4.87MB
This report presents the following FY2011 activities undertaken to achieve the above goals. (1) 
Stress Measurements using Core-based Methods on the - 400 m Stage (2) Laboratory tests using Cores and Block samples (3) Literature survey for planning of 
experiments in Phase III (4) Application of specific energy for evaluation of rock mass properties (5) Study on estimation of rock stress with results of various measurements.
Takeyasu, Masanori
JAEA-Review 2013-016, 92 Pages, 2013/07
JAEA-Review-2013-016.pdf:3.65MB
The following studies were carried out with the purpose that the variation of environmental gamma-ray dose rate was determined due to radioactivity released from nuclear fuel cycle facility; Development of calculation code system (SIERRA-II) in order to determine in quasi-real time the variation of environmental gamma-ray dose rate due to the operation of reprocessing facility, examination for determining the variation of the dose rate during the operation using SIERRA-II, measurement of the concentration of 
Rn decay products in rainwater, and construction of the wet scavenging model for the atmospheric Rn decay products, determination of the variation of environmental gamma-ray dose rate due to the released 
Kr during rainfall. By these studies, it became clear that the developed SIERRA-II could determined the variation of environmental gamma-ray dose rate during the operation of reprocessing plant with practical accuracy.
Sato, Sohei; Yamamoto, Kazuya
JAEA-Review 2013-015, 89 Pages, 2013/07
JAEA-Review-2013-015.pdf:14.79MB
After the accident of TEPCO's Fukushima Dai-ichi Nuclear Power Station occurred on March 11, 2011, actions for controlling the accident and protective actions for the residents like evacuation were taken. In parallel with this, it has been developed to reform the nuclear regulatory systems and the emergency preparedness and response systems in Japan. Especially the Nuclear Regulation Authority's Nuclear Emergency Preparedness and Response Guidelines were adopted with the introducing the basic concepts and the criteria on the basis of the IAEA's safety standards and differed greatly from the prior guidelines. Thus the arrangement of emergency response systems, resources and the operational procedures will be developed complying with according to the guidelines in municipalities around the nuclear power station sites. This work attempts to provide a plain explanation as possible for the regional officials and emergency workers about the basic concepts of the new guidelines.
Committee for JAEA Internationalization Initiative
JAEA-Review 2013-014, 36 Pages, 2013/07
JAEA-Review-2013-014.pdf:1.58MB
In global circumstances surrounding nuclear energy, the role expected by the Japan Atomic Energy Agency (JAEA) is becoming increasingly important. JAEA has promoted an initiative for an international hub in order to increase the scientific competitiveness of Japan and make international contributions, by gathering excellent researchers from the entire world with the latest facilities. Also, JAEA has established the Committee for JAEA Internationalization Initiative, which will discuss issues such as environmental improvement for accepted foreigners, direction of efforts for internationalization initiative and strategies to improve the current situation. This report mentions the results of the committee's discussion including current issues for the initiative and recommendations for their solution, as well as issues to be discussed in order to enhance international awareness of JAEA staff.
Sakai, Ryutaro; Takeda, Seiji; Munakata, Masahiro; Kimura, Hideo
JAEA-Research 2013-006, 18 Pages, 2013/07
JAEA-Research-2013-006.pdf:2.77MB
In the safety assessment for a geological disposal of radioactive waste, it is important to establish validation methods for deep groundwater flow to estimate radionuclide migration to human environment through groundwater flow. Costal sedimentary rocks in our country provide dominant fossil water formed during sub-seabed sedimentation and chemical compositions of the water mixed with meteoric water and fossil water depend on the initial fossil water composition and groundwater flow conditions. Analytical study on the effects of groundwater flow on the mixed water quality as a indicator of its Cl/
O ratios was carried out in case of Horonobe district, where geochemical data is now being stored.
Fujita, Ichiro*; Eto, Motokuni*; Osaki, Hirotaka; Shibata, Taiju; Sumita, Junya; Konishi, Takashi; Yamaji, Masatoshi; Kunimoto, Eiji
JAEA-Research 2013-004, 20 Pages, 2013/07
JAEA-Research-2013-004.pdf:2.4MB
Graphite components in HTGR and VHTR may be oxidized by impurities in coolant helium-gas even at normal operation, as well as by air at air-ingress accident. In this study, by air-oxidation test at 520-900C, oxidation characteristics of IG-110 and IG-430 graphites, and associated decrease in compressive strength were examined. The following results were obtained. (1) The activation energy of the air-oxidation for IG-430 is 176 kJ/mol being almost same as for IG-110, though the oxidation rate for IG-430 is less than a half of that for IG-110. (2) There are correlations between density change and decrease in compressive strength. Decrease in strength is the largest in case that the oxidation temperature is lower than 600 C where the homogenous oxidation occurs. (3) In the process of oxidation, amorphous binder regions are predominantly oxidized. It suggests that peeling-off of cokes grains is necessary to be considered for oxidation weight loss, as well as gasification.
Fast Breeder Reactor Research and Development Center, Tsuruga Head Office
JAEA-Research 2013-001, 392 Pages, 2013/07
JAEA-Research-2013-001.pdf:29.81MB
Comprehensive safety assessments of MONJU taking into account the accident at Fukushima Dai-ichi Nuclear Power Station of Tokyo Electric Power Company have been performed based on the request of Nuclear and Industrial Safety Agency on July 22, 2011. The assessments focus on earthquake and tsunami as natural phenomena as well as the loss of all alternating current power sources (SBO: Station Blackout) and loss of the ultimate heat sink (LUHS) as the loss of safety functions. Assessed systems are the reactor, the ex-vessel storage tank (EVST) and the spent fuel pool (SFP). The safety margins are assessed by evaluating the scale of events that the plant could withstand against the events beyond design basis without significant damage to the fuel. The ability of natural circulation in primary cooling systems and natural convection of air in the auxiliary air cooling system are taken into account in the assessment for the reactor and the EVST in SBO.
Karino, Tomoyuki; Takeuchi, Ryuji
JAEA-Data/Code 2013-007, 100 Pages, 2013/07
JAEA-Data-Code-2013-007.pdf:7.78MB
JAEA-Data-Code-2013-007-appendix(CD-ROM).zip:507.56MB
Mizunami Underground Research Laboratory (MIU) Project has three overlapping phases: Surface-based investigation phase (Phase I), Construction phase (Phase II), and Operation phase (Phase III), with a total duration of 20 years. The main goals of the MIU Project from Phase I through to Phase III are: to establish techniques for investigation, analysis and assessment of the deep geological environment, and to develop a range of engineering for deep underground application. Currently, the project is being carried out under the Phase II. One of the Phase II goals is set to develop and revise models of the geological environment using the investigation results obtained during excavation, and determine and assess the changes in the geological environment in response to excavation. The long term hydro-pressure monitoring has been continued to achieve the Phase II goals. This paper describes the results of the long term hydro-pressure monitoring from April, 2011 to March, 2012.
Suzuki, Motoe; Saito, Hiroaki*; Udagawa, Yutaka; Nagase, Fumihisa
JAEA-Data/Code 2013-005, 382 Pages, 2013/07
JAEA-Data-Code-2013-005.pdf:6.4MB
A light water reactor fuel analysis code FEMAXI-7 has been developed for the purpose of analyzing the fuel behavior in both normal conditions and anticipated transient conditions. This code is an advanced version which has been produced by incorporating the former version FEMAXI-6 with numerous functional improvements and extensions. In FEMAXI-7, many new models have been added and parameters have been clearly arranged. Also, to facilitate effective maintenance and accessibility of the code, modularization of subroutines and functions have been attained, and quality comment descriptions of variables or physical quantities have been incorporated in the source code. With these advancements, the FEMAXI-7 code has been upgraded to a versatile analytical tool for high burnup fuel behavior analyses. This report describes in detail the design, basic theory and structure, models and numerical method, and improvements and extensions.
Sato, Hiroyuki; Ohashi, Hirofumi; Tazawa, Yujiro; Imai, Yoshiyuki; Nakagawa, Shigeaki; Tachibana, Yukio; Kunitomi, Kazuhiko
JAEA-Technology 2013-015, 68 Pages, 2013/06
JAEA-Technology-2013-015.pdf:2.22MB
In present study, requirements in order to design, construct and operate hydrogen production plants coupled to HTGRs under conventional chemical plant standards are identified. In addition, design considerations for safety design of nuclear facility are suggested. Furthermore, feasibility of proposed safety design and design considerations are clarified.
Takemoto, Noriyuki; Sugaya, Naoto; Otsuka, Kaoru; Hanakawa, Hiroki; Onuma, Yuichi; Hosokawa, Jinsaku; Hori, Naohiko; Kaminaga, Masanori; Tamura, Kazuo*; Hotta, Koji*; et al.
JAEA-Technology 2013-013, 44 Pages, 2013/06
JAEA-Technology-2013-013.pdf:4.42MB
A real-time simulator for operating both a reactor and irradiation facilities of a materials testing reactor, Simulator of Materials Testing Reactors, was developed for understanding reactor behavior and upskilling in order to utilize for a nuclear human resource development and to promote partnership with developing countries which have a plan to introduce nuclear power plant. The simulator is designed based on the JMTR (Japan Materials Testing Reactor) and it simulates operation, irradiation tests and various kinds of anticipated operational transients and accident conditions caused by the reactor and irradiation facilities. The development of the simulator was sponsored by the Japanese government as one of the specialized projects of advanced research infrastructure in order to promote basic as well as applied researches. This report summarizes the simulation model, hardware specification and operation procedure of the simulator.
Mizuno, Tomoyasu; Koyama, Shinichi; Kaito, Takeji; Uwaba, Tomoyuki; Tanaka, Kenya
JAEA-Technology 2013-012, 13 Pages, 2013/06
JAEA-Technology-2013-012.pdf:2.34MB
A mixed oxide fuel pin concept with annular pellets and an ODS cladding is a possible driver fuel for commercialized Sodium-cooled fast reactor (SFR) core. This fuel concept was considered with low breeding ratio as a standard, break-even breeding cores and cores with high breeding ratio (high breeding cores). Some calculations of fuel pin irradiation performance of (U,Pu) oxide fuel and minor actinides bearing oxide fuel were conducted by a fuel performance analysis code CEDAR developed in JAEA to understand the steady state irradiation behavior of fuel pins for the cores with high breeding ratio. The fuel temperature profiles, fuel and cladding deformation profiles, and radial temperature distribution at end of life (EOL) were evaluated. Those results show that the MOX fuel pin having the specifications and irradiation conditions used in this investigation would be irradiated moderately up to approximately 250 GWd/t with well integrity.
Mizuno, Tomoyasu; Koyama, Shinichi; Kaito, Takeji; Uwaba, Tomoyuki; Tanaka, Kenya
JAEA-Technology 2013-011, 10 Pages, 2013/06
JAEA-Technology-2013-011.pdf:2.02MB
In order to evaluate integrity limiting parameters of fuel pins during fast reactor core transient events, such as fuel center line temperature and cladding maximum temperature, the fast reactor fuel pin performance code CEDAR was used for calculation. The temperature histories of fuel pins during a loss of flow (LOF) type transient events was calculated based on Ross & Stoute type gap conductance model and constant gap conductance model used in a core transient calculation code like HIPRAC. The calculated maximum temperatures of cladding and adjacent coolant channel were lower in the case with Ross & Stoute type model than in the case of constant gap conductance model due to the dynamic change of gap conductance of the former case. It is indicated that core transient calculations with constant gap conductance give conservative cladding and coolant temperatures than that with Ross & Stoute type gap conductance model which is thought to be realistic.
Mizuno, Tomoyasu; Koyama, Shinichi; Kaito, Takeji; Uwaba, Tomoyuki; Tanaka, Kenya
JAEA-Technology 2013-010, 17 Pages, 2013/06
JAEA-Technology-2013-010.pdf:2.46MB
Metallic fuel, U-Pu(TRU)-Zr is a fuel candidate for Sodium-cooled fast reactor (SFR) selected as a possible promising future nuclear reactor system in Generation-IV international forum (GIF). Design studies were performed in the Japanese feasibility study on commercialized fast reactor cycle system, and the irradiation behavior of metallic fuel is under investigation through analytical fuel performance code calculations with preliminary analytical models. Some calculations of U-Pu(TRU)-Zr fuel irradiation performance were conducted by a simplified calculation grogram developed in JAEA. Axial profile of fuel pin centerline temperature calculated by using effective fuel thermal conductivity where sodium ingress into fuel was considered fits well with actual fuel micro structures after the irradiation. The effective fuel thermal conductivity with sodium ingress is suitable for the irradiation behavior investigation.
Mizuno, Tomoyasu; Koyama, Shinichi; Kaito, Takeji; Uwaba, Tomoyuki; Tanaka, Kenya
JAEA-Technology 2013-009, 12 Pages, 2013/06
JAEA-Technology-2013-009.pdf:1.3MB
Metallic fuel, U-Pu(TRU)-Zr is a fuel candidate for Sodium-cooled fast reactor (SFR) selected as a possible promising future nuclear reactor system in Generation-IV international forum (GIF). Design studies were performed in the Japanese feasibility study on commercialized fast reactor cycle system, and the irradiation behavior of metallic fuel is under investigation through analytical fuel performance code calculations with preliminary analytical models. As fuel temperature analyses at overpower events are also major interest, some calculations of U-Pu(TRU)-Zr fuel irradiation performance were conducted by a simplified calculation program developed in JAEA. The calculated fuel temperature at the maximum power of overpower events, 110-120% of steady state power, was around 1100K in maxim. It is clear that this temperature was low enough to avoid fuel melting in the event.
