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Tanimoto, Masataka; Taguchi, Taketoshi; Okada, Manabu; Hanawa, Yoshio; Tsuchiya, Kunihiko; Ikeda, Masayuki*; Fujimoto, Yoichi*; Kotov, V.*; Kenzhin, E.*; Kenzhin, Y.*
JAEA-Technology 2011-001, 39 Pages, 2011/03
JAEA-Technology-2011-001.pdf:4.15MB
It is important problem to recycle the irradiated beryllium from the points of effective use of resources, reduction of radioactive waste and nuclear nonproliferation. The recycling of the irradiated beryllium has been considered as the part of the development of Irradiation technology for JMTR refurbishment and restart. The ISTC regular project (K-1566) on recycling technology of irradiated beryllium has been carried out in the Institute of Atomic Energy (IAE), National Nuclear Center of Republic of Kazakhstan (NNC-RK). This paper is described on the transport procedure and transport results of the irradiated beryllium from Japan Atomic Energy Agency (JAEA) to IAE, NNC-RK under the ISTC project.
Takegami, Hiroaki; Ishikura, Shuichi*; Terada, Atsuhiko; Inagaki, Yoshiyuki
JAEA-Technology 2011-002, 41 Pages, 2011/03
JAEA-Technology-2011-002.pdf:5.08MB
The IS process is the hydrogen production method which used the thermochemical reaction cycle of sulfuric acid and iodyne. The sulfuric acid decomposer, which is one of the important equipment of the IS process, is the equipment to heat with hot helium and for the sulfuric acid of 90 wt% to evaporate. The heat exchanger is required to be pressure-resistant structure because it uses high-pressure helium of 4 MPa, and the material is required to have heat resistance and corrosion resistance with high temperature sulfuric acid more than 700 
C. Therefore, silicon carbide (SiC) was selected from the corrosion experiment as the most excellent material. However, the structure design technique of ceramics structures is not serviced as the standard. In this report, the structural design technique was studied by the material strength characteristic of the ceramics into consideration.
Satoyama, Tomonori; Kishimoto, Katsumi; Hoshi, Akiko; Takaizumi, Hirohide; Tsutsumi, Masahiro; Inanobe, Hiroshi; Yoshimori, Michiro
JAEA-Technology 2011-003, 53 Pages, 2011/03
JAEA-Technology-2011-003.pdf:1.6MB
In Nuclear Science Research Institute, clearance activities for extremely low-level radioactive concrete debris, which were generated from the modification activities of JRR-3 from FY 1985 to FY 1989 and now are stored in the waste storage facility NL, have been carried out in order to plan reasonable disposal and effectively reusing of concrete waste, moreover to secure storage capacity at the waste storage facilities. Method for measuring and evaluating of radioactivity concentration was applied for approval of Minister of MEXT on November 8, 2007, approved on July 25, 2008. After that the necessary equipments for clearance works were equipped and operational safety progress and manuals for clearance works were prepared. So clearance works were started in FY 2009. This report summarizes the method for measuring and evaluating of radioactivity concentration for concrete generated from modification activities of JRR-3.
Kanamori, Masashi; Suto, Toshiyuki; Tanaka, Kenichi*; Takada, Jun*
JAEA-Technology 2011-004, 12 Pages, 2011/03
JAEA-Technology-2011-004.pdf:0.97MB
In the previous report "A Study on Dose Control for JCO Criticality Accident Termination" (JAEA-Technology 2009-043), we discussed how to control the dose received during the termination work of the criticality accident. In this paper, we focused on the difference of the way in which dose rate attenuates between within 100 m from the source point and beyond 100 m and discussed the validity of using log-log plotting/semi-log plotting of dose rate - distance relation in order to extrapolate the dose rate at work place near the criticality accident point. In addition, we studied on the effect of the number of dose rate measurement data to be used for extrapolation. We recommend that about 10 mSv which is a half of 20 mSv annual dose limit should be used as worker's dose control target for the high neutron dose field work to ensure enough safety margin considering the following three points; (1) annual dose limit for workers, (2) dose received before, (3) measurement error.
Nakanishi, Chika; Sato, Sohei; Furuno, Akiko; Terada, Hiroaki; Nagai, Haruyasu; Muto, Shigeo
JAEA-Technology 2011-005, 141 Pages, 2011/03
JAEA-Technology-2011-005.pdf:6.13MB
Nuclear Emergency Assistance and Training Center (NEAT) has developed the response system to evaluate the radiological consequences of an accident on a nuclear power plant or nuclear weapons testing around Japan and to support prediction of radioactive material distributions by using an atmospheric dispersion model on the framework of the Response Assistance Network (RANET) which is established by the International Atomic Energy Agency (IAEA). For the enhancement of assistance capability to external organizations at a nuclear or radiological emergency, NEAT will introduce a computer-based emergency response system, "Worldwide version of System for Prediction of Environmental Emergency Dose Information: WSPEEDI 2nd version (WSPEEDI-II)" developed by Division of Environmental and Radiation Sciences. This manual covers the overview of the system and configuration parameters as the basic knowledge needed for operating the systems.
Sakaguchi, Shinobu; Tachibana, Ikuya; Koshino, Katsuhiko; Shirozu, Hidetomo; Shirai, Nobutoshi; Imamoto, Nobuo; Tomita, Tsuneo; Tobita, Hiroo; Yamanaka, Atsushi; Kobayashi, Daisuke; et al.
JAEA-Technology 2011-006, 24 Pages, 2011/03
JAEA-Technology-2011-006.pdf:3.07MB
In the Niigataken Chuetsu-oki Earthquake on 2007, observed earthquake motion exceeded design base at the Kashiwazaki Kariwa nuclear plant. However, there was no earthquake damage in safety important equipments to stop reactor, to cool reactor, and to contain radioactive materials. One of this reason is said that many safety margin are included in the design and the permissible value. To know more accurate safety margin, shearing force examinations for the base bolts were conducted. In examinations, delegate test-bolts were made; the test bolts were selected from heavier equipment in Tokai Reprocessing Plant. In this report, the shearing strength obtained from the examinations shows more accurate safety margin.
Ito, Chikara; Ito, Hideaki; Ishida, Koichi; Aoyama, Takafumi
JAEA-Technology 2011-007, 56 Pages, 2011/06
JAEA-Technology-2011-007.pdf:9.2MB
In the experimental fast reactor Joyo, measurement for characterizing and predicting the deposition condition and the condition change of the corrosion product (CP) that is the major radiation source in equipments and piping of primary cooling system has been carried out regularly from early period of reactor operation. Cooling system modification work with the shift to the MK-III core was carried out after the last measurement that was carried out, and the main equipments such as intermediate heat exchangers were replaced. This measurement in this report was carried out at after the 2nd cycle operation of the MK-III core which started formal operation.
Shimizu, Shigeru; Sawahata, Tadahiro*; Kajimoto, Yoichi; Shikaze, Yoshiaki; Yoshihara, Yasuaki*; Tatebe, Yosuke
JAEA-Technology 2011-008, 53 Pages, 2011/06
JAEA-Technology-2011-008.pdf:2.91MB
The International Standard, ISO 4037-1, is applied worldwide for setting the condition of X-ray reference fields to be used for the performance test of radiation measuring instruments for radiation protection. X-ray reference fields were established at the Facility of Radiation Standard in Nuclear Science Research Institute in 2003 and had been operated. Recently, we rebuilt the X-ray reference fields by replacing the X-ray tube with a new model due to the damage of the old one of the middle-hard X-ray irradiation device. We have established three series of medium-hard X-ray reference fields, Narrow, Wide and High air-kerma series with 27 radiation qualities, based on ISO 4037-1. This article described quality of the X-ray fields, X-ray spectra, conversion coefficients to the dose equivalent from Air-kerma and comparison with the quality of ISO 4037-1 in the X-ray fields of medium-hard X-ray voltages ranging from 20 kV to 300 kV. Result of experiments, these X-ray reference fields were well agreed with the condition of the international standard. As a result, these X-ray reference fields were found to be used to carry out the performance test, standard irradiation based on the international standard, and an intercomparison experiment with the reference laboratories in the world.
Mizuno, Mineo; Haga, Tetsuya; Sudo, Katsuo; Takeuchi, Kentaro; Okita, Takatoshi; Kihara, Yoshiyuki
JAEA-Technology 2011-009, 100 Pages, 2011/06
JAEA-Technology-2011-009.pdf:32.59MB
Crystalline cellulose granulated to sizes from 70 to 100 micron was previously used as pore former (PF) to fabricate low density MOX pellets for MONJU. When sale of Avicel was discontinued, it became necessary to find a substitute PF. Then, small scale fabrication tests of MOX pellets with candidate PFs were conducted. Three candidate PFs, cellulose beads, CEOLUS and CELPHERE, were examined in the tests. The results are summarized below. (1) The CELPHERE gave MOX pellets with almost same density depression performance as pellets using Avicel, and standards deviation of the sintered densities of pellets was the smallest. (2) MOX pellets with CELPHERE had lower incidence of observable defects. (3) MOX pellets with CELPHERE had almost the same O/M as pellets with Avicel. (4) MOX pellets with CELPHERE had lower incidence of micro cracks. (5) The densification amount of pellets with CELPHERE was almost the same as that of pellets with Avicel. It was concluded CELPHERE was a suitable substitute for Avicel.
Shibahara, Yuji; Tachibana, Mitsuo; Izumi, Masanori; Nanko, Takashi
JAEA-Technology 2011-010, 44 Pages, 2011/06
JAEA-Technology-2011-010.pdf:2.43MB
Manpower needs for the preparation and clean-up process on the dismantling of equipments in FUGEN 3rd/4th feedwater heater room conducted in 2008 was calculated with the management data evaluation system: PRODIA Code, and it was inspected whether the conventional evaluation model had the applicability for large nuclear facilities such as FUGEN or not. It was confirmed that the conventional evaluation model had no applicability for FUGEN causing by the difference in the plant scale between JPDR and FUGEN bringing the expanding of working area. The difference between the actual data and the calculated value was improved by the reviewing of the evaluation model, and this reviewing process also brought the new evaluation model.
Kanayama, Fumihiko; Hagiya, Kazuaki; Sunaoshi, Mizuho; Muraguchi, Yoshinori; Satomi, Shinichi; Nemoto, Koichi; Terunuma, Akihiro; Shiraishi, Kunio; Ito, Shinichi
JAEA-Technology 2011-011, 36 Pages, 2011/06
JAEA-Technology-2011-011.pdf:2.53MB
Dismantling activities of equipments in JAERI's Reprocessing Test Facility (JRTF) started from 1996 as a part of decommissioning of this facility. Removing out of the large liquid waste storage tank LV-2 as a whole tank without cutting in pieces from the annex building B to confirm safety and efficiency of this method started from 2006. After preparatory works, ceiling of LV-2 room was opened, and LV-2 was transferred. Useful data were collected on manpower, radiation control and waste amount through the preparatory works, and work efficiency was analyzed by use of these data.
Kimura, Akihiro; Tanimoto, Masataka; Ishida, Takuya; Tsuchiya, Kunihiko; Hasegawa, Yoshio*; Hishinuma, Yukio*; Suzuki, Masashi*
JAEA-Technology 2011-012, 17 Pages, 2011/06
JAEA-Technology-2011-012.pdf:1.72MBJP, 2010-263801 Patent publication (In Japanese)
PZC (Poly-Zirconium Compound) was developed as adsorbent of molybdenum for 
Mo-
Tc generator. However, PZC has some faults. So, new adsorbent based on titanium (PTC), was developed for getting rid of faults. This time, Mo adsorption and Tc elution tests with PZC and PTC were carried out. As a result, the Mo adsorption performance of the PTC was lower than PZC, on the other hand, Tc elution performance of the PTC was higher than PZC.
Ohashi, Hirofumi; Sato, Hiroyuki; Tazawa, Yujiro; Yan, X.; Tachibana, Yukio
JAEA-Technology 2011-013, 67 Pages, 2011/06
JAEA-Technology-2011-013.pdf:3.13MB
In the present study, major specifications of a small-sized HTGR system (HTR50S) aiming to deploy in developing countries in 2030s are investigated. In addition, technology to be demonstrated (e.g. increasing power density, reduction of the number of uranium enrichment in the fuel, increasing the burn up, side-by-side arrangement between the reactor pressure vessel and the steam generator) are identified. Also, a system design of HTR50S which offers the capability of electricity generation, cogeneration of electricity and steam for a district heating and industries, is performed. Furthermore, a market size for small-sized HTGR systems are estimated.
Yonekawa, Minoru; Kato, Yoshiaki; Taguchi, Taketoshi; Sozawa, Shizuo
JAEA-Technology 2011-014, 16 Pages, 2011/06
JAEA-Technology-2011-014.pdf:3.6MB
The Japan Materials Testing Reactor (JMTR) is proceeding with the preparation for re-operation on 2011. The facilities and equipments in the hot laboratory had been improved from 2007 in order to deal with new requests for post irradiation examinations after re-operation of JMTR. Improvement of concrete cells and irradiation facilities are planned to be completed until the end of FY 2010 in order to carry out the post irradiated examination for research on high burnup fuel (maximum burn up: 110 GWd/t). In this report, improvement of concrete cells and irradiation facilities to handle the high burnup fuel in the hot laboratory is summarized.
Sudo, Tomoyuki; Mimura, Ryuji; Ishihara, Keisuke; Satomi, Shinichi; Myodo, Masato; Momma, Toshiyuki; Kozawa, Kazushige
JAEA-Technology 2011-015, 24 Pages, 2011/06
JAEA-Technology-2011-015.pdf:2.28MB
The super compactor in the Advanced Volume Reduction Facilities (AVRF) treats metal wastes mainly generated from research reactors in the Nuclear Science Research Institute of JAEA. Those wastes are compacted from one third to one fourth with maximum 2,000-ton force. In the trial operation using simulated wastes, some technical problems were found to be improve for the stable operation. One problem is the motion mechanism for carrying wastes before and after compaction. The other problem is the mechanism for treating the irregular supercompacted products. In this report, we describe the detail and the result of improvement on those problems for the stable operation in the super compactor.
Onuma, Yuichi; Inoue, Shuichi; Okada, Yuji; Sakuta, Yoshiyuki; Kanno, Masaru
JAEA-Technology 2011-016, 13 Pages, 2011/06
JAEA-Technology-2011-016.pdf:3.58MB
The Japan Material Testing Reactor (JMTR) in the Oarai Research and Development Center has been continued to improvement of the temperature control capability for irradiation specimens is being carried out for applying the JMTR. The JMTR had developed and been utilized the High accuracy capsule temperature control system had developed by adopting a feed forward control using measured reactor output power, and have been utilized in the JMTR. Based on the development knowledge, the advanced capsule temperature control system is now under development taking into consideration of additional function and so on so as to obtain high quality irradiation test data in the world in order to contribute the nuclear technology development.
Editorial Committee of Refining and Conversion Facility Decommissioning Results
JAEA-Technology 2011-017, 77 Pages, 2011/06
JAEA-Technology-2011-017.pdf:5.58MB
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, and all equipments in radiation controlled area will be dismantled by the 2011 fiscal year. This report describes the master plan of this decommissioning and shows as the progress in first half year of 2010FY, the actual time schedule, the method of decommissioning, the decommissioning progress appearance with photographs, work rates of each room / each worker class, and the quantity of dismantled materials and secondary wastes.
Tochio, Daisuke; Saito, Kenji; Shimazaki, Yosuke; Nakagawa, Shigeaki
JAEA-Technology 2011-018, 43 Pages, 2011/06
JAEA-Technology-2011-018.pdf:2.44MB
In the HTTR, safety demonstration tests are performed after the first criticality achieved in 1998. Thermal load fluctuation test of the heat utilization system using the HTTR are planned in order to demonstrate reactor system stability in the case of thermal load fluctuation of the heat utilization system in HTGR hydrogen production system. So pre-investigations of thermal-load fluctuation tests using the HTTR are conducted to investigate the available test condition. As the result, it is confirmed that the ACL fan stopping tests can be conducted under a condition and provide the data needed to verify the plant dynamics simulation code for future HTGR.
Tc master-milker; Comparison with PZC based wet methodIshitsuka, Etsuo; Yamabayashi, Hisamichi*; Tanase, Masakazu*; Fujisaki, Saburo*; Sato, Norihito*; Hori, Naohiko; Awaludin, R.*; Gunawan, A. H.*; Lubis, H.*; Mutalib, A.*
JAEA-Technology 2011-019, 18 Pages, 2011/06
JAEA-Technology-2011-019.pdf:2.61MB
Feasibility study of sublimation type Tc master-milker was carried out as a Mo/T production development with the JMTR. As the feasibility study, the experimental equipment for sublimation method and wet method with PZC based Tc solution were tentatively manufactured, and their properties as the master-milker were investigated by comparing two methods with each other. As a result, it was found that the Tc recovery rate and process time of the sublimation method were about 80% and 1.5 hour, respectively, and the similar values were observed with the wet method. Superior points of the sublimation method are easier operation and reusability of the used MoO
comparing with the wet method. On the other hand, disadvantageous point is that the Tc recovery rate decreases with the increase of treating amount of MoO.
Ichikawa, Shoichi; Haga, Hiroyuki; Kikukawa, Kiyohide*; Fukasaku, Hironobu*; Kurosawa, Yoichi*; Katsuyama, Kozo; Maeda, Koji; Nagamine, Tsuyoshi
JAEA-Technology 2011-020, 32 Pages, 2011/07
JAEA-Technology-2011-020.pdf:6.56MB
Disassembling technique of the driver fuel assembly irradiated in the experimental fast reactor JOYO has been established at Fuel Monitoring Facility in JAEA. This technique made it possible to remove the fuel pins from the driver fuel assembly without the fuel pin sectioning. After disassembling the fuel assembly, some selected fuel pins can be reassembled into the new irradiation vehicle for the continuous irradiation at JOYO. This technique enables us to obtain the irradiation data of high burn-up fuel and high neutron dose material.
Shibahara, Yuji; Ishigami, Tsutomu; Morishita, Yoshitsugu; Yanagihara, Satoshi; Arita, Yuji*
JAEA-Technology 2011-021, 35 Pages, 2011/07
JAEA-Technology-2011-021.pdf:4.52MB
To implement reasonable decommissioning of nuclear facilities, it is necessary and important to beforehand evaluate project management data as well as to select 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 FY2009, 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 the research is to construct a methodology for selecting 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 feed water heater at Fugen, and an optimum scenario was discussed using the multi-criteria decision analysis. This report describes the results of the joint research in FY2009.
Ito, Masayasu; Kawamata, Kazuo; Tayama, Yoshinobu; Kanazawa, Yoshiharu; Yonekawa, Minoru; Nakagawa, Tetsuya; Omi, Masao; Iwamatsu, Shigemi
JAEA-Technology 2011-022, 44 Pages, 2011/07
JAEA-Technology-2011-022.pdf:3.29MB
Hot laboratory are facilities that execute the post irradiation examination of sample irradiated in material testing reactors etc. The handling of high burn-up fuel is scheduled in the JMTR (Japan Materials Testing Reactor) Hot Laboratory with JMTR re-operate in FY 2011. This report describes evaluation, production and installation of shielding of the hot cells in the JMTR Hot Laboratory.
Nakata, Hisakazu; Amazawa, Hiroya; Sakai, Akihiro; Arikawa, Masanobu; Sakamoto, Yoshiaki
JAEA-Technology 2011-023, 54 Pages, 2011/08
JAEA-Technology-2011-023.pdf:6.4MB
JAEA will settle on near surface disposal facilities with and without engineered barriers for radioactive wastes. Both of them are so called concrete pit type and trench type, respectively. Technical standards of constructing a disposal facility based on Law for the Regulations of Nuclear Source Material, Nuclear Fuel Material and Reactors have been regulated partly by referring to that of Waste Management and Public Cleansing Law. This means that the concrete pit type and the trench type facility resemble an isolated type and a non leachate controlled type final disposal site, respectively. On the other, we plan to design a disposal facility with a liner system corresponding to a leachate controlled type final disposal site. By current nuclear related regulations, There are no technical standards of constructing the disposal facility with the liner system. So we investigate the function of the liner system in order to design a proper liner system for the trench type disposal facility.
Editorial Committee of Refining and Conversion Facility Decommissioning Results
JAEA-Technology 2011-024, 67 Pages, 2011/09
JAEA-Technology-2011-024.pdf:4.88MB
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 describes the master plan of this decommissioning and shows as the progress in latter half year of 2010FY, the actual time schedule, the method of decommissioning, the decommissioning progress appearance with photographs, work rates of each room / each worker class, and the quantity of dismantled materials and secondary wastes.
Sukegawa, Takenori; Shimada, Taro; Ito, Takeshi*; Tanaka, Tadao
JAEA-Technology 2011-025, 41 Pages, 2011/09
JAEA-Technology-2011-025.pdf:5.83MB
Nuclear facility sites after decommissioning are allowed to be released from nuclear safety regulations after confirming that sites have been decontaminated to acceptable levels. In-situ measurement with the use of a portable Ge detector is a suitable technology for confirmatory survey. A conservative method to evaluate residual radioactivity was proposed in this study. In the evaluation method concept, all of the radionuclide, which are in reality distributed across the area of interest, is assumed to be the single point source located at the furthest position of the area from a Ge detector. Based on this assumption, the detectable minimum time of the interest radionuclide were predicted by the calculation. If radiation from the point source is not detected for longer than the predicted detectable time, it can be proven that the radioactivity remaining in the interest area is lower than the radioactivity corresponding to the assumed point source. Results of the field test in JAEA site indicate that the proposed method was reasonable for the conservative evaluation of residual radioactivity.
Iwamoto, Yosuke; Satoh, Daiki; Endo, Akira; Sakamoto, Yukio; Kureta, Masatoshi; Kugo, Teruhiko
JAEA-Technology 2011-026, 18 Pages, 2011/09
JAEA-Technology-2011-026.pdf:4.05MBJAEA-Technology-2011-026(errata).pdf:0.24MB
The present report discusses the effect of dose rate reduction by soil decontamination in order to make a remediation strategy for contaminated environment by radionuclides discharged by the accident at the Fukushima Daiichi Nuclear Power Plant. The relation between area of soil decontamination and dose rate reduction for lands considered to be typical residences, public facilities and schools has been analyzed using the particle and heavy ion transport code PHITS, and an analytical model to assess the dose reduction rate with a simple equation was also suggested from the calculation results of PHITS. In the case of DF (Decontamination Factor) = 10 and decontamination radius = 100 m for the soil uniformly contaminated by Cs-137, the dose rate at the center of decontamination area is decreased by a factor of about five compared with the dose rate before decontamination.
Kimura, Hideo; Aoyagi, Tetsuo; Sato, Taiichi; Sakai, Manabu; Hikasa, Naoki*; Suzuki, Hitoshi; Tsuji, Minoru
JAEA-Technology 2011-027, 31 Pages, 2011/09
JAEA-Technology-2011-027.pdf:2.16MB
The financial accounting and contract management system of JAEA, built on a commercial ERP package, had suffered from serious problems of high lifecycle cost, poor response, and lack of extensibility, due to the too much customization to the ERP package, and disorganized software structure. To solve those problems, three approaches were applied; (1) conducting thorough analysis of business flow and fit/gap, which enabled removing all customization brought to the ERP package; (2) dividing the system into subsystems, and clearly defining interfaces between the subsystems, which increases the transparency, extensibility and performance of the system; (3) outsourcing the development of the subsystems to multiple venders to reduce the development cost. Those approaches can be useful for developing business information systems using commercial software to save time and cost, while meeting the unique requirements of an organization.
Tsuji, Tomoyuki; Kameo, Yutaka; Sakai, Akihiro; Amazawa, Hiroya; Takahashi, Kuniaki
JAEA-Technology 2011-028, 66 Pages, 2011/11
JAEA-Technology-2011-028.pdf:3.16MB
In order to dispose of low-level radioactive wastes generated from various nuclear facilities in JAEA, we need to establish practical evaluation methods to determine radioactivity concentrations of the important nuclides for safety assessment on disposal of radioactive wastes. In this report, we have studied on establishing the practical evaluation methods such as the scaling factor method for bituminized products generated at Nuclear Science Research Institute and also summarized subjects for establishment of the practical evaluation methods for the bituminized products.
Shinohara, Masanori; Yanagi, Shunki; Tochio, Daisuke; Shimazaki, Yosuke; Nojiri, Naoki; Owada, Hiroyuki; Sato, Nao; Sagawa, Hiroshi; Umeda, Masayuki
JAEA-Technology 2011-029, 39 Pages, 2011/12
JAEA-Technology-2011-029.pdf:3.03MB
JAEA plans and performs the safety demonstration test using the HTTR to develop High Temperature Gas Reactor technologies. Cold test of the loss of forced cooling was conducted prior to the safety demonstration test, to check test procedure and plant behavior. Cold test consists of two phases, Phase1, 1 or 2 Vessel Cooling System (VCS) terminates, in the Phase2, all 3 Gas circulators and 1 VCS terminates. Cold test could confirm test process, and obtain data necessary to analysis and 2-dimensional horizontal sectional model analysis was verified to simulate actual measurement value.
Ishikawa, Hiroyuki; Tate, Akihiro; Murakami, Tadashi*
JAEA-Technology 2011-030, 62 Pages, 2012/02
JAEA-Technology-2011-030.pdf:4.34MB
In the J-PARC network, yet we already have several kinds of systems to detect and protect network information security threats, it is also important and necessary to countermeasure security vulnerabilities or holes at servers connected to the network. For such purposes, server host vulnerability inspection system is suitable. The system scans target server systems, checks running OS and server software versions on them and warns server administrators against known software vulnerabilities, if there exists. However, we suppose that it is not enough to inspect only at once at the server installation time. Regularly server administrators should do inspection, apply software patches according to its result during the server lives. In this point of view, we developed a web portal system to easily control this continual improve process of server side information security countermeasures by server administrators themselves.
Imaizumi, Tomomi; Miyauchi, Masaru; Ito, Masayasu; Watahiki, Shunsuke; Nagata, Hiroshi; Hanakawa, Hiroki; Naka, Michihiro; Kawamata, Kazuo; Yamaura, Takayuki; Ide, Hiroshi; et al.
JAEA-Technology 2011-031, 123 Pages, 2012/01
JAEA-Technology-2011-031.pdf:16.08MB
The number of research reactors in the world is decreasing because of their aging. However, the planning to introduce the nuclear power plants is increasing in Asian countries. In these Asian countries, the key issue is the human resource development for operation and management of nuclear power plants after constructed them, and also the necessity of research reactor, which is used for lifetime extension of LWRs, progress of the science and technology, expansion of industry use, human resources training and so on, is increasing. From above backgrounds, the Neutron Irradiation and Testing Reactor Center began to discuss basic concept of a multipurpose low-power research reactor for education and training, etc. This design study is expected to contribute not only to design tool improvement and human resources development in the Neutron Irradiation and Testing Reactor Center but also to maintain and upgrade the technology on research reactors in nuclear power-related companies. This report treats the activities of the working group from July 2010 to June 2011 on the multipurpose low-power research reactor in the Neutron Irradiation and Testing Reactor Center and nuclear power-related companies.
Ichikawa, Shoichi; Abe, Kazuyuki; Haga, Hiroyuki; Kajima, Hisashi*; Sakurai, Satoshi*; Katsuyama, Kozo; Maeda, Koji; Nishinoiri, Kenji
JAEA-Technology 2011-032, 46 Pages, 2012/01
JAEA-Technology-2011-032.pdf:8.46MB
The assembly technique to the capsular irradiation rig newly developed was established. In the irradiation examination, the assembling disassembling and reassembling to PFB110 "B11(1), B11(2)" and PFB140 "B14" that built in Am-MOX fuel pin was achieved. The reassembly technique by recycling the irradiation material was established in the assembly of B11(2). This time, the assembly and disassembly of B11 (1) were reported. Moreover, the assembly of B14 which improved the assembly technology of B11 (1) was reported.
Tochio, Daisuke; Saito, Kenji; Shimazaki, Yosuke; Nakagawa, Shigeaki
JAEA-Technology 2011-033, 43 Pages, 2012/02
JAEA-Technology-2011-033.pdf:16.44MB
Thermal load fluctuation test of the heat utilization system using the HTTR are planned in order to demonstrate the reactor system stability in the case of thermal load fluctuation of the heat utilization system in the HTGR hydrogen production system. In the previous report, the investigation on the ACL fan stopping tests were conducted, and it was confirmed that the tests can be conducted under several conditions and provide the data needed to verify the plant dynamics simulation code for future HTGR. In this report, the investigations on the ACL pressurized water flow rate fluctuation tests were conducted. As the result, it is confirmed that the ACL pressurized water flow rate fluctuation tests can be conducted under several conditions and provide the data needed to verify the plant dynamics simulation code for future HTGR.
Shibata, Akira; Ito, Masayasu; Takemoto, Noriyuki; Nakatsuka, Masafumi*; Ohara, Hiroshi*; Kodama, Mitsuhiro*; Tanimoto, Masataka; Tsuchiya, Kunihiko
JAEA-Technology 2011-034, 67 Pages, 2012/02
JAEA-Technology-2011-034.pdf:6.94MB
Reflector elements made from metal beryllium is widely used as neutron reflectors to increase neutron flux in test reactors. When beryllium reflector elements are irradiated by neutron, bending of reflector elements caused by swelling occurs, and beryllium reflector elements must be replaced in several years. In this report, investigation for non-destructive inspection method of metal Beryllium and experiments for Preliminary inspection to establish post irradiation examination method for research of characteristics of metal beryllium under neutron irradiation were reported.
Neutron Source Section Materials and Life Science Division
JAEA-Technology 2011-035, 536 Pages, 2012/02
JAEA-Technology-2011-035.pdf:40.3MB
One of the experimental facilities in Japan Proton Accelerator Research Complex (J-PARC) is the Materials and Life Science Experimental Facility (MLF), where high-intensity neutron beams are used as powerful probes for basic research on materials and life science, as well as research and development in industrial engineering. Neutrons are generated with nuclear spallation reaction by bombarding a mercury target with high-intensity proton beams. The neutrons are slowed down with supercritical hydrogen moderators and then extracted as beams to each experimental apparatus. The principal design of the spallation neutron source is compiled in this comprehensive report.
Nakata, Hisakazu; Amazawa, Hiroya; Sakai, Akihiro; Yamamoto, Masayuki*; Sakamoto, Yoshiaki
JAEA-Technology 2011-036, 195 Pages, 2012/03
JAEA-Technology-2011-036.pdf:12.94MB
The waste package, which Japan Atomic Energy Agency plans to dispose, must be satisfied the technical standard specified by Law for the Regulations of Nuclear Source Material, Nuclear Fuel Material and Reactors. One of the technical standards is that it must have enough strength to withstand the load when the waste package is disposed finally by a burial method. Japan Atomic Energy Agency is required to prove the compliance of the waste package with the technical standard. Accordingly we conducted the actual load test of waste containers and imitated waste package in order to evaluate the anti-load strength of them by collecting strain and displacement data. The test was carried out by the compression apparatus which can imitate the supposed loading condition in a concrete pit type disposal facility. Based on the loading test result, we evaluate that 200 liter drum (M-class) has a minimum strength of 18 kN and 1 m
cubic container has a maximum strength of 400 kN.
Nojima, Takehiro; Yasuda, Ryo; Takenaka, Nobuyuki*; Hayashida, Hirotoshi; Iikura, Hiroshi; Sakai, Takuro; Matsubayashi, Masahito
JAEA-Technology 2011-037, 33 Pages, 2012/02
JAEA-Technology-2011-037.pdf:4.12MB
We have equipped fuel cell operation system for TNRF at JRR-3 in order to visualize on performance of PEFC. Our system, which is aimed to be used in nuclear facility, is composed by various equipments that give safety in experiments such as hydrogen diluting system and purge system, etc. We confirmed normal operation of our system with JARI-standard fuel cell, and succeeded in visualizing water distribution of fuel cell on performance by our system with neutron radiography.
Kochiyama, Mami; Haraga, Tomoko; Kameo, Yutaka; Takahashi, Kuniaki
JAEA-Technology 2011-038, 26 Pages, 2012/02
JAEA-Technology-2011-038.pdf:2.94MB
A nondestructive measurement of gamma-ray emitting nuclides has been studied and Multiple gamma-ray Detection Instrument is newly constructed with 4 detection units consisting of Ge and BGO detectors. Compton scattering was decreased by the combination of Ge and BGO detectors. This instrument was applied to the detection of interested nuclides in radioactive waste sample, which contains significant amount of Co-60, and detection limit of the interested gamma-ray emitting nuclides were improved by a factor of 4 to 12 times than single gamma-ray spectrometer. As for Nb-94, the radioactivity determined from measurements using Multiple gamma-ray Detection Instrument in this sample was agreed with that determined by radiochemical analysis within 15%. It was confirmed that the instrument are useful for radioactivity determination of gamma-ray emitting nuclides in radioactive waste.
Sakai, Kenji; Sakamoto, Shinichi; Kinoshita, Hidetaka; Seki, Masakazu; Haga, Katsuhiro; Kogawa, Hiroyuki; Wakui, Takashi; Naoe, Takashi; Kasugai, Yoshimi; Tatsumoto, Hideki; et al.
JAEA-Technology 2011-039, 121 Pages, 2012/03
JAEA-Technology-2011-039.pdf:10.87MB
This report investigates the behavior, damage and restoration of a neutron source station of the MLF at the Great East Japan Earthquake and verified the safety design for emergency accidents in the neutron source station. In the MLF, after an occurrence of the Earthquake, strong quakes were detected at the instruments, the external power supply was lost, all of the circulators shut down automatically, and the hydrogen gas was released. The leakages of mercury, hydrogen and radio-activation gases did not occur. While, the quakes made gaps between the shield blocks and ruptured external pipe lines by subsidence around the building. But significant damages to the components were not found though the pressure drop of compressed air lines influenced on a target trolley lock system and so on. These results substantiated the validity of the safety design for emergency accidents in the source station, and suggested several points of improvement.
Kinoshita, Hidetaka; Wakui, Takashi; Matsui, Hiroki; Maekawa, Fujio; Kasugai, Yoshimi; Haga, Katsuhiro; Teshigawara, Makoto; Meigo, Shinichiro; Seki, Masakazu; Sakamoto, Shinichi; et al.
JAEA-Technology 2011-040, 154 Pages, 2012/03
JAEA-Technology-2011-040.pdf:8.08MB
In the MLF, relatively high level irradiated components will be generated. Therefore, these components can not be kept in standard facilities. For the irradiated components at the MLF, the storage plan using the facilities in the Nuclear Science Research Institute has been studied, but the concrete plan is not decided yet. In this report, outline of the components, prehistory of the studying for storage, schedule of the component generation and status of the possible facility, which is a hot laboratory, are described. Resulting from the comparison between the generation schedule and the plan of the hot laboratory, the difference is very large. Present status of the hot laboratory and the cost estimation of the modification to use for storage of the MLF components were studied. Using the hot laboratory seems not to have advantage from the view point of cost and modification method. Therefore, the study on a new storage facility construction will be started as soon as possible.
Suwa, Masayuki; Isaka, Koji; Ouchi, Satoshi; Goto, Shingo; Ikekame, Yoshinori; Terakado, Yoshibumi
JAEA-Technology 2011-041, 35 Pages, 2012/03
JAEA-Technology-2011-041.pdf:7.11MB
JRR-3 process control computer system is used to monitor and control various process parameters such as flow rates, temperatures, pressures and so on, and operate many reactor components such as cooling pumps and valves. The system has been under aging degradation at this time and the renewal of the system has become indispensable. The renewal work has planned, paying a due consideration to minimizing renewal costs and duration, to be separated in three stages. This paper describes the renewal plan and renewal works of main part of the system.
Kawakami, Takeshi; Yamamoto, Kazuya; Fukumoto, Masahiro
JAEA-Technology 2011-042, 56 Pages, 2012/03
JAEA-Technology-2011-042.pdf:3.17MB
This work evaluated the dynamic traffic flow of evacuees' cars during the evacuation drill with family car conducted in the Ibaraki Prefecture Comprehensive Nuclear Disaster Exercise 2010. The opinion survey was also conducted to participants to get the data of choice of measures for evacuation. Consideration based on the survey of this drill revealed important outcomes as follows. (1) The evacuation routes should be chosen more than one per one residential district from the roads including low capacity road to ease traffic congestion and to secure substitute route. (2) Taking into account traffic control and guiding at the intersections on the evacuation routes by policemen and staffs is very important to make the vehicles of evacuees running smoothly. (3) Considering of the capacity and the gate size of the parking of reception center is very important to make the stream of vehicles smooth when Reception centers are chosen. (4) Considering of the effect from experiments of participants is important for the opinion surveys to get the choice of measures of evacuation. (5) The opinion surveys about evacuation from nuclear disaster should be done in the wide area including the outside of the evacuation zone.