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JAEA Reports

Comprehensive safety assessments of MONJU taking into account the accident at Fukushima Dai-ichi Nuclear Power Station of Tokyo Electric Power Company

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.

JAEA Reports

Study on development of evaluation technique of in-situ tracer test in Horonobe Underground Research Laboratory Project (Contract research)

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 ${it in-situ}$ 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 ${it in-situ}$ 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.

JAEA Reports

Applicability study of numerical analysis for coupled mechanical and hydrological processes by drift excavation (Contract research)

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 ${it in-situ}$ 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.

JAEA Reports

Evaluation of oxidation characteristics of fine-grained graphites (IG-110 and IG-430) for very high temperature reactor; Changes in density distribution and compressive strength caused by air-oxidation

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 520-900$$^{circ}$$C, 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 $$^{circ}$$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.

JAEA Reports

Animal study on biological responses by radon inhalation making use of waste rock which contains feeble activity of uranium (Joint research)

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.

JAEA Reports

Study on evaluation methodology for groundwater flow based on geochemical data, 2; Case study for Horonobe area (Contract research)

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/$$delta$$$$^{18}$$O ratios was carried out in case of Horonobe district, where geochemical data is now being stored.

JAEA Reports

Study on evaluation method for gas entrainment and vortex cavitation phenomena; Evaluation of gas entrainment behavior in large-scale test and development of proto-type evaluation method for vortex cavitation

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.

JAEA Reports

Study on numerical simulation of bubble and dissolved gas behavior in liquid metal flow

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.

JAEA Reports

Dissolutions of oxide dispersion strengthened ferritic steels in various nitric acid solutions, 2; The Amount of the corrosion products in the dissolution process

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.

JAEA Reports

Proliferation resistance of nuclear fuel cycles with transmutation

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.

JAEA Reports

Basic study on flow separation phenomenon in cooling system piping in fast reactors; Clarification of complex flow structure in a multi-elbow in a high Reynolds number regime (Joint research report in JFY2008 and JFY2009)

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.

JAEA Reports

Advancing an evaluation methodology to assess the potential effects of uplift, erosion, and climate and sea-level changes on HLW disposal; Modeling geomorphic change caused by fluvial erosion in Japan

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.

JAEA Reports

Estimation of thermodynamic properties of gases affecting aerosol transport behaviors in boiling accident of reprocessed liquid wastes at fuel reprocessing facilities

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$$_{3}$$ 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$$_{3}$$, NO$$_{2}$$ and N$$_{2}$$O$$_{4}$$. Recommended values are discussed for applying those existing code to boiling accident.

JAEA Reports

Study on geology on the Mizunami Underground Research Laboratory Project; Geology and geological structure from G.L. -300m to G.L. -500m

Tsuruta, Tadahiko; Sasao, Eiji; Kawamoto, Koji; Kuboshima, Koji; Ishibashi, Masayuki

JAEA-Research 2013-014, 35 Pages, 2013/11

JAEA-Research-2013-014.pdf:12.15MB

JAEA is performing the Mizunami Underground Research Laboratory (MIU) Project in order to establish comprehensive techniques for the investigation, analysis and assessment of the deep geological environment in the fractured crystalline rock. The Project has three overlapping phases with a total duration of about 20 years, and is under the Phase II (Construction phase) and the Phase III (Operation phase). One of the Phase II goals is set up to develop and revise models of the geological environment using the investigation results, and to determine and assess changes in the geological environment in response to excavation. This report aims compiling the study on geology and geological structure from G.L. -300m to G.L. -500m, excavated in the fiscal years from FY2008 to FY2012, and provides the fundamental information on the geology and geological structure for future study and modelling of geological environment. The compiling data are utilized in the updating of the geological models.

JAEA Reports

Studies on the reconstruction of the concept of rock mass around the tunnel; Fiscal year, 2012 (Contract research)

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$$sim$$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.

JAEA Reports

Effects of Misasa hot spring water on the growth of vegetables, 2 (Joint research)

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.

JAEA Reports

Development of the conductive glove for glove box operation; Production of prototypes and their experimental results

Kodato, Kazuo; Enuma, Masahito; Kawasaki, Takeshi; Nogami, Yoshitaka; Kaneko, Kazunori; Kimura, Masanori*; Yasumori, Tomokazu*

JAEA-Research 2013-017, 45 Pages, 2014/02

JAEA-Research-2013-017.pdf:3.98MB

The glove used at glove boxes in the nuclear fuel plants is usually made with Chlorosulfonated polyethylene rubber. The rubber is excellent in terms of resistance to radiation because it has no double bond in its main chain of the component, however, it deteriorates rapidly in high dose environment such as direct contact of alpha ray1). Plutonium oxide powder is treated in glove boxes at plutonium fuel facilities where the alpha ray from plutonium oxide power attached on surface of a glove causes the deterioration of the rubber. Therefore the effective method for prevent of the rapid deterioration is to decrease the amount of attached powder, and the glove with conductive property which can prevent static generation on its surface has been developed and tested. The results showed that the rubber has less adherent property to powder compared with conventional one.

JAEA Reports

Development of 3D reconstruction technology using captured images; Study of matching method and preliminary examination

Kamiji, Yu; Akai, Naoki*; Ozaki, Koichi*; Ito, Chikara

JAEA-Research 2013-018, 18 Pages, 2013/11

JAEA-Research-2013-018.pdf:2.1MB

Preliminary examination of image processing was conducted using existing reactor inside images through a fiber scope in order to confirm applicability of 3D-mapping in a reactor as a part of development of 3D-measurement technology. The Upright SURF (Speeded Up Robust Features) was used to find corresponding points between two captured images. In case of images showing many similar textures or lack of texture, it was difficult to find corresponding points using SURF only. By coupling with a canny algorithm to detect edges of the inside structure, it was found that 3D-structure could be measured for rectilinear objects. Also, image acquisition model was examined in order to clarify camera specs.

JAEA Reports

Development of geological models in the Mizunami Underground Research Laboratory Project; Updating results of "Shaft460 geological model" and "shaft500 geological model" in Phase 2

Ishibashi, Masayuki; Sasao, Eiji; Kuboshima, Koji; Matsuoka, Toshiyuki

JAEA-Research 2013-019, 31 Pages, 2013/11

JAEA-Research-2013-019.pdf:11.64MB

Japan Atomic Energy Agency at Tono Geoscience Center is developing a geoscientific research project named the Mizunami Underground Research Laboratory (MIU) project in crystalline rock environment in order to establish scientific and technological basis for geological disposal of HLW. Geoscientific research at MIU is planned to be carried out in three phases; Surface-based Investigation Phase (Phase 1), Construction Phase (Phase 2) and Operation Phase (Phase 3). Currently, the project is under the Construction Phase (Phase 2) and the Operation Phase (Phase 3). In the phase 2, the geological models have been updated six times (Shaft180, Pilot500, Substage200, Stage300, Shaft460 and Shaft500 geological model) based on the increasing data. The updating result from Shaft180 geological model to Stage300 geological model was already published. Thus this document mainly describes Shaft460 and Shaft500 geological models at the Phase 2.

JAEA Reports

Examination of measurement method of isotopic composition of fission products in spent fuel

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.

JAEA Reports

Hydrogeochemical research and development at Mizunami Underground Research Laboratory up to 500m depth

Iwatsuki, Teruki; Yuguchi, Takashi; Omori, Kazuaki; Hasegawa, Takashi; Munemoto, Takashi

JAEA-Research 2013-021, 63 Pages, 2013/12

JAEA-Research-2013-021.pdf:13.42MB

We evaluated the Phase I - hydrogeochemical model constructed by Surface-based investigation phase (Phase I), and observed hydrogeochemical change resulting from facility construction in Phase II research. Additionally we developed investigation technique on redox condition, colloid/organics, etc. at gallery in Phase III research. Hydrogeochemical changes in sedimentary rocks and granite resulting from facility construction have been caused by the change of mixing ratio among salinity-distinct groundwaters. Multivariate numerical analysis shows that the groundwater chemistry around drifts would change to that of shallow groundwater in the future. The know-hows on hydrochemical monitoring at the hydrogeological structures and numerical analysis were summarized to infer the hydrochemical changing processes during the facility construction.

JAEA Reports

Evaluation of fission product and actinide release behaviors focusing on their chemical forms; Phase relation and fission product release behavior resulting from interaction between molten zircaloy and irradiated MOX fuel

Tanaka, Kosuke; Miwa, Shuhei; Sato, Isamu; Hirosawa, Takashi; Sekine, Shinichi; Seki, Takayuki*; Tokoro, Daishiro*; Obayashi, Hiroshi; Koyama, Shinichi

JAEA-Research 2013-022, 62 Pages, 2014/01

JAEA-Research-2013-022.pdf:33.64MB

In order to establish the method for heating tests focused on the fission product release resulting from the high temperature chemical interaction between fuel and cladding material and to obtain the novel data on fission product release behaviors, the heating test was carried out with irradiate MOX fuel pellet and cladding.

JAEA Reports

Study of hydrogeology in the Mizunami Underground Research Laboratory Project; Hydrogeological modeling and groundwater flow simulation based on data of hydraulic and geochemical impacts during the construction of the MIU facilities; FY 2010

Hishiya, Tomoyuki*; Maemura, Tsuneyuki*; Kimura, Hitoshi*; Onoe, Hironori; Saegusa, Hiromitsu; Mizuno, Takashi

JAEA-Research 2013-023, 84 Pages, 2013/11

JAEA-Research-2013-023.pdf:11.72MB

In this study, hydrogeological modeling and groundwater flow simulations have been carried out in order to construct site descriptive model using data of hydraulic responses and groundwater chemistry changes until 460 m depth of MIU excavation. As a result of this study, the effect of hydraulic conductivity and flow porosity of hydrogeological structure to hydraulic and geochemical impacts due to the MIU excavation were confirmed. In addition, trend of inflow rate into the MIU facilities and hydraulic and geochemical impacts around the MIU Construction Site caused by the MIU construction could be reproduced.

JAEA Reports

Research on removal technologies of fuel debris and in-vessel structures using laser light (I); Research plan and research activities on FY2012

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.

JAEA Reports

R&D of remote decontamination technique in reactor building (2-$$ textcircled{1} $$-1) towards the decommissioning of Fukushima Daiichi Nuclear Power plant; Results of Examinations of contaminated samples at JAEA hot laboratories

Maeda, Koji; Sasaki, Shinji; Kumai, Misaki; Sato, Isamu; Suto, Mitsuo; Osaka, Masahiko

JAEA-Research 2013-025, 123 Pages, 2014/01

JAEA-Research-2013-025-01.pdf:50.58MB
JAEA-Research-2013-025-02.pdf:61.94MB
JAEA-Research-2013-025-03.pdf:52.86MB
JAEA-Research-2013-025-04.pdf:61.52MB
JAEA-Research-2013-025-05.pdf:44.49MB

In order to clarify the situation of the contamination in the Fukushima Daiichi reactor buildings of Units 1, 2 and 3, selected samples were transported to the Oarai Engineering Center of JAEA where they were subjected to analyses to determine the surface radionuclide concentrations and to characterize the radionuclide distributions in the samples. The analysis results indicate that the situation of contamination in the building of Unit 2 was different from others, and the protective surface coatings on the concrete floors provided significant protection against radionuclide penetration. contaminants.

JAEA Reports

Research on engineering technology in the full-scale demonstration of EBS and operation technology for HLW disposal; Research report in 2010 (Joint research)

Nakatsuka, Noboru; Hatanaka, Koichiro; Sato, Haruo; Sugita, Yutaka; Nakayama, Masashi; Asano, Hidekazu*; Saito, Masahiko*; Suyama, Yasuhiro*; Hayashi, Hidero*; Honda, Yuko*; et al.

JAEA-Research 2013-026, 57 Pages, 2013/11

JAEA-Research-2013-026.pdf:7.48MB

JAEA and RWMC concluded the letter of cooperation agreement on the research and development of radioactive waste disposal in April, 2005, and have been carrying out the collaboration work described above based on the agreement. JAEA have been carrying out the Horonobe URL Project which is intended for a sedimentary rock in the Horonobe town, Hokkaido, since 2001. In the project, geoscientific research and research and development on geological disposal technology are being promoted. Meanwhile, the government (the Agency for Natural Resources and Energy, Ministry of Economy, Trade and Industry) has been promoting construction of equipments for the full-scale demonstration of engineered barrier system and operation technology for high-level radioactive waste (HLW) disposal since 2008, to enhance public's understanding to the geological disposal of HLW, using underground facility, etc. RWMC received an order of the project in fiscal year 2010 continuing since fiscal year 2008. Since topics in this project are included in the Horonobe URL Project, JAEA carried out this project as collaboration work continuing in FY 2008. This report summarizes the results of engineering technology carried out in this collaboration work in fiscal year 2010. In fiscal year 2010, part of the equipments for emplacement of buffer material was produced and a house for the equipments and apparatus was opened in the adjoining land of Public Information House of JAEA Horonobe.

JAEA Reports

Research on engineering technology in the full-scale demonstration of EBS and operation technology for HLW disposal; Research report in 2011 (Joint research)

Nakatsuka, Noboru; Sato, Haruo; Tanai, Kenji; Sugita, Yutaka; Nakayama, Masashi; Sawada, Sumiyuki*; Niinuma, Hiroaki*; Asano, Hidekazu*; Saito, Masahiko*; Yoshino, Osamu*; et al.

JAEA-Research 2013-027, 34 Pages, 2013/11

JAEA-Research-2013-027.pdf:5.84MB

Japan Atomic Energy Agency (JAEA) and Radioactive Waste Management Funding and Research Center (RWMC) concluded the letter of cooperation agreement on the research and development of radioactive waste disposal in April, 2005, and have been carrying out the collaboration work based on the agreement. JAEA have been carrying out the Horonobe Underground Research Laboratory (URL) Project which is intended for a sedimentary rock in the Horonobe town, Hokkaido, since 2001. In the project, geoscientific research and research and development on geological disposal technology are being promoted. Meanwhile, the government (the Agency for Natural Resources and Energy, Ministry of Economy, Trade and Industry) has been promoting construction of equipments for the full-scale demonstration of engineered barrier system and operation technology for high-level radioactive waste (HLW) disposal since 2008, to enhance public's understanding to the geological disposal of HLW, e.g. using underground facility. RWMC received an order of the project in fiscal year 2010 (2010/2011) continuing since fiscal year 2008 (2008/2009). Since topics in this project are included in the Horonobe URL Project, JAEA carried out this project as collaboration work continuing in fiscal year 2008. This report summarizes the results of engineering technology carried out in this collaboration work in fiscal year 2011. In fiscal year 2011, part of the equipments for emplacement of buffer material was produced and visualization test for water penetration in buffer material were carried out.

JAEA Reports

Re-interpretation of data obtained by airborne geophysical survey using helicopter

Hasegawa, Ken; Yamada, Nobuto; Endo, Yoshinobu*; Koide, Kaoru

JAEA-Research 2013-028, 83 Pages, 2013/12

JAEA-Research-2013-028.pdf:18.29MB

To evaluate the applicability of the airborne geophysical methods to granitic area, Tono Geoscience Center conducted the airborne geophysical survey using helicopter in the region of the Toki granite from 1997 to 1999. Data of electromagnetic survey, magnetic survey and radiometric survey were collected. This time, we re-interpreted these data. The following is the summary of the results obtained. (1) Electromagnetic survey; We developed the new calculation method and the data was reprocessed. As a result, it made us possible to obtain the apparent resistivity value corresponding to the rock resistivity. And the new apparent resistivity contour map clearly shows the depth changes of the granitic rock. (2) Magnetic survey; Magnetic susceptibility of the target granite is not uniform. From the viewpoint of magnetic susceptibility, the granite is divided into about five parts using a color shaded relief map. This map is a very useful tool for a qualitative interpretation of magnetic data. (3) Radiometric Survey; Some local anomalies were obtained. It is inferred that they correspond with the autocrops of the granitic rocks or the uranium deposits, not with the open fractures. These results indicate that an airborne geophysical survey using helicopter provides the useful information for planning of the geological and geophysical ground surveys.

JAEA Reports

Decontamination pilot projects for the environmental remediation of evacuation areas contaminated with radioactive materials discharged from the Fukushima Daiichi Nuclear Power Plant accident; Survey on individual doses to the inhabitants living in the areas contaminated by the accident (Contract research)

Takahara, Shogo; Iijima, Masashi; Kushida, Teruo; Shiratori, Yoshitake

JAEA-Research 2013-029, 36 Pages, 2013/12

JAEA-Research-2013-029.pdf:2.7MB

In the areas contaminated by the Fukushima Daiichi Nuclear Power Plant accident, to clarify the influences of the lifestyle habits to radiation exposures for inhabitants, we performed surveys on their behavioral patterns and measurements of their individual doses due to external exposures. In addition, an assessment model was developed and the assessments of the doses were performed based on the results of the surveys and the measurements of ambient dose equivalent rates. The assessed individual doses were compared with those measured in order to confirm the validity of the model. Clear differences were found in time spent outdoors of the inhabitants of various occupations. Significant differences in individual doses were also observed between those of indoor workers and outdoor workers. In order to assess more precisely the doses of inhabitants who continue to live in the affected areas, assessments should be performed taking into account the population-specific behavioral patterns.

JAEA Reports

Evaluation of irradiation behavior on oxide dispersion strengthened (ODS) steel claddings irradiated in Joyo/CMIR-6

Yano, Yasuhide; Otsuka