Nagata, Hiroshi; Inoue, Shuichi; Yamaura, Takayuki; Tsuchiya, Kunihiko; Nagao, Yoshiharu
JAEA-Technology 2013-008, 30 Pages, 2013/06
JAEA-Technology-2013-008.pdf:2.24MB
Refurbishment of JMTR was completed in FY2010. For damage caused by the 2011 off the Pacific coast of Tohoku Earthquake, the repair of facilities was completed in October 2012. Currently, the JMTR is in preparation for restart. Irradiation tests for LWRs safety research, science and technologies, etc. are expected after the JMTR restart. On the other hand, aiming at the attractive irradiation testing reactor, the usability improvement has been discussed. As a part of the usability improvement, shortening of turnaround time was discussed focusing on the fabrication process of irradiation capsules, where the fabrication process was analyzed and reviewed by referring a trial fabrication of the mockup capsule. As a result, it was found that the turnaround time can be shortened 2 months from fabrication period of 6 months with communize of irradiation capsule parts, application of ready-made instrumentation including the sheath heater, reconsideration of inspection process, etc.
Hirayama, Takashi; Kannari, Masaaki
JAEA-Technology 2013-003, 33 Pages, 2013/06
JAEA-Technology-2013-003.pdf:1.95MB
The optimization of the JAEA network system has been promoted in accordance with the optimization plan which has the fundamental principles of ensuring its dependability, information security and usability. In respect to ensuring the dependability, we addressed to (a) the reduction of both trouble probability and recovery time, and (b) an execution of the business continuity plan in time of large-scale earthquake. For the latter, we installed an e-mail backup server and an alternate connection to the internet in Kansai Photon Science Institute (Kizu-area) based on lesson learned from the experience of the Tohoku earthquake on March 11th, 2011. In addition, we introduced a backup system for data and servers of other main IT infrastructure services. This report documents the configuration and operation of the backup system.
Ashida, Takashi; Miyamoto, Kazuyuki; Okazaki, Yoshihiro*; Ito, Hideaki
JAEA-Technology 2012-047, 106 Pages, 2013/06
JAEA-Technology-2012-047.pdf:11.09MBJAEA-Technology-2012-047-appendix(CD-ROM).zip:15.46MB
In the experimental fast reactor Joyo, failure of disconnecting the irradiation test subassembly MARICO-2 (Material Testing Irradiation Rig with Temperature Control) was occurred and top of the MARICO-2 test subassembly was bent onto the in-vessel storage rack. As a result of this incident, the operation area of rotating plug for the fuel exchange in Joyo is limited. The replacement of the damaged UCS and retrieving the bent MARICO-2 are required to Joyo restoration. This report describes about investigations and some tests to know the status of MARICO-2 test subassembly and the optimized detail design of retrieval device reflecting those results.
Ishikawa, Masashi
JAEA-Review 2013-013, 51 Pages, 2013/06
JAEA-Review-2013-013.pdf:4.73MB
Japan Atomic Energy Agency has provided the twenty-thousand technical reports on the internet to publish results of research and development activities in detail. In technical reports, detailed results, experimental data, findings etc. are recorded. Technical report system is effective for communication among scientists and engineers for research development in big science like nuclear research. The number of download of technical reports is over 4.7 million in a year. Recently, scientist and engineers engaged in research and development projects are inclined to submit papers to journals which have high impact factor. But technical reports are more useful for carrying research results of big projects than journal articles. It is also useful for knowledge management to transfer results and achievements to the following generation. To improve the technical report system to meet the needs of scientists and engineers and assisting the knowledge management is proposed.
Nuclear Science Research Institute
JAEA-Review 2013-012, 186 Pages, 2013/06
JAEA-Review-2013-012.pdf:9.83MB
Nuclear Science Research Institute (NSRI) is composed of Planning and Coordination Office and seven departments such as Department of Operational Safety Administration, Department of Radiation Protection, Department of Research Reactor and Tandem Accelerator, Department of Hot Laboratories and Facilities, Department of Criticality and Fuel Cycle Research Facilities, Department of Decommissioning and Waste Management, and Engineering Services Department. This annual report of JFY 2011 summarizes the activities of NSRI, the R&D activities of the Research and Development Directorates and human resources development at site, and is expected to be referred to and utilized by R&D departments and project promotion sectors at NSRI site for the enhancement of their own research and management activities to attain their goals according to "Middle-term Plan" successfully and effectively.
Department of Decommissioning and Waste Management
JAEA-Review 2013-010, 107 Pages, 2013/06
JAEA-Review-2013-010.pdf:4.43MB
This report describes the activities of Department of Decommissioning and Waste Management (DDWM) in Nuclear Science Research Institute (NSRI) in the period from April 1, 2009 to March 31, 2010. The report covers organization and missions of DDWM, operation and maintenance of facilities which belong to DDWM, treatment and management of radioactive wastes, decommissioning activities, and related research and development activities which were conducted by DDWM.
Sumiya, Shuichi; Watanabe, Hitoshi; Nakano, Masanao; Takeyasu, Masanori; Nakada, Akira; Fujita, Hiroki; Isozaki, Tokuju; Morisawa, Masato; Mizutani, Tomoko; Nagaoka, Mika; et al.
JAEA-Review 2013-009, 195 Pages, 2013/06
JAEA-Review-2013-009.pdf:3.35MB
Environmental radiation monitoring around the Tokai Reprocessing Plant has been performed by the Nuclear Fuel Cycle Engineering Laboratories, based on "Safety Regulations for the Reprocessing Plant of Japan Atomic Energy Agency, Chapter IV - Environmental Monitoring". This annual report presents the results of the environmental monitoring and the dose estimation to the hypothetical inhabitant due to the radioactivity discharged from the plant to the atmosphere and the sea during April 2011 to March 2012. In this report, some data include the influence of the accidental release from the Fukushima Daiichi Nuclear Power Plant on Tokyo Electric Power Co. in March 2011.
Ishimori, Yuu; Sakoda, Akihiro; Tanaka, Hiroshi; Mitsunobu, Fumihiro*; Yamaoka, Kiyonori*; Kataoka, Takahiro*; Yamato, Keiko*; Nishiyama, Yuichi*
JAEA-Research 2013-005, 60 Pages, 2013/06
JAEA-Research-2013-005.pdf:4.49MB
Okayama University and the Japan Atomic Energy Agency (JAEA) have carried out the collaborative study of physiological effects of inhaled radon for the low-dose range. From 2007 to 2011, the following results were obtained. (1) Literature on effects of radon for the low-dose range was surveyed to determine the present tasks. (2) The first Japanese large-scale facility was developed for radon inhalation experiments with small animals. (3) Relationships between radon concentration and inhalation time were widely examined to understand the change in antioxidative functions due to radon, which are the most basic parameters. (4) Inhibitory effects of radon on oxidative damages were observed using model mice with reactive oxygen- or free radical-related diseases like alcohol-induced oxidative damages and type I diabetes. (5) In order to discuss biological responses quantitatively following radon inhalation, the biokinetics of inhaled radon was examined and the model for calculation of absorbed doses for organs and tissues was obtained.
Yamamoto, Nobuyuki; Iwano, Keita*; Namikawa, Tadashi*; Morikawa, Seiji*; Seno, Shoji*; Tabei, Kazuto*; Toida, Masaru*; Yokota, Hideharu
JAEA-Research 2013-003, 252 Pages, 2013/06
JAEA-Research-2013-003.pdf:77.85MB
This study reconsiders rock's mechanical and hydrological parameters based on additional data given in this year, and conducts the mechanical-hydrological analysis using the Micromechanics-Based Continuum (MBC) model which can consider the behavior of fracture. The acquired analysis results are compared with actual test data such as drift convergence and hydraulic pressure around the drift. Then, following knowledge is obtained.
Yokota, Hideharu; Amano, Kenji; Maekawa, Keisuke; Kunimaru, Takanori; Naemura, Yumi*; Ijiri, Yuji*; Motoshima, Takayuki*; Suzuki, Shunichi*; Teshima, Kazufumi*
JAEA-Research 2013-002, 281 Pages, 2013/06
JAEA-Research-2013-002.pdf:13.03MB
To evaluate permeable heterogeneity in a fracture and scale effects which are problems to be solved based on the mass transportation data of fractures in hostrock, a number of tracer tests are simulated in a fictitious single plate fracture generated on computer in this study. And the transport parameters, e.g. longitudinal dispersion length, true velocity and dilution rate, are identified by fitting one- and two-dimensional models to the breakthrough curves obtained from the simulations in order to investigate the applicability of these models to the evaluation of tracer test. As a result, one-dimensional model yields larger longitudinal dispersion length than two-dimensional model in the both cases of homogeneous and heterogeneous hydraulic conductivity fields of the fictitious fracture. And, the longitudinal dispersion length identified from a tracer test is smaller and/or larger than the macroscopic longitudinal dispersion length identified from whole fracture. It is clarified that these are occurred by shorter or longer distance between boreholes compare to the correlation length of geostatistical heterogeneity of fictitious fracture.
Yamada, Junya; Seya, Natsumi; Haba, Risa; Muto, Yasunobu; Numari, Hideyuki*; Sato, Naomitsu*; Nemoto, Koji*; Takasaki, Hiroichi*; Shimizu, Takehiko; Takasaki, Koji
JAEA-Data/Code 2013-006, 100 Pages, 2013/06
JAEA-Data-Code-2013-006.pdf:12.04MB
This report presents the results of emergency radiation monitoring, including ambient -ray dose rate, atmospheric radioactivity, meteorological observation and estimation of internal exposure resulting from the accident at the Fukushima Daiichi Nuclear Power Plant triggered by the earthquake off the pacific coast of Tohoku on 11th March 2011, conducted by Oarai Research and Development Center (ORDC), Japan Atomic Energy Agency (JAEA) from March to May, 2011. ORDC is located in the central part of Ibaraki prefecture and approximately 130 km southwest of the Fukushima Daiichi Nuclear Power Plant. From around 15th to 21st March, 2011, the ambient -ray dose rate increased and many radioactive nuclides were detected in the atmosphere.
Yuguchi, Takashi; Ishibashi, Masayuki; Morikawa, Keita; Kunimaru, Takanori
JAEA-Data/Code 2013-004, 38 Pages, 2013/06
JAEA-Data-Code-2013-004.pdf:15.49MB
Tono Geoscientific Research Unit of Japan Atomic Energy Agency (JAEA) is carrying out the Underground Research Laboratory Project, which is a scientific study revealing the deep geological environment as a basis of research and development for geological disposal of high level radioactive wastes. Nowadays, the project is under the Phase II and Phase III. In the 2011 fiscal year, rock specimens accompanied with grout-filling fracture were collected from -300m Access / Research Gallery of the Mizunami Underground Research Laboratory Construction Site, which were processed into thin sections, and then observed through polarizing microscopy. The grout-filling fracture can be identified as groundwater flow path and thus mass transfer pathway. Investigation methodology and petrological / mineralogical data are basic information for the study of mass transfer in Phase III. This paper presents sampling procedure of rock specimen accompanied with grout-filling fracture and compiles the results of these petrographical observations and analyses.
Sato, Seiji; Takeda, Masaki; Takeuchi, Ryuji
JAEA-Data/Code 2013-003, 19 Pages, 2013/06
JAEA-Data-Code-2013-003.pdf:2.36MBJAEA-Data-Code-2013-003-appendix(CD-ROM).zip:15.46MB
The Tono Geoscientific Research Unit of Japan Atomic Energy Agency (JAEA) has carried out the subsurface water balance observation in order to estimate groundwater recharge rate for setting the upper boundary conditions on groundwater flow simulation and to obtain data for the calibration of the hydrogeological model. In the subsurface water balance observations, rainfall data and river flow rate have been observed in the Garaishi river and the Hiyoshi river watersheds. The missed data and data error in the monitoring data during the fiscal year 2010 were complemented or corrected, and these data were compiled in data set. Both of the observation data and compiled data are included into the data set, and the data set is recorded on CD-ROM.
Hiratsuka, Hajime; Hatano, Toshihisa; Abe, Tetsuya
JAEA-Testing 2013-001, 42 Pages, 2013/05
JAEA-Testing-2013-001.pdf:7.71MBJAEA-Testing-2013-001(errata).pdf:0.08MB
The Breath-Mass was put in practical use in the development of the gas analysis technology with quadrupole mass specrometer. Features of the Breath-Mass are measurement at short time, high sensitivity and reproducibility. Moreover, on-site measurement was added to features and application of the Breath-Mass in various fields was aimed at. In development of application, lectures of operation with the instrument were required. This report was summarized as operation manual whose contents ware handling, measurement and maintenance.
Mizuno, Tomoyasu; Koyama, Shinichi; Kaito, Takeji; Uwaba, Tomoyuki; Tanaka, Kenya
JAEA-Technology 2013-007, 17 Pages, 2013/05
JAEA-Technology-2013-007.pdf:1.69MB
As a swelling resistant austenitic steel, PNC316, is candidate cladding tube material of the first core of demonstration Sodium-cooled fast reactor (SFR). The irradiation behavior of an annular MOX fuel pin with (U,Pu) oxide fuel contained in PNC 316 cladding was evaluated by a fuel performance analysis code CEDAR developed in JAEA. The fuel temperature profiles, fuel and cladding deformation profiles, and radial temperature distribution at EOL were evaluated. Those results show that the fuel pin keeps its integrity at least up to 100 GWd/t of peak burnup.
Mizuno, Tomoyasu; Koyama, Shinichi; Kaito, Takeji; Uwaba, Tomoyuki; Tanaka, Kenya
JAEA-Technology 2013-006, 17 Pages, 2013/05
JAEA-Technology-2013-006.pdf:1.72MB
As a fuel concept for commercialized Sodium-cooled fast reactor (SFR) system, minor actinides (MA) bearing oxide fuel with oxide dispersion strengthened martensitic steel (ODS) cladding was considered under homogeneous TRU recycling strategy. The MA content is calculated to be around 5% of heavy metal in case of trans-uranium (TRU) feed from light water reactor (LWR) spent fuel during the transition phase from LWR to fast reactor era. The fuel temperature profiles, fuel and cladding deformation profiles, and radial temperature distribution at end of life (EOL) were evaluated by fuel performance analytical code CEDAR developed in JAEA to investigate the irradiation behavior of annular MOX fuel pins with (U,Pu) oxide fuel and Am bearing oxide fuel under a high burnup condition. Also, the profiles of pressure on the cladding inner surface and the cladding deformation after irradiation were evaluated.
Mizuno, Tomoyasu; Koyama, Shinichi; Kaito, Takeji; Uwaba, Tomoyuki; Tanaka, Kenya
JAEA-Technology 2013-005, 17 Pages, 2013/05
JAEA-Technology-2013-005.pdf:1.7MB
A mixed oxide fuel pin concept with annular pellets and an oxide dispersion strengthened martensitic steel (ODS) cladding is a possible driver fuel for commercialized Sodium-cooled fast reactor (SFR) core. The capability of annular MOX fuel pins with (U,Pu) oxide fuel and Am bearing oxide fuel under a high burnup condition was evaluated by a fuel performance analysis code CEDAR developed in JAEA. The fuel temperature profiles, fuel and cladding deformation profiles, and radial temperature distribution at EOL were evaluated. Those results show that the fuel pin had enough safety margin to fuel melting under the irradiation. Also, the profiles of pressure on the cladding inner surface and the cladding deformation after irradiation were evaluated. Those results show that the gap of the fuel pin at fabrication had enough width not to occur the considerable fuel-cladding mechanical interaction (FCMI).
Mizuno, Tomoyasu; Koyama, Shinichi; Kaito, Takeji; Uwaba, Tomoyuki; Tanaka, Kenya
JAEA-Technology 2013-004, 16 Pages, 2013/05
JAEA-Technology-2013-004.pdf:1.52MB
In order to be an alternative concept to the conventional concept consisting of mixed oxide (MOX) fuel, Metallic fuel, U-Pu(TRU)-Zr metallic fuel slug and ODS cladding were considered for Sodium-cooled fast reactor (SFR) cycle system. The capability of the U-Pu(TRU)-Zr metallic fuel with ODS cladding under a high burnup condition was calculated and conducted by a simplified calculation grogram developed in JAEA. The fuel temperature profiles, gap width profiles, and radial temperature distribution at EOL were evaluated. Those results show that the fuel pin had enough safety margin to fuel melting under the irradiation. Evaluation of the profiles of plenum gas pressure and the cladding deformation after irradiation shows that the fuel pin had enough plenum volume not to cause considerable cladding deformations by plenum gas pressure. In case of 0.4% Am bearing fuel, calculation result shows that fuel centerline temperature becomes high, but increase from U-Pu-Zr fuel is insignificant.
Rai, D.*; Yui, Mikazu
JAEA-Technology 2013-002, 35 Pages, 2013/05
JAEA-Technology-2013-002.pdf:1.18MB
The solubility method is one of the most powerful tools to obtain reliable thermodynamic data for (1) solubility products of discrete solids and double salts, (2) complexation constants for various ligands, (3) development of data in a wide range of pH values, (4) evaluation of data for metals that form very insoluble solids (e.g. tetravalent actinides), (5) determining solubility-controlling solids in defferent types of wastes and (6) elevated temperature for redox sensitive systems. This document is focused on describing various aspects of obtaining thermodynamic data using the solubility method. This manuscript deals with various aspects of conducting solubility studies, including selecting the study topic, modeling to define important variables, selecting the range of variables and experimental parameters, anticipating results, general equipment requirements, conducting experiments, and interpreting experimental data.
Hamada, Shozo
JAEA-Review 2013-008, 107 Pages, 2013/05
JAEA-Review-2013-008.pdf:30.09MB
Since the Headquarter of the International Science and Technology Center (ISTC) was established in Moscow, Russian Federation in 1994, Japan Atomic Energy Agency (JAEA), which includes both Japan Atomic Energy Research Institute and Japan has been made various, considerable contributions as well as participation in partner projects in ISTC activities. By the way, the Russian Federation Party, made the statement that the Russian Federation would withdraw from ISTC until the end of 2015 in the 52nd Government Board in held Moscow, 9 December 2010. So that the Government Board has been discussing about the continuation and /or the establishment of a new organization for ISTC. This time is considered as a transition period of ISTC and it is summarized that the collaborations, contributions of JAEA and outcomes from them for ISTC activities in this report.
Matsuo, Yoichiro; Sasaki, Shinji
JAEA-Review 2013-007, 46 Pages, 2013/05
JAEA-Review-2013-007.pdf:4.68MB
Radioactive corrosion products (CP) are main cause of personal radiation exposure during maintenance without fuel failure in FBR plants. The most important CP species are 
Mn and 
Co. The deposited radioactive CP cause radiation fields near the piping and components. Then, the deposited radioactive CP contributes to the radiation exposure of the plant-worker. In this review, firstly, collects knowledge about CP transfer behavior in the fast reactor and analyzes it and organize essence of the CP transfer behavior. Secondly, existing method to parse CP transfer behavior is investigated and extracts the issues and discusses it about the solution of those issues. Finally, about a specific example of the improvement based on the solution, a recent trend is investigated and describes evaluated content.
Sumiya, Shuichi; Watanabe, Hitoshi; Miyagawa, Naoto; Nakano, Masanao; Fujita, Hiroki; Kono, Takahiko; Hiyama, Yoshinori; Yoshii, Hideki*; Otani, Kazunori*; Goto, Ichiro*; et al.
JAEA-Review 2013-005, 116 Pages, 2013/05
JAEA-Review-2013-005.pdf:9.69MB
Based on the regulations (the safety regulation of Tokai reprocessing plant, the safety regulation of nuclear fuel material usage facilities, the radiation safety rule, the regulation about prevention from radiation hazards due to radioisotopes, which are related with the nuclear regulatory acts, and the local agreement concerning with safety and environment conservation around nuclear facilities, the water pollution control law, and byelaw of Ibaraki prefecture), this report describes the effluent control results of liquid waste discharged from the JAEA's Nuclear Fuel Cycle Engineering Laboratories in the fiscal year 2011, from 1st April 2011 to 31st March 2012. In this period, the concentrations and the quantities of the radioactivity in liquid waste discharged from the reprocessing plant, the plutonium fuel fabrication facilities, and the other facilities were much lower than the authorized limits of the above regulations.
Ohgama, Kazuya; Ando, Yoko; Yamaguchi, Mika; Ikuta, Yuko; Shinohara, Nobuo; Murakami, Hiroyuki; Yamashita, Kiyonobu; Uesaka, Mitsuru*; Demachi, Kazuyuki*; Komiyama, Ryoichi*; et al.
JAEA-Review 2013-004, 76 Pages, 2013/05
JAEA-Review-2013-004.pdf:13.53MB
JAEA together with the Japan Nuclear Human Resource Development Network (JN-HRD Net), the University of Tokyo (UT) and the Japan Atomic Industrial Forum (JAIF) cohosted the IAEA-Nuclear Energy Management School in Tokai Village, aiming that Japan will be the center of nuclear HRD in the Asian region. In the school, not only lectures by IAEA experts, but also lectures by Japanese experts and technical visits were included for foreign participants. The school contributed to the internationalization of Japanese young professionals, development of nuclear human resource of other countries, and enhancement of cooperation between IAEA and Japan. Additionally, collaborative relationship within JN-HRD Net was strengthened by the school. In this report, findings obtained during the preparatory work and the school period are reported for future international nuclear HRD activities in Japan.
Nagane, Satoru; Kyoya, Masahiko; Matsuno, Satoru; Hatanaka, Koki; Tobinai, Kazuhito; Hori, Hiroshi; Kitahara, Katsumi; Yoshikawa, Seiji
JAEA-Review 2013-003, 56 Pages, 2013/05
JAEA-Review-2013-003.pdf:9.35MB
Nuclear Facilities Management Section implements the operation, maintenance and decommissioning of the first nuclear ship MUTSU and the operation and maintenance of the liquid waste facility and the solid waste facility where a small amount of nuclear fuel is used. This is the report on the operations of the Nuclear Facilities Management Section for FY 2010 and FY 2011.
Karino, Tomoyuki; Takeuchi, Ryuji
JAEA-Data/Code 2013-002, 45 Pages, 2013/05
JAEA-Data-Code-2013-002.pdf:7.73MBJAEA-Data-Code-2013-002-appendix(CD-ROM).zip:173.68MB
Tono Regional Hydrogeological Study (RHS) Project is a one of the geoscientific research programme at Tono Geoscience Center (TGC). This project started since April, 1992 and main investigations were finished to March 2004. Since 2005, hydrogeological and hydrochemical monitoring are continued by the existing monitoring system. This paper describes the results of the long term hydro-pressure monitoring from April, 2011 to March, 2012.
Omori, Kazuaki; Shingu, Shinya; Hagiwara, Hiroki; Masuda, Kaoru*; Iizuka, Masatoshi*; Inui, Michiharu*; Iwatsuki, Teruki
JAEA-Data/Code 2013-001, 330 Pages, 2013/05
JAEA-Data-Code-2013-001.pdf:23.85MB
Japan Atomic Energy Agency has been investigated the groundwater chemistry on excavating the underground facilities as part of the Mizunami Underground Research Laboratory (MIU) Project at Mizunami, Gifu, Japan. This report compiles data of the groundwater chemistry obtained at MIU in the fiscal year 2011. In terms of ensuring traceability of data, basic information (e.g. sampling location, sampling date, sampling method, analytical method) and methodology for quality control is described.
Department of Research Reactor and Tandem Accelerator
JAEA-Review 2013-002, 98 Pages, 2013/04
JAEA-Review-2013-002.pdf:5.02MB
The JAEA-Tokai tandem accelerator complex has been used in various research fields such as nuclear science and material science by researchers not only of JAEA but also from universities, research institutes and industrial companies. This annual report covers developments of accelerators and research activities carried out using the tandem accelerator, superconducting booster, and radioactive nuclear beam accelerator, from April 1, 2011 to March 31, 2012. Twenty-seven summary reports were categorized into seven research/development fields: (1) accelerator operation and development (2) nuclear structure (3) nuclear reaction (4) nuclear chemistry (5) nuclear theory (6) atomic physics and solid state physics (7) radiation effects in materials. This report also lists publications, meetings, personnel, committee members, cooperative researches and common use programs.
Ono, Masato; Goto, Minoru; Shinohara, Masanori; Nojiri, Naoki; Tochio, Daisuke; Shimazaki, Yosuke; Yanagi, Shunki
JAEA-Technology 2013-001, 35 Pages, 2013/03
JAEA-Technology-2013-001.pdf:6.04MB
The temperature coefficient measurements of the HTTR have been carried out. In the beginning of the operation, temperature coefficients at the reactor power of 30 kW and 9 MW were obtained through 1999 to 2000. The operation days of the HTTR fuel reached 375 Effective Full Power Days (EFPD), which is over a half of design operation days (660 EFPD). The temperature coefficient measurements were conducted at the same power levels of 30 kW and 9 MW to evaluate burnup effect. Also, to measure temperature coefficient in high accuracy, technique of core temperature control and technique of core temperature homogenization were established.
Yamawaki, Hiroyuki; Torikai, Kazuyoshi; Arimoto, Yosuke*
JAEA-Technology 2012-049, 64 Pages, 2013/03
JAEA-Technology-2012-049.pdf:8.28MB
An agreement was concluded among MEXT (Ministry of Education, Culture, Sports, Science and Technology), Tottori Prefecture, Misasa Town and JAEA (Japan Atomic Energy Agency) on May 31st, 2006, aiming at resolving the problem due to the waste soil deposited at JAEA's Katamo Waste Soil Yards. Based on the agreement, a plant was constructed in the land JAEA rented form the Misasa Town to manufacture bricks from the micture of the waste soil and additives such as cement. The plant manufactured about 1.45 million bricks during the period of operation between April 28th, 2008, and December 13th, 2010. This report summarizes the outline of the brick manufacturing plant, the results of trial and pilot operations and the performance of full-scale operation.
Ohara, Yoshiyuki; Naganuma, Masaki; Nohiro, Tetsuya*; Yoshida, Kimikazu*; Makita, Akinori*; Sakate, Mitsuo*; Irisawa, Takumi*; Murashita, Tatsuya*
JAEA-Technology 2012-048, 39 Pages, 2013/03
JAEA-Technology-2012-048.pdf:5.1MB
In Japan Atomic Energy Agency Ningyo-Toge Environmental Engineering Center, exploration for uranium and technical development of uranium refining, conversion and enrichment which are the front end of a nuclear fuel cycle have been performed since 1955. By these research and development, about 15000 radioactive waste (200 liter drum) has occurred by now. The analytical and measurement technique of the amount of uranium which are included in radioactive waste drum were very an inexperienced in those days. Therefore, measurement strict till 2002 was not able to be started. Such a situation as this, we introduced "Q2 low-level-waste drum measuring system" which is a bulk measuring method of the passive ray using a NaI scintillation detector in 2002. As a result, the total amount of uranium in a waste drum was estimated as about 20 tons.
Tazaki, Makiko; Yamamura, Tsukasa; Suzuki, Mitsutoshi; Kuno, Yusuke; Mochiji, Toshiro
JAEA-Review 2013-001, 76 Pages, 2013/03
JAEA-Review-2013-001.pdf:8.59MB
The Japan Atomic Energy Agency held "International Forum on Nuclear Energy, Nuclear Non-proliferation and Nuclear Security; Measures to ensure nuclear non-proliferation and nuclear security for the back end of nuclear fuel cycle and regional cooperation in Asia" on 12 and 13 December 2012. In the forum, 5 keynote speakers respectively explained their views and efforts regarding challenges for peaceful use of nuclear energy and nuclear non-proliferation. In two panel discussions, entitled "Measures to ensure nuclear non-proliferation and nuclear security of nuclear fuel cycle back end" and "Measures to ensure nuclear non-proliferation and nuclear security for nuclear energy use in the Asian region and a multilateral cooperative framework", active discussions were initiated among panelists. This report includes abstracts of keynote speeches, summaries of two panel discussions and materials of the presentations in the forum.
Department of Hot Laboratories and Facilities
JAEA-Review 2012-056, 100 Pages, 2013/03
JAEA-Review-2012-056.pdf:14.89MB
This report describes the operation and management of eleven facilities under the Department of Hot Laboratories and Facilities during a fiscal year of 2011. In Reactor Fuel Examination Facility, various post-irradiation examinations were performed regarding "the advanced light water reactor fuel performance and safety research program", and "the development of vessel material for spallation target of neutron scattering facility". In Waste Safety Testing Facility, various examinations were performed regarding the irradiation assisted stress corrosion cracking behavior for nuclear power plant materials, corrosion properties for stainless steel against the dense uranyl solution, and properties of minor actinide bearing fuels. Since 2010, chemical analyses have been made by request at No.4 Research Laboratory, including maintenance of shared instruments and the technical assistance. In addition, the facility management was carried out of Research Hot Laboratory, No.1 Plutonium Laboratory, No.2 Research Laboratory, Analytical Chemistry Laboratory, Uranium Enrichment Laboratory, Simulation Test for Environmental Radionuclide Migration, Clean Laboratory for Environmental Analysis and Research, and Fuel Storage.
Kimura, Nobuaki; Takemoto, Noriyuki; Ooka, Makoto; Ishitsuka, Etsuo; Nakatsuka, Toru; Ito, Haruhiko; Ishihara, Masahiro
JAEA-Review 2012-055, 40 Pages, 2013/03
JAEA-Review-2012-055.pdf:93.64MB
Training courses using JMTR and related facilities as advanced research infrastructures have been newly organized for domestic students, young researchers and engineers since FY2010 from a viewpoint of nuclear human resource development in order to support global expansion of nuclear power industry. In FY 2012, two courses were carried for foreign as well as Japanese young researchers and engineers in order to carry out effective practical training. For the foreigner course, 16 young researchers and engineers were joined from July 23rd to August 10th. For the Japanese course, total 35 young researchers and engineers were joined two courses from August 20th to August 31st and from September 3rd to September 14th. Lectures of these training courses were consisted from basics of nuclear energy to its application, especially for irradiation tests in Motrin this paper, results of these foreigners and Japanese training courses are reported.
Committee for JAEA Internationalization Initiative
JAEA-Review 2012-054, 28 Pages, 2013/03
JAEA-Review-2012-054.pdf:1.71MB
In global circumstances surrounding nuclear energy, the role expected to Japan Atomic Energy Agency (JAEA) is becoming increasingly important. JAEA has been promoted an initiative for the international center of excellence in order to increase the scientific competitiveness of Japan and make international contributions, by gathering excellent researchers from the entire world with the latest facilities. Also, JAEA established "Committee for JAEA Internationalization Initiative", which will discuss issues such as environmental improvement for accepted foreigners, direction of efforts for the international center of excellence and strategies to improve current situation. This report mentions the results of the committee's discussion including current issues for the initiative and recommendations for their solution, as well as the issues to be discussed in order to enhance international awareness of JAEA staff.
Environmental Management Section, Safety Administration Department
JAEA-Review 2012-053, 213 Pages, 2013/03
JAEA-Review-2012-053.pdf:7.85MB
In September, 2012 Japan Atomic Energy Agency published the Environmental Report 2012 concerning the activities of FY 2011 under "Law Concerning the Promotion of Business Activities with Environmental Consideration by Specified Corporations, etc, by Facilitating Access to Environmental Information, and Other Measures". This report has been edited to show detailed environmental performance data in FY 2011 as the base of the Environmental Report 2012. This report would not only ensure traceability of the data in order to enhance the reliability of the environmental report, but also make useful measures for promoting activities of environmental considerations in JAEA.
Department of Research Reactor and Tandem Accelerator
JAEA-Review 2012-052, 192 Pages, 2013/03
JAEA-Review-2012-052.pdf:16.58MB
The Department of Research Reactors and Tandem Accelerator is in charge of the operation, utilization and technical development of JRR-3 (Japan Research Reactor No.3), JRR-4 (Japan Research Reactor No.4), NSRR (Nuclear Safety Research Reactor) and Tandem Accelerator. This annual report describes a summary of activities of services and technical developments carried out in the period between April 1, 2011 and March 31, 2012. The activities were categorized into six service/development fields: (1) Recovery from the Great East Japan Earthquake, (2) Operation and maintenance of research reactors and tandem accelerator, (3) Utilization of research reactors and tandem accelerator, (4) Upgrading of utilization techniques of research reactors and tandem accelerator, (5) Safety administration for research reactors and tandem accelerator, (6) International cooperation. Also contained are lists of publications, meetings, granted permissions on lows and regulations concerning atomic energy, number of staff members dispatched to Fukushima for the technical assistance, commendation, outcomes in service and technical developments and so on.
Ochs, M.*; Tachi, Yukio; Trudel, D.*; Suyama, Tadahiro*
JAEA-Research 2012-044, 130 Pages, 2013/03
JAEA-Research-2012-044.pdf:3.61MB
JAEA has developed the setting approaches of sorption parameter (Kd) for site-specific conditions, to derive reliable parameter for performance assessment (PA) of geological disposal. These approaches include any transferring procedures from experimental conditions to PA conditions through expert judgments, semi-quantitative estimation procedures and thermodynamic sorption models (TSMs). The present report focused on illustrating a range of example calculations regarding the derivation of Kd values and their uncertainties based on semi-quantitative estimation procedures and TSMs. The Kd values of four key radionuclides, Cs, Ni, Am and Th were derived for Horonobe mudstone systems. These Kd-setting exercises allowed to estimate the magnitude of sorption under the site-specific conditions, and to identify some critical gaps in the existing data and process understanding. The possibilities of extending such approaches to further rock types including granitic rocks were also discussed.
Shimo, Michito*; Kumamoto, So*; Tsuyuguchi, Koji; Onoe, Hironori; Saegusa, Hiromitsu; Mizuno, Takashi; Oyama, Takuya
JAEA-Research 2012-043, 98 Pages, 2013/03
JAEA-Research-2012-043.pdf:26.71MB
One of the goals of the Mizunami Underground Research Laboratory (MIU) Project is to develop technical basis for investigation, analysis and evaluation technologies for understanding the deep underground geological environment in various scales. Understanding groundwater flow system is one of the important issues in the project, and to achieve this purpose, technologies for hydrogeological model and groundwater flow simulation technique, have to be established. As a result of this study, the significant hydrogeological structures around the MIU Construction Site were estimated. The inflow rate into the MIU facilities and hydraulic and geochemical impacts around the MIU Construction Site caused by the MIU facilities construction were predicted. The effect of pre-grouting to the MIU facilities was also confirmed.
Tatematsu, Kenji
JAEA-Research 2012-042, 45 Pages, 2013/03
JAEA-Research-2012-042.pdf:2.47MB
Long-term energy demand-and-supply were analyzed for our country using the MARKAL model, supposing six kinds of energy demand-and-supply scenarios where different installed capacity of nuclear power generation and the emission standard of carbon-dioxide were employed. It was shown that even when nuclear power generation was not used, the carbon-dioxide emissions in the whole country and a power generation sector are reducible by 37% and 47% in 2050 from the 1990 level, respectively. However, when nuclear power generation was phase-out and renewable energy and natural gas were substituted, it was found that an average power generating cost was higher than the case where use of nuclear or coal was continued, 3.7 yen/kWh or more. Moreover, in the case where immediate cessation of the nuclear power generation was carried out, it was also shown that a current average power generating cost rose by 4.4 yen/kWh. In order to evaluate and visualize the influence of power supply composition change on both the average power generating cost and the carbon-dioxide emissions, a new mapping method was proposed where diversity of an energy source, the carbon-dioxide emissions, and the average power generating cost were used as indexes. Based on the result of model analysis, when nuclear power generation was substituted with renewable energy, natural gas, or coal, oligopoly of an energy source was shown to increase sharply by abolition of nuclear power generation. These results showed that by continuing use of the nuclear power generation with a fixed scale, less carbon-dioxide emissions, avoiding oligopolization of an energy source and suppressing the steep rise of an average power generating cost were possible.
Kuboshima, Koji; Ishibashi, Masayuki; Sasao, Eiji; Tsuruta, Tadahiko; Tagami, Masahiko*; Yuguchi, Takashi
JAEA-Research 2012-037, 78 Pages, 2013/03
JAEA-Research-2012-037.pdf:235.85MB
The MIU (Mizunami Underground Research Laboratory) Project has three overlapping phases, Surface-based investigation phase (Phase I), Construction phase (Phase II), and Operation phase (Phase III). Currently, the project is under Phase II and Phase III. One of Phase II goals is set up to develop and revise models of the geological environment using the investigation results obtained during excavation, and to determine and assess changes in the geological environment in response to excavation. This report aims compiling results of study on geology and geological structure from the surface to G.L. -300m in the Phase II and provides the fundamental information on the geology and geological structure for future study. The compiling results of this report reflected basic data are utilized in the updating of the geological models in the Phase II.
Tokiwa, Tetsuya; Sugimoto, Shingo*
JAEA-Data/Code 2012-033, 28 Pages, 2013/03
JAEA-Data-Code-2012-033.pdf:10.56MB
GPS analysis was carried out to understand the characteristics of the crustal deformation due to the Tohoku-oki Earthquake in the northern Hokkaido, Japan. The data period for the analysis is from October 1, 2010 to May 31, 2011. The result of the analysis indicated that the displacement in the direction of the south-southeast was detected in this area, and the amount of displacement of the western side of northern Hokkaido is relatively larger than that of the eastern side. Therefore, the eastern side of northern Hokkaido was displaced to the north with respect to Horonobe area, and the west side was displaced to the south. Although the analysis period is short, the crustal deformation is different from a seismic crustal deformation showing the E-W crustal compression.
Okumura, Keisuke; Sugino, Kazuteru; Kojima, Kensuke; Jin, Tomoyuki*; Okamoto, Tsutomu; Katakura, Junichi*
JAEA-Data/Code 2012-032, 148 Pages, 2013/03
JAEA-Data-Code-2012-032.pdf:6.99MB
A set of cross section libraries for the isotope generation and depletion calculation code ORIGEN2 was produced by using recent nuclear data JENDL-4.0. In this new library (ORLIBJ40), neutron-induced cross sections, fission product yields, isomeric ratios and half-lives were updated. ORLIBJ40 includes 24 libraries for typical UO or MOX fuels of PWR and BWR. In addition, it includes 36 libraries for various fast reactor fuels. ORLIBJ40 was applied to the post irradiation examination analyses of LWR nuclear spent fuels. As a result, it was confirmed that improvements were achieved especially for inventory and radioactivity estimations of minor actinides (Am and Cm isotopes) and fission products sensitive to cross sections (Eu and Sm isotopes) and for long-lived fission products (
Se, etc.), compared with other existing ORIGEN2 libraries.
Takatori, Ryoichi; Yasue, Kenichi; Tanikawa, Shinichi*; Ninomiya, Atsushi*; Tanase, Atsushi*
JAEA-Data/Code 2012-028, 15 Pages, 2013/03
JAEA-Data-Code-2012-028.pdf:34.12MBJAEA-Data-Code-2012-028-appendix(CD-ROM).zip:0.52MB
To develop a method for estimating late Quaternary uplift rates of inland mountainous terrains where fluvial terraces are poorly developed, we focused on "circular abandoned channels", formed by meander cut-offs or river capture of an incised meandering river. We studied about 1,000 circular abandoned channels distributed throughout the Islands of Japan, and developed GIS database on circular abandoned channel in Japan. This database contains formation process, relative heights, degree of dissection and bedrocks of circular abandoned channels. Circular abandoned channels are distributed in inland mountainous terrains, where late Quaternary uplift rates are unknown, and indicate different relative heights along the same river. Relative heights tend to correlate with degree of dissection of the circular abandoned channels, which may indicate that degree of dissection correlate with ages of abandonment of circular abandoned channels.
Shimojo, Yutaka; Ihata, Yoshiaki; Kaneko, Koji; Takeda, Masayasu
JAEA-Testing 2012-005, 63 Pages, 2013/02
JAEA-Testing-2012-005.pdf:11.94MB
Taking an advantage of high penetration capability of neutron, neutron scattering experiments can be performed under various sample environment, such as low (high) temperature, pressure, magnetic field and stress, and those complex conditions. To this aim, a number of sample environment accessories, refrigerators, furnaces, pressure cells, superconducting magnets are equipped in JRR-3 to be used for experiments. In this document, all available equipment in both JRR-3 reactor hall and guide hall are summarized. We hope this document would help neutron scattering users to perform effective, and excellent experiments.
Oyamatsu, Yasuko*; Someya, Hiroyuki
JAEA-Technology 2012-046, 80 Pages, 2013/02
JAEA-Technology-2012-046.pdf:5.43MB
In the experimental fast reactor Joyo, there were many tests using the irradiation rigs that it was possible to be set irradiation conditions for each compartment independently. In case of no alternative fuel element to irradiate after unloading the irradiated compartments, the irradiation test was restarted with the dummy compartment which the fuel elements was not mounted. If the material specimens are mounted in this space, it is possible to realize effective utilization of the irradiation space. For these reasons, the irradiation rig (hybrid rig) consolidated with fuel elements and material specimens are developed. Fuel elements and material specimens differ greatly with heat generation, so that the point for developing of hybrid rig is being able to distribute appropriately the coolant flow which satisfies irradiation conditions. The following is described by this report. (1) It was confirmed that the flow distribution of loading the same irradiation rig with the compartment from which a flow demand differs could be satisfied. (2) It was confirmed that temperature setting capability equivalent to the former was securable. (3) By standardizing the coolant entrance structure of the compartment lower part, the prospect which can perform easily recombination of the compartment from which a kind differs between irradiation rigs was acquired.
Tsuji, Tomoyuki; Kameo, Yutaka; Sakai, Akihiro; Hoshi, Akiko; Takahashi, Kuniaki
JAEA-Technology 2012-045, 37 Pages, 2013/02
JAEA-Technology-2012-045.pdf:2.43MB
It is necessary to establish practical evaluation methods to determine radioactivity concentrations of the important nuclides for safety assessment on disposal of radioactive wastes in order to dispose of low-level radioactive wastes generated from various nuclear facilities in JAEA. In this report, the practical evaluation methods such as the scaling factor method for JPDR facilities have been studied for disposal of the low-level radioactive wastes generated from nuclear reactor facilities in JAEA.
Aihara, Jun; Ueta, Shohei; Ohashi, Hirofumi; Tachibana, Yukio
JAEA-Technology 2012-044, 9 Pages, 2013/02
JAEA-Technology-2012-044.pdf:1.22MB
Evaluation of integrity of coated fuel particles of GTHTR300 has already been carried out. On the other hand, new knowledge on pressure vessel failure, one of the causes of failure of coated fuel particles under irradiation, was obtained by preliminary irradiation experiment of coated fuel particles for HTTR up to official burnup of 7% FIMA. Then in this report, extrapolative evaluation of volume averaged pressure vessel failure probability was carried out based on method which is already published. Considering evaluated pressure vessel failure probability, in addition to corrosion behavior of SiC layer and fuel kernel migration of GTHTR300 coated fuel particles, already analyzed in past paper, volume averaged failure probability of coated fuel particles of GTHTR300 at refueling is small in view of public dose by accident, if initial failure probabilities of coated fuel particles are same as those of HTTR first loading fuel.
Kubo, Shinji; Tanaka, Nobuyuki; Noguchi, Hiroki; Iwatsuki, Jin; Onuki, Kaoru; Inagaki, Yoshiyuki
JAEA-Technology 2012-043, 41 Pages, 2013/02
JAEA-Technology-2012-043.pdf:7.74MB
Providing safety measures for workers and external environments are indispensable in R&D activities of the iodine sulfur water-splitting hydrogen production process, since this process uses toxic chemicals as sulfur dioxide, sulfuric acid, iodine and hydriodic acid. One of the R&D subjects is proof of manufacturability of chemical reactors made of practical structural materials and confirmation of the reactors' sound performance in the harsh process conditions. In order to examine the task, test apparatuses of the process are being constructed; the apparatus for a Bunsen reactor has been built and assembled. Capacities of vessels of the apparatus are about 50-150 liter; normal operating pressure will be 0.5 MPa [abs], and that of temperature will be 90 degrees centigrade. Safety measures for the test apparatus, operations, and in abnormal situations were considered prior to the start of the operation. This report summarizes the results of the considerations.
Ono, Takanori; Hatanaka, Nobuhiro; Okita, Takatoshi; Aono, Shigenori
JAEA-Technology 2012-042, 96 Pages, 2013/02
JAEA-Technology-2012-042.pdf:2.6MB
In January of 1993, plutonium dioxide powder was received from the reprocessing plant "La Hague" of COGEMA in France to Plutonium Fuel Production Facility (PFPF) of JAEA to use as feed powder of MOX fuel for FBR prototype "Monju". Since the plutonium dioxide powder was contained in COGEMA type canisters, the powder had to be rebottled from CCGEMA type canisters to JAEA type canisters which can be handled in the PFPF. Therefore feed powder rebottling equipment and temporary feed storage equipment were developed and installed in the PFPF. Rebottling work with their equipments was started from March of 1993 and completed in March of 2006. This report summarizes operating and maintenance experiences on feed powder rebottling equipment and temporary feed storage equipment. It's important to reflect the operating and maintenance experiences of the rebottling equipment into design of a new rebottling equipment for uranium-plutonium mixed oxide powder.
Kokusen, Junya; Sumiya, Masato; Seki, Masakazu; Kobayashi, Fuyumi; Ishii, Junichi; Umeda, Miki
JAEA-Technology 2012-041, 32 Pages, 2013/02
JAEA-Technology-2012-041.pdf:1.6MB
Uranyl nitrate solution fuel used in the STACY and the TRACY is adjusted in the Fuel Treatment System, in which such parameters are varied as concentration of uranium, free nitric acid, soluble neutron poison, and so on. Operations for concentration and denitration of the solution fuel were carried out with an evaporator from JFY 2004 to JFY 2008 in order to adjust the fuel to the experimental condition of the STACY and the TRACY. In parallel, the solution fuel in which some kinds of soluble neutron poison were doped was also adjusted in JFY 2005 and JFY 2006 for the purpose of the STACY experiments to determine neutron absorption effects brought by fission products, etc. After these experiments in the STACY, a part of the solution fuel including the soluble neutron poison was purified by the solvent extraction method with mixer-settlers in JFY 2006 and JFY 2007. This report summarizes operation data of the Fuel Treatment System from JFY 2004 to JFY 2008.
Geoscience Facility Construction Section, Tono Geoscience Center
JAEA-Review 2012-051, 184 Pages, 2013/02
JAEA-Review-2012-051.pdf:63.96MB
This progress report presents an outline compilation of construction activities, primary tasks performed, construction progress and problems reported, in fiscal year 2007. The outline of construction activities is a summary based on the scope of work planned in 2006. The main activities are based on the Tono Geoscience Center weekly reports and the construction progress is based on the planned and actual schedules and the Tono Geoscience Center weekly reports. The problems reported are based on accident reports, natural disasters, nonconformance and defects recorded by the Geoscience Facility Construction Section. Plan and actual performance of the MIU construction project No.2 (started on July 1, 2006 and completed on March 15, 2008) is described in this report.
J-PARC Center, Radiation Safety Section, Safety Division
JAEA-Review 2012-050, 88 Pages, 2013/02
JAEA-Review-2012-050.pdf:12.44MB
This annual report describes the activities of radiation safety of Japan Proton Accelerator Research Complex (J-PARC) for FY 2011. The activities described are radiation protection in workplaces, environmental monitoring, individual monitoring, maintenance of monitoring instruments, and the technological developments of radiation protection. Occupational exposures have not exceeded the prescribed dose limit. No effluent releases were recorded exceeding the prescribed limits on the amount and concentration of radioactivity for gaseous release and liquid waste. J-PARC was suffered from the Great East Japan Earthquake and the accident at the Fukushima Daiichi Nuclear Power Plant. The report also covers the activities for the recovery of J-PARC and the environmental monitoring of radioactivity from the accident.
Nishio, Kazuhisa; Shimada, Akiomi
JAEA-Review 2012-049, 99 Pages, 2013/02
JAEA-Review-2012-049.pdf:24.73MB
Japan Atomic Energy Agency (JAEA) at Tono Geoscience Center (TGC) has been conducting a geoscientific studies in order to establish a scientific and technological basis for the geological disposal of HLW. Information and Opinion Exchange Conference on Geoscientific Study has been held by TGC annually. The conference provides technical information and an opportunity for peer review and exchange of opinions on the geoscientific studies conducted at TGC. Research specialists and engineers from Japanese universities, research organizations and private companies usually participate in the conference. This document compiles research presentations, posters of the conference in Mizunami on November 14, 2012.
Task Group for Research Results Diffusion
JAEA-Review 2012-048, 83 Pages, 2013/02
JAEA-Review-2012-048.pdf:10.24MB
The missions of the Nuclear Safety Research Center (NSRC) are to support the nuclear safety improvement by providing research results and proper recommendation, and to be responsible for correct information diffusion to the public as the specialists of nuclear safety. As a part of actions to achieve these tasks, the meeting, Nuclear Safety Research Center Progress 2010, was held in Tokyo on January 14th, 2011, in order to present the latest safety research results and to collect opinions from participants on the researches and activities in the NSRC. This meeting was first held after the establishment of the Japan Atomic Energy Agency. Four oral presentations and poster sessions were made by active researchers and extensive discussions were conducted lively by approximately 100 participants from government agencies, universities, research institutes, utilities, manufacturers and so on. This report summarizes the presentations in the meeting and the questionnaire results.
Aihara, Jun; Ueta, Shohei; Maekawa, Masaki; Kawasuso, Atsuo; Sawa, Kazuhiro
JAEA-Review 2012-047, 34 Pages, 2013/02
JAEA-Review-2012-047.pdf:19.96MB
From the year 2004 to 2008, the Japan Atomic Energy Agency (JAEA) carried out the R&Ds on ZrC-coating process involving up to 200 g per batch scale with reduced excess carbon by bromide process. It should be noted that too much excess carbon adversely affects the performance of the ZrC-coating layer. In this paper, the authors summarize some characteristics of the microstructures and positron annihilation spectroscopy (PAS) of ZrC layers fabricated in the above R&D with carbon to zirconium atomic ratio (C/Zr) and the effects of the heat treatment, that imitates the thermal history of the sintering process, on the above-mentioned characteristics, reported in some papers.
Ouchi, Masaru; Takebe, Shinichi; Kawatsuma, Shinji; Fukushima, Tadashi*
JAEA-Review 2012-019, 186 Pages, 2013/02
JAEA-Review-2012-019.pdf:11.86MB
We have reviewed information about justification for establishing uranium bearing waste acceptance for near surface disposal (trench and concrete pit disposals) in foreign countries, to intend to discuss clearance level and disposal of uranium bearing waste in Japan. Most of EU countries have adopted the unconditional clearance level 1 Bq/g described in EU Guidance RP 122 Part 1 and IAEA Safety Guide RS-G-1.7 for uranium wastes. And in the case of special landfill burial, the conditional clearance level about 10 Bq/g (equivalent to exemption level) has been adopted in Germany, Sweden and UK.
Uematsu, Mari Mariannu; Sugino, Kazuteru; Kawashima, Katsuyuki; Okano, Yasushi; Yamaji, Akifumi; Naganuma, Masayuki; Oki, Shigeo; Okubo, Tsutomu; Ota, Hirokazu*; Ogata, Takanari*; et al.
JAEA-Research 2012-041, 126 Pages, 2013/02
JAEA-Research-2012-041.pdf:16.49MB
The characteristics of sodium-cooled metal fuel core compared to MOX fuel core are given by its higher heavy metal density and superior neutron economy. By taking advantage of these characteristics and allowing flexibility in metal fuel specification and core design conditions as sodium void reactivity and bundle pressure drop, core design with high burnup, high breeding ratio and low fuel inventory features will be achievable. On ground of the major achievements in metal fuels utilization as driver fuels in sodium fast reactors in U.S., the metal fuel core concept is selected as a possible alternative of MOX fuel core concept in FaCT project. This report describes the following items as a result of the joint study on "Reactor core and fuel design of metal fuel core of sodium-cooled fast reactor" conducted by JAEA and CRIEPI during 4 years from fiscal year 2009 to 2012.
TiO under D-T neutron irradiationEdao, Yuki; Kawamura, Yoshinori; Ochiai, Kentaro; Hoshino, Tsuyoshi; Takakura, Kosuke; Ota, Masayuki; Iwai, Yasunori; Yamanishi, Toshihiko; Konno, Chikara
JAEA-Research 2012-040, 15 Pages, 2013/02
JAEA-Research-2012-040.pdf:1.8MB
Tritium generation and recovery studies on LiTiO as a solid breeding material under neutron irradiation carried out in the Fusion Neutron Source (FNS) facility. A capsule with LiTiO packed bed was put in a system which simulated an actual blanket system which built in beryllium blocks and lithium titanate ones. Estimated values of the amount of tritium generation by a numerical calculation agreed closely with experimental values. The capsule was heated up to 300C, and helium, helium with water vapor, hydrogen or hydrogen/water vapor were selected as purge gas. In the case of purge by helium added water vapor, the ratio of HTO to total tritium release was 98%. In helium with hydrogen/water vapor purge, the ratio of HTO to total tritium release was 80%, which was confirmed that HTO released by isotope exchange reaction between water vapor and tritium. In helium with hydrogen purge, the ratio of HT to total tritium release was 6070%, which was shown that HT released by isotope exchange reaction between hydrogen gas and tritium. HTO released by water generation reaction between hydrogen in purge gas and oxygen in LiTiO although water vapor was not added in purge gas. The ratio of HTO release seemed to be small under the deoxidized condition of the LiTiO surface. Tritium release behavior in the LiTiO depended on the composition of purge gas, and its chemical form was affected by the surface conditions of LiTiO.
Kimura, Masanori; Takahara, Shogo; Homma, Toshimitsu
JAEA-Research 2012-039, 24 Pages, 2013/02
JAEA-Research-2012-039.pdf:1.91MB
To consider the method of implementing urgent protective actions in a nuclear accident appropriately, the authors have been assessing the effects of reducing doses by taking such actions using a Level 3 Probabilistic Safety Assessment (PSA) code, the OSCAAR, developed by the JAEA. Iodine thyroid blocking is an effective urgent protective action to reduce the equivalent doses to the thyroid due to inhalation of radioactive iodine. However, the timing of the administration of stable iodine is important to maximize the effectiveness for thyroidal blocking. Therefore, the careful consideration should be given to the most effective way of iodine thyroid blocking when preparing off-site emergency plans. In the present study, the authors introduced a metabolic model of iodine into the OSCAAR for evaluating the effect of the administration of stable iodine for reducing equivalent doses to the thyroid depending on the its timing. Then, examined the effectiveness of iodine thyroid blocking combined with sheltering or evacuation in the containment bypass scenario with large radioactive release to the environment.
Hayano, Akira; Sawada, Atsushi
JAEA-Research 2012-038, 32 Pages, 2013/02
JAEA-Research-2012-038.pdf:3.66MB
The purpose of this study is to contribute to methodology development for evaluating retardation effects of nuclide transport in near-field host rock to flexibly respond to the uncertainty of SDMs. Initially, the methodology for evaluating retardation effects of nuclide transport quantitatively in near-field host rock was developed. Then, the nuclide transport analysis using the data obtained at the surface-based investigation phase of Mizunami underground laboratory project was carried out in order to show the example of application for the methodology. Finally, the impact on results of evaluation caused by the uncertainty of SDMs was considered, and feedback to the investigation of geological environment was given from the result of the analysis of this study.
Tagami, Masahiko*; Yamada, Yasuhiro*; Yamashita, Yoshihiko*; Miyakawa, Ayumu*; Matsuoka, Toshifumi*; Xue, Z.*; Tsuji, Takeshi*; Tsuruta, Tadahiko; Matsuoka, Toshiyuki; Amano, Kenji; et al.
JAEA-Research 2012-036, 110 Pages, 2013/02
JAEA-Research-2012-036.pdf:44.93MB
Northeast strike faults developed in and around the Mizunami Underground Research Laboratory (MIU) control groundwater flow. These faults were possibly formed as a part of pull-apart structure by the right lateral movement of the Tsukiyoshi fault distributed in the north of MIU site. But the formational mechanism of these faults is still uncertain. In this joint research, the analog experiment and the numerical simulation were used to restore the geological structures around MIU site. The paleo-stress analysis were exposed an ancient deformation mechanism, and the formation timing was presumed in the regional tectonics. The results are adopted for the design of the analog experiment and the numerical simulation. The results of obtained analog experiment and numerical simulation are verified three-dimensionally, and then compared to the current geological structure model. Then the geological structure in the uninvestigated area is estimated.
Haraga, Tomoko; Kameo, Yutaka; Ishimori, Kenichiro; Shimada, Asako; Tobita, Minoru*; Takahashi, Shigemi*; Takahashi, Kuniaki
JAEA-Data/Code 2012-031, 39 Pages, 2013/02
JAEA-Data-Code-2012-031.pdf:9.28MB
The Fugen Nuclear Power Station was shut down and decommissioning of the Fugen has been implemented. To calculate the scaling factor of radioactive waste or advance the clearance of dismantled materials, a large number of radioactivity concentration data of dismantled materials have to be accumulated. For these reasons, the simple and rapid radioactivity determination method was applied for metal samples, which were taken from pipes of the Fugen. The present report is summarized analytical procedures and obtained radioactivity data of the Fugen pipe samples.
Aihara, Jun; Ohashi, Hirofumi; Sawa, Kazuhiro; Tachibana, Yukio
JAEA-Data/Code 2012-030, 13 Pages, 2013/02
JAEA-Data-Code-2012-030.pdf:1.18MB
We have developed Code-B-2 for the prediction of pressure vessel failure probabilities of SiC-tri-isotropic (TRISO) coated fuel particles for the high temperature gas-cooled reactors (HTGRs) under operation by modification of an existing code, Code-B-1. We have modified internal pressure calculation part of Code-B-1 to treat fluctuation of irradiation temperature for Code-B-2. In addition, we have added part of calculation of irradiation creep constants and irradiation swelling rates of PyC layers, which are very important for stress calculation. In this report, we first describe on details of Code-B-2. Next, we calculate a property of PyC (Bacon anisotropic factor (BAF) value) for Code-B-2, which is used for calculation of failure probabilities of Japanese high-quality SiC-TRISO fuel particles under operation with a method we have suggested.
Inagaki, Daisuke; Tokiwa, Tetsuya; Murakami, Hiroaki
JAEA-Data/Code 2012-029, 132 Pages, 2013/02
JAEA-Data-Code-2012-029.pdf:8.0MBJAEA-Data-Code-2012-029-appendix(DVD-ROM)-1.zip:5339.82MBJAEA-Data-Code-2012-029-appendix(DVD-ROM)-2.zip:4415.05MBJAEA-Data-Code-2012-029-appendix(DVD-ROM)-3.zip:127.72MB
In the Horonobe Underground Research Laboratory (URL) Project, construction of the Ventilation Shaft, the East Shaft and the drifts has been conducted as a phase 2 research. In the research, observation of the lithofacies and fracture, and tests, simple elastic wave exploration, schmidt hammer test, equotip test, point load test are conducted in each face, and measuring instruments such as extensometer, rock-bolt axial force meter, shotcrete stress meter and tunnel lining concrete stress meter are installed in particular face. In addition, for the purpose of the validation of the results of predictive analysis, conducted in phase 1, about the amount of spring water during construction of underground facilities, data on the changes of amount of spring water and water quality is obtained. This report summarizes the measurements data acquired at the Ventilation Shaft, the East shaft and the 250 m Gallery.
Kimura, Masanori; Kinase, Sakae; Hato, Shinji*
JAEA-Data/Code 2012-027, 27 Pages, 2013/02
JAEA-Data-Code-2012-027.pdf:2.33MB
The Fukushima Daiichi Nuclear Power Plant accident resulted in a wide range of radioactive contamination. As a result, the public concerns the internal doses for chronic exposure due to intake in daily life. To reduce some concerns, it is important to develop the evaluation method of chronic internal dose. The JAEA developed the DSYS code that calculates internal dose to the public with dose coefficients and treats dose assessment of internal exposure due to acute intake based on the ICRP's Publications (Publ.30, 56, 66, 67, 69, 71, 72). Therefore, it cannot apply to the evaluation of whole-body retention values or committed effective/equivalent dose for chronic exposure. In the present study, the authors considered the evaluation method of chronic internal dose and developed the DSYS-Chronic to evaluate chronic internal dose by incorporating into the DSYS code. This report shows the outline of the DSYS-Chronic code and the example of evaluation results.
Sasaki, Shunichi; Kojima, Atsushi; Shimizu, Tatsuo; Kawai, Mikito*; Hanada, Masaya
JAEA-Technology 2012-040, 26 Pages, 2013/01
JAEA-Technology-2012-040.pdf:5.6MB
Breakdowns occur in the JT-60U 500 kV negative ion accelerator with a high probability during the high voltage conditioning. The breakdown in the accelerator is the same phenomena as a short circuit for the power supply. Surge noise generated by the short circuit causes malfunctions of components in the NBI system and other systems. To evaluate the surge noise characteristics, the breakdown noise has been measured using a test circuit with a spark gap which is the protection gap for the accelerator and it considered to be a source of noise. Further, reduction of the surge noise at the spark gap and countermeasure of the malfunction due to the noise have been studied quantitatively at the side of the system where the malfunction occurs. As a result, it has been observed that the noise propagates through space or grounding lines and gives malfunctions for other systems. To reduce the noise, resistors have been connected in the ground potential side of the gap. It was confirmed that the resistor is effective to reduce the noise and probability of the malfunction has been reduced from 100% to 15%. In addition, by placing the ferrite core in the grounded line and by using an isolation amplifier, the malfunction was further reduced to 10%.
Park, C.; Tanimoto, Masataka; Imaizumi, Tomomi; Miyauchi, Masaru; Ito, Masayasu; Kaminaga, Masanori
JAEA-Technology 2012-039, 87 Pages, 2013/01
JAEA-Technology-2012-039.pdf:3.55MB
Preliminary accident analysis has been carried out for a LOFA (Loss of Flow Accident) and RIAs (Reactivity Insertion Accidents) of the conceptual 10 MW MRR (multi-purpose research reactor) under design study by using the RELAP5/MOD3 code in order to provide the preliminary evaluation of safety margin as well as the intuitions to the design of the MRR. Input and modeling for the RELAP5/MOD3 simulations have also been described. The analysis results indicate that the concept of the MRR is feasible with practical safety margins. The same events have been also analyzed by using the PARET/ANL and the EUREKA-2/RR codes to compare the codes suitability, which have been widely used for the analysis of research reactors. Same geometric and modeling data used for the RELAP5/MOD3 have been used as long as they correspond to each code's input requirements. The three codes show the same or similar overall trends for the events analyzed, but show a small difference in a specific condition.
Shibahara, Yuji; Ishigami, Tsutomu; Morishita, Yoshitsugu; Yanagihara, Satoshi*; Arita, Yuji*
JAEA-Technology 2012-038, 72 Pages, 2013/01
JAEA-Technology-2012-038.pdf:3.68MB
To implement a decommissioning project reasonably, it is necessary and important to beforehand evaluate project management data as well as to select an optimum dismantling scenario among various scenarios postulated. Little study on the subject of selecting an optimum scenario has been carried out, and it is one of the most important subjects in terms of decision making. In FY 2009, Japan Atomic Energy Agency and University of Fukui launched the joint research of a decision making method which is important to determine a decommissioning plan. The purpose of this research is to construct a methodology for selecting an optimum dismantling scenario among various scenarios postulated based on calculated results of project management data for FUGEN. Project management data for several dismantling scenarios postulated at FUGEN were evaluated based on actual dismantling work for feedwater heater at FUGEN, and an optimum scenario was discussed using the AHP, one of Multi-Criteria Decision Analysis Method. This report describes the results of the joint research in FY 2010.
Kubo, Shinji; Yoshino, Koji*; Takemoto, Jumpei*; Kasahara, Seiji; Imai, Yoshiyuki; Onuki, Kaoru
JAEA-Technology 2012-037, 20 Pages, 2013/01
JAEA-Technology-2012-037.pdf:17.29MB
Densities of Bunsen reaction solutions in the iodine-sulfur process were measured with an oscillating U-tube density meter. Two types of the solutions were prepared to simulate sulfuric acid solutions and hydriodic acid solutions of the Bunsen reaction step. The former solution ranged in concentration from 0 to 45 wt% of sulfuric acid containing HI and I of 0-2 mole%; the latter solution contained 0-17 mole% I, 1-15 mole% HI and 0-2 mole% HSO. The temperature of the measured solution were 10-60 C. It was found that, in both solutions, the effect of HI and I concentration on the density could well be represented by using a kind of mole fraction of iodine atom. Based on the finding, a set of correlation equations between the densities and the compositions were derived. Additionally, viscosities of ploy-hydriodic acid were measured using an oscillating viscosity meter in temperature range of 5-40 C, and in the composition range of 0-17 mole% I and 1-15 mole% HI; a empirical equation to calculate viscosity from the composition and the temperature are obtained.
Kojima, Takuji
JAEA-Review 2012-046, 209 Pages, 2013/01
JAEA-Review-2012-046.pdf:16.28MB
JAEA Takasaki annual report 2011 describes research and development activities performed from April 1, 2011 to March 31, 2012 with Takasaki Ion Accelerators for Advanced Radiation Application (TIARA, four ion accelerators), and electron/-ray irradiation facilities (an electro accelerator and three Co -ray irradiation facilities) at Takasaki Advanced Radiation Research Institute, Japan Atomic Energy Agency (JAEA Takasaki). These activities are classified into four research fields: (1) Space, Nuclear and Energy Engineering, (2) Environmental Conservation and resource Exploitation, (3) Medical and Biotechnological Application, and (4) Advanced Materials, Analysis and Novel Technology. This annual report contains 158 reports consisting of 150 research papers and 8 status reports on operation/maintenance of the irradiation facilities described above.
Kurikami, Hiroshi; Yoshikawa, Hideki; Sasamoto, Hiroshi; Iijima, Kazuki; Zaima, Naoki; Munakata, Masahiro; Tokizawa, Takayuki; Nakayama, Shinichi
JAEA-Review 2012-045, 129 Pages, 2013/01
JAEA-Review-2012-045.pdf:15.94MB
This report shows the records of JAEA's investigation on dose rate reduction at the Fukushima University Junior High School and Kindergarten. The main outcomes are as follows. (1) experiments were performed to investigate intrusion depth of radiocesium in the soil. Based on the experiment, we proposed a countermeasure to reduce air dose rates. (2) The action we proposed allowed dose rate reduction to about one tenth to one twentieth at playgrounds. (3) Follow-up monitoring was performed after one year, and shows no obvious evidence of recontamination at the playgrounds. (4) Decontamination of a tree was tested. Radiocesium was accumulated around the root. By removing the soil, the air dose rate at about one-meter distance from the tree was decreased.
Suzuki, Mitsutoshi; Iwabuchi, Junichi*; Kasai, Yoshimitsu*; Kuno, Yusuke; Mochiji, Toshiro
JAEA-Review 2012-044, 109 Pages, 2013/01
JAEA-Review-2012-044.pdf:6.71MB
JAEA has worked for the contribution to the world disarmament and nonproliferation through the United States and Russia cooperation on the excess weapon plutonium disposition from Russian as well as to acquire the basic data of the post irradiation test with the BN-600 and the vibropack MOX fuel fabrication technologies. To support the initiative of Japan government, JAEA has started the joint research activities with some of the Russian national laboratories under the MINATOM in 1999. Since then, JAEA has been involved into the demonstration experiment for the vibropack fuel irradiation with the BN-600 that was managed by the PESCO corp. under the contract with MEXT. The joint researches with Russian national laboratories and the demonstration studies on vibropac MOX fuel assemblies from 1999 to 2011 are surmmarized in this document.
Information Technology Systems' Management and Operating Office
JAEA-Review 2012-042, 259 Pages, 2013/01
JAEA-Review-2012-042.pdf:23.73MB
Japan Atomic Energy Agency (JAEA) conducts research and development (R&D) in various fields related to nuclear power as a comprehensive institution of nuclear energy R&Ds, and utilizes computational science and technology in many activities. As more than 20% of papers published by JAEA are concerned with R&D using computational science, the supercomputer system of JAEA has become an important infrastructure to support computational science and technology utilization. In FY2011, the system was used for analyses of the accident at the Fukushima Daiichi Nuclear Power Station and establishment of radioactive decontamination plan, as well as the JAEA's major projects such as Fast Reactor Cycle System, Fusion R&D and Quantum Beam Science. This report presents a great amount of R&D results accomplished by using the system in FY2011, as well as user support structure, operational records and overviews of the system, and so on.
Department of Radiation Protection, Nuclear Science Research Institute; Safety Section, Department of Administrative Services, Takasaki Advanced Radiation Research Institut; Safety Section, Department of Administrative Services, Kansai Photon Science Institute; Operation Safety Administration Section, Mutsu Office, Aomori Research and Development Center; Safety Section, Department of Administrative Services, Naka Fusion Institute
JAEA-Review 2012-041, 181 Pages, 2013/01
JAEA-Review-2012-041.pdf:6.04MB
This annual report describes the activities of Radiation Protection Sector in Department of Radiation Protection in Nuclear Science Research Institute, Safety Section in Takasaki Advanced Radiation Research Institute, Safety Section in Kansai Photon Science Institute, Operation Safety Administration Section in Aomori Research and Development Center and Safety Section in Naka Fusion Institute.
Kutsuna, Hideki; Koda, Yuya; Shibahara, Yuji; Kadowaki, Haruhiko
JAEA-Review 2012-040, 36 Pages, 2013/01
JAEA-Review-2012-040.pdf:8.2MB
Fugen Decommissioning Engineering Center is establishing "Technical special committee on Fugen decommissioning" which consists of the members well-informed, aiming to make good use of Fugen as a place for technological development which is opened inside and outside the country, as the central point in the energy research and development base making project of Fukui prefecture, and to utilize the outcome in our decommissioning to the technical development effectively. This report compiles presentation materials "The Current Situation of Fugen Decommissioning", "The Application Results of Various Cutting Methods in the Dismantling of the Equipments of the Turbine System", "Study of Work Program on the Dismantling Activities with the Project Management Data Evaluation System", "Record and Knowledge in Working for a Heavy Water Withdraw and a Tritium Removal", presented in the 26th Technical special committee on Fugen decommissioning which was held on September 13, 2012.
Abe, Hitoshi; Tashiro, Shinsuke; Watanabe, Koji; Uchiyama, Gunzo
JAEA-Research 2012-035, 26 Pages, 2013/01
JAEA-Research-2012-035.pdf:1.94MB
To contribute on confirmation of safety of fuel cycle facilities, an evaluation method for soundness of confinement capability of the facilities under fire accident has been investigated. Organic extraction solvents, zinc stearate, which is added into MOX powder in MOX fuel preparation process, and typical lubricating oil were considered to be examination objects as the representative combustible materials in the facilities. Combustion property data, such as mass loss rate and soot release fraction, of them and clogging property data of HEPA filter with combustion of the organic extraction solvents were measured. As the results, it was found that soot release fraction from burning 30%TBP/70%dodecane was larger than that of the other materials including dodecane and very rapid rise of differential pressure of HEPA filter, which has not been reported, would be induced in the last stage of combustion of 30%TBP/70%dodecane. Furthermore, it was confirmed that zinc stearate, of which combustibility has not been considered, burned continuously in the condition which was heated from outside.
Yoshida, Eiichi; Kato, Shoichi; Furukawa, Tomohiro
JAEA-Research 2012-034, 68 Pages, 2013/01
JAEA-Research-2012-034.pdf:11.75MB
Oxygen concentration in sodium is the important factor for the corrosion of FBR structural materials. In this study, the experiments have been done to clarify the effect of sodium contaminated by oxygen on corrosion and low cycle fatigue strength of the materials. The materials for use of the experiments were FBR Grade type 316 SS (316FR) and Mod. 9Cr-1Mo steel. The corrosion test has been performed in sodium containing of 1, 10 and 10
ppm of initial oxygen at 650C for 500 hours. The fatigue test has been done for the post-immersed steels at 650C in air.
Hosoma, Takashi
JAEA-Research 2012-033, 66 Pages, 2013/01
JAEA-Research-2012-033.pdf:13.1MB
An exquisite shape of gas-liquid interface, that is a bubble/drop/liquid bridge, is the result of continuous pressure balance along vertical axis between the pressure due to difference of density and the pressure due to surface tension and curvature of interface. However, there have been surprisingly a little papers arguing the accurate shape, curvatures and volume. Regarding the research and development of U-Pu co-conversion technology, some phenomena were well understood by obtaining the accurate shape and/or volume. A numerical solving method by polar coordinate system with a switched-origin algorithm applicable to the shape that includes multiple tangential planes both in horizontal and in vertical was derived through such experiences, although static physical conditions and axisymmetrical property are assumed. The real interface shape is actualized or selected as a part of the calculated curve, which depends on physical conditions. A bubble at the tip of dip-tube used for density/level measurement, a bubble nucleates in the cylindrical shape of liquid heated by microwave and an estimated liquid bridge in the granule after co-conversion were described as actual examples. Interfaces between water and air under normal temperature and atmospheric pressure were described as numerical examples for systematic investigation. Contact angle, internal/external pressure difference, volume, surface energy and wavelength of periodically deforming shape are physical conditions actualizing the calculation.
Editorial Committee of Refining and Conversion Facility Decommissioning Results
JAEA-Data/Code 2012-026, 78 Pages, 2013/01
JAEA-Data-Code-2012-026.pdf:26.08MB
The Refining and Conversion Facility located in the Ningyo-toge Environmental Engineering Center had the natural uranium conversion process and reprocessed uranium conversion process. The construction of this facility was started in 1979 and completed in October 1981. Dismantling of equipments in radiation controlled area of this facility was started from 2008. Equipments in radiation controlled area (excluding ventilating equipment and liquid waste treatment equipment) will be dismantled by the 2011 fiscal year, and ventilating equipment and liquid waste treatment equipment will be dismantled by the 2014 fiscal year. This report is a record of the dismantlement situation of the Refining and Conversion Facility in 2011 fiscal years. Concretely, dismantlement logs, dismantlement material, and secondary waste are published.
Kawamoto, Koji; Kuboshima, Koji; Ishibashi, Masayuki; Tsuruta, Tadahiko; Sasao, Eiji; Ikeda, Koki; Mikake, Shinichiro; Hara, Ikuo; Yamamoto, Masaru
JAEA-Data/Code 2012-025, 32 Pages, 2013/01
JAEA-Data-Code-2012-025.pdf:3.03MBJAEA-Data-Code-2012-025-appendix.zip:126.32MB
This document presents the data of geological investigations in the shafts and research galleries from the depth of 300m to 500m of the MIU from the 2008 fiscal year to the 2011 fiscal year. In the shafts and research galleries of the MIU, although the Cretaceous Toki granite is distributed, pegmatite, aplite and lampropyre dike are distributed partially.
Torii, Tatsuo; Sanada, Yukihisa; Sugita, Takeshi; Kondo, Atsuya*; Shikaze, Yoshiaki; Takahashi, Masaki; Ishida, Mutsushi; Nishizawa, Yukiyasu; Urabe, Yoshimi
JAEA-Technology 2012-036, 182 Pages, 2012/12
JAEA-Technology-2012-036.pdf:41.89MB
We carried out aerial radiation monitoring (ARM) of all Japan area in order to investigate the influence of the radio cesium which was emitted into the atmosphere by disaster of the Fukushima Dai-ichi Nuclear Power Plant of Tokyo Electric Power Co., Inc.. AMS can measure a ray quickly by flight from 300 m height above the ground. Moreover, ARM has an advantage which can grasp self-possessed quantity distribution of an air dose rate and radioactive cesium in "field", and is visually intelligible. Although there were apparatus and the technique of ARM in our country, sufficient preparations for wide area monitoring were not made. Therefore, it fixed based on the method of the U.S. Department of Energy (DOE) about the method of the conversion to all radiation dose, and the conversion method to radiocesium deposition and the method of mapping. It is possible to discriminate from a background (cosmic-ray, self-contamination and natural nuclides) at the time of western-part-of-Japan measurement by improving of the method in parallel to data acquisition. By this monitoring, it was able to check about the distribution situation of the air dose rate of the Japanese whole region, or the radioactive cesium deposition. Here, the measurement technique and a result are described.
Muraguchi, Yoshinori; Kanayama, Fumihiko; Usui, Hideo; Izumo, Sari; Tachibana, Mitsuo
JAEA-Technology 2012-035, 69 Pages, 2012/12
JAEA-Technology-2012-035.pdf:4.96MB
Dismantling activities of equipment in JAEA's Reprocessing Test Facility (JRTF) used for wet reprocessing test started from 1996. Glove boxes and hoods installed in the main building were dismantled preferentially for securing temporary place of dismantled waste and dismantling tools by dismantling activities. Of these, 8 glove boxes (glove box group) were installed in room 232 of the main building. The glove box group was dismantled by setting up a large plastic enclosure (greenhouse) for work efficiency. In this report, dismantling procedure and actual data obtained from dismantling activity were arranged about dismantling activity of glove box group of room 232 in 1996. About dismantling activity of glove box group, manpower of the basic work items extracted by classifying into common work items and independent work items were analyzed. In addition, calculation equation was examined concerning dismantling of glove boxes.
Sakatani, Keiichi; Nakatani, Takayoshi; Funabashi, Hideyuki
JAEA-Technology 2012-034, 20 Pages, 2012/12
JAEA-Technology-2012-034.pdf:10.22MB
We planned the gas-accumulating type corrosion test on Zr-2.5wt%Nb alloy which is used in the pressure tube of Fugen (ATR) in order to obtain long-term corrosion rate data under the low oxygen and alkaline conditions assuming the disposal environment. Before starting the test, we examined the specimen machining method and confirmed the corrosion test conditions.
Geoscience Facility Construction Section, Tono Geoscience Center
JAEA-Review 2012-038, 235 Pages, 2012/12
JAEA-Review-2012-038.pdf:23.37MB
This progress report presents an outline compilation of construction activities, primary tasks performed, construction progress and problems reported in Fiscal Year 2006. The outline of construction activities is a summary based on the scope of work planned in 2006. The main activities are based on the Tono Geoscience Center weekly reports. The construction progress is based on the planned and actual schedules and the Tono Geoscience Center weekly reports. The problems reported are based on accident reports, natural disasters, nonconformance and defects recorded by the safety manager of the Geoscience Facility Construction Section. Construction plan of the MIU construction project No.2 (started on July 1, 2006) is described in this report. Regarding the plan and actual performance of MIU construction project No.1 (completed on June 30, 2006), it is described in "Construction Progress Report from Fiscal Year 2002 to Fiscal Year 2005 (including a part of Fiscal Year 2006)".
Department of HTTR
JAEA-Review 2012-037, 80 Pages, 2012/12
JAEA-Review-2012-037.pdf:16.02MB
The High Temperature Engineering Test Reactor (HTTR) constructed at the Oarai Research and Development Center of the Japan Atomic Energy Agency (JAEA) is the first high-temperature gas-cooled reactor (HTGR) in Japan. The HTTR is a graphite-moderated and helium gas-cooled reactor with 30 MW of thermal power. In fiscal year 2011, planed operations and maintenance was disturbed by the 2011 off the Pacific coast of Tohoku Earthquake and the operation and maintenance plans were revised. The certification evaluation of the nuclear facilities after the earthquake was carried comprehensively out with the equipment inspections and the seismic response analysis. This report summarizes activities and results of HTTR operation, maintenance, and several R&Ds, which were carried out in the fiscal year 2011.
Seguchi, Tadao*; Tamura, Kiyotoshi*; Watashi, Katsumi; Suzuki, Masahide; Shimada, Akihiko; Sugimoto, Masaki; Idesaki, Akira; Yoshikawa, Masahito; Oshima, Takeshi; Kudo, Hisaaki*
JAEA-Research 2012-029, 158 Pages, 2012/12
JAEA-Research-2012-029.pdf:9.4MB
The degradation mechanisms of ethylene-propylene rubber (EPR), crosslinked polyethylene (XLPE), polyvinylchloride (PVC), and silicone rubber (SiR) as the cable insulation materials were investigated for the cable ageing research of the nuclear power plant. The materials as same insulations for the practical cable (practical formulation) and as the model formulation containing specific additive were selected. They were exposed to the accelerated radiation and thermal environments. The mechanical properties, the crosslinking and chain scission, and the distribution of antioxidant and of oxidative products were measured and analyzed.
Tokiwa, Tetsuya; Sugimoto, Shingo*
JAEA-Data/Code 2012-024, 53 Pages, 2012/12
JAEA-Data-Code-2012-024.pdf:5.36MB
GPS analysis was carried out to understand the characteristics of the crustal movement in the northern Hokkaido, Japan. GPS data from 33 stations were used for this analysis. The analysis covered data during the period from October 2000 to October 2010. The results of this analysis indicate that this area is in nearly E-W compressive stress field. In addition, dilatation rate and maximum shear strain rate is -70-10
10
and 5012010 strain/year, respectively.
Ishihara, Masahiro; Ishitsuka, Etsuo; Suzuki, Masahide
JAEA-Conf 2012-002, 179 Pages, 2012/12
JAEA-Conf-2012-002.pdf:26.34MB
Under the "Arrangement for Corporation in the field of peaceful uses of Nuclear Energy between the Japan Atomic Energy Agency (JAEA) and the Korean Atomic Energy Research Institute (KAERI)", the 2012 JAEA/KAERI Joint Seminar on Advanced Irradiation and PIE (post-irradiation examination) Technologies has been held at Mito, Japan from March 28 to 30, 2012. This triennial seminar is the seventh in series of bilateral exchange of irradiation and PIE technologies and research reactor management. Since the first joint seminar on the PIE Technology between JAERI (Japan Atomic Energy Research Institute, former agency of JAEA) and KAERI was held at JAERI Oarai Research Institute, Japan in 1992, the international cooperation program between JAEA and KAERI has been actively carried out in the field of neutron irradiation. At the fifth seminar in 2005 and sixth in 2008, the irradiation technology and the research reactor management fields were included, respectively, to the joint seminar, and it covers whole areas of irradiation using research reactors. In this seminar total 37 presentations were made in three technical sessions, which are "research reactor management", "advanced irradiation technology" and "post-irradiation examination technology", and active information exchange was done among participants. Papers or manuscripts presented in the 2012 JAEA/KAERI Joint Seminar on Advanced Irradiation and PIE Technologies are contained in the proceedings.
Fujiwara, Takeshi
JAEA-Testing 2012-004, 13 Pages, 2012/11
JAEA-Testing-2012-004.pdf:2.7MB
In the 4-Group partitioning process developed in Japan Atomic Energy Research Institute (presently: Japan Atomic Energy Agency), a heat-generating nuclide group including Sr and Cs is separated by inorganic ion exchangers. Hydrous titanic acid and zeolite are used as the inorganic ion exchangers. The mechanical durability of the particles of hydrous titanic acid used for Sr recovery is not enough in case of mixing with zeolite used for Cs recovery. The method of drying the hydrous titanic acid was improved to provide sufficient mechanical durability to the product of hydrous titanic acid in case of mixing with zeolite. A procedure of producing hydrous titanic acid from the raw material, titanyl sulfate, was established and documented with cares to be taken at each step.
Kinoshita, Junichi; Endo, Masayuki; Uesaka, Takahiro
JAEA-Testing 2012-003, 29 Pages, 2012/11
JAEA-Testing-2012-003.pdf:2.95MB
The comparatively high level liquid radioactive wastes generated from the nuclear facilities in the Nuclear Science Research Institute of JAEA have been treated by the bituminization system. In the future, bituminized products could be disposed of as homogeneously solidified products, if their qualities would meet with the technical standards of homogeneously solidified products which are stipulated in nuclear regulatory law. In this report, we summarized the measurement results of the density and radioactivity of solidified products in order to get basic data for future disposal.
Yoshida, Eiichi; Hirakawa, Yasushi; Yatabe, Toshio
JAEA-Technology 2012-033, 177 Pages, 2012/11
JAEA-Technology-2012-033.pdf:17.98MB
In JAEA, lots of tests using sodium had been carried out on the development of sodium component systems and sodium technologies for the experimental reactor JOYO and prototype reactor MONJU. When research and development has come to the end of the first stage for these reactors, those sodium test facilities has dismantled and attached sodium has been cleaned. Lots of experiences and knowledge of sodium cleaning treatment technologies has accumulated. In order to use those experiences and knowledge effectively for future sodium technology and research on the next generation fast reactors, experiences and knowledge of sodium technologies for typical systems and components has been evaluated and knowledge related important topics has been rearranged. Based on those evaluation and rearrangement, technical guidelines of sodium cleaning treatment technologies has been proposed for the purpose of effective reference of the past experiences and knowledge.
Sugawara, Takanori
JAEA-Review 2012-043, 181 Pages, 2012/11
JAEA-Review-2012-043.pdf:26.88MB
The International Symposium on "Future of Accelerator-Driven System" was held on 29th February, 2012 at Gakushi-Kaikan, Tokyo, Japan hosted by Nuclear Science and Engineering Directorate, JAEA (Japan Atomic Energy Agency) and J-PARC (Japan Proton Accelerator Research Complex) Center. The objectives of the symposium were to make participants acquainted with the current status and future plans for research and development of ADS in the world and to discuss an international collaboration for ADS and P&T (Partitioning and Transmutation) technology. About 100 scientists participated in the symposium from Belgium, China, France, India, Italy, Japan, Korea and Mongol. In the morning session, current R&D activities of ADS in Japan were reported. In the afternoon session, current R&D activities were reported from China, Korea, India, Belgium and EU. A panel discussion was taken place with regards to the international collaboration for ADS at the final session. Two keynote speakers presented their outlooks on the topics and seven panelists and audience discussed those topics.
FBR Plant Engineering Center
JAEA-Review 2012-039, 56 Pages, 2012/11
JAEA-Review-2012-039.pdf:10.59MB
This annual report was compiled for research activities of FBR Plant Engineering Center of early 2011.
Morita, Yasuji; Yamagishi, Isao; Tsubata, Yasuhiro; Matsumura, Kazumi; Sakurai, Koji*; Iijima, Takahiko
JAEA-Research 2012-031, 39 Pages, 2012/11
JAEA-Research-2012-031.pdf:4.87MBJAEA-Research-2012-031(errata).pdf:0.14MB
Solvent extraction process with di-2-ethylhexylphosphoric acid has been developed for the purpose of Mo separation from high-level radioactive liquid wastes (HLLW). Mo has very low solubility in borosilicate glasses and makes so-called yellow phase when it contained beyond the solubility. After extraction and back-extraction data of Mo and other fission products were obtained by batch extraction tests, continuous extraction tests with simulated HLLW were performed using mixer-settler twice. At the second test, reduction of Y extraction yield and increase of Mo and Zr back-extraction yield were obtained compared with the results of the first tests, but those values should be still improved. Process simulation technique was developed using simulation code named PARC-MA, and the optimized process condition was obtained by the simulation.
Matsuoka, Toshiyuki; Hodotsuka, Yasuyuki*; Yamada, Nobuto
JAEA-Research 2012-028, 70 Pages, 2012/11
JAEA-Research-2012-028.pdf:19.33MB
Reverse Vertical Seismic Profiling (R-VSP) using vibration during the construction of underground facility has been carried out at the MIU construction site to develop the technique that estimate the 3-dimensional geological structure. In this report, we apply plural data processing/analysis methods (VSP-CDP transform, VSP migration, IP transform and seismic interferometory) to observed vibration data (blasting data, drilling vibration data and construction noise data), and discuses the applicability of the R-VSP. In this study, geological structures such as unconformities between sedimentary rocks and granite, and steep faults were extracted using applied prual data processing/analysis methods. We conclude that it is likely that the R-VSP using various vibration data and prual data processing/analysis, can apply to estimate the 3-dimensional geological structure.
Kawaguchi, Masanao; Nakanishi, Tatsuro; Kishi, Hirokazu; Nobuto, Jun*; Yamada, Tsutomu*; Fujita, Tomoo; Hatanaka, Koichiro
JAEA-Data/Code 2012-007, 250 Pages, 2012/11
JAEA-Data-Code-2012-007.pdf:20.55MB
Cementitious materials are commonly used for rock support, lining, and grouting, their pH plume are considered to have an adverse effect on long-term safety of a geological disposal system. In addition, during the emplacement of waste package with buffer material, it is required to limit amount of groundwater inflow to a certain level by grouting. Therefore, it is necessary to develop new grout materials with penetrability for smaller fractures. We have developed new grout materials, which have better penetrability and are environmentally more friendly than exinting cementitious grout materials since FY 2007. This sequel report shows the most appropriate composition and the penetration characteristic of new grout materials to be suitable for the experiment based on the result of indoor test carried out after FY 2008.
Amazawa, Hiroya; Sakai, Akihiro; Nakata, Hisakazu; Hara, Hironori; Kurosawa, Ryohei; Yamamoto, Masayuki*; Kawata, Yosuke*; Sakamoto, Yoshiaki
JAEA-Technology 2012-031, 338 Pages, 2012/10
JAEA-Technology-2012-031.pdf:19.43MB
JAEA is responsible for siting a proper location to establish new disposal facilities with siting criterion and procedure, in consideration of transparency and impartial for the siting process, based on Plan Concerning the Disposal Business Execution. As a part of the study to draw up siting criterion and procedure, Sensitivity analysis of the disposal facilities from the viewpoint of dose evaluation and cost estimation under various siting condition will be carried out. Therefore, Conceptual design of disposal facilities as a reference case is necessary. The basic condition of the design conforms to the property, quantity, radioactivity of waste packages, technical standards and likely siting condition. This report summarizes the results of the reasonable design of our disposal facilities and the layout of the place of activity where the disposal facilities and associated facilities to be installed.
Shibata, Masahiro; Sawada, Atsushi; Tachi, Yukio; Makino, Hitoshi; Hayano, Akira; Mitsui, Seiichiro; Taniguchi, Naoki; Oda, Chie; Kitamura, Akira; Osawa, Hideaki; et al.
JAEA-Research 2012-032, 298 Pages, 2012/09
JAEA-Research-2012-032.pdf:33.68MB
JAEA and NUMO have conducted a collaborative research work which is designed to enhance the methodology of repository design and performance assessment in preliminary investigation phase. The topics and the conducted research are follows; (1) Study on selection of host rock: in terms of hydraulic properties, items for assessing rock property, and assessment methodology of groundwater travel time has been organized with interaction from site investigation. (2) Study on development of scenario: the existing approach has been embodied, in addition, the phenomenological understanding regarding dissolution of and nuclide release from vitrified waste, corrosion of the overpack, long-term performance of the buffer are summarized. (3) Study on setting nuclide migration parameters: the approach for parameter setting has been improved for sorption and diffusion coefficient of buffer/rock, and applied and tested for parameter setting of key radionuclides. (4) Study on ensuring quality of knowledge: framework for ensuring quality of knowledge has been studied and examined aimed at the likely disposal facility condition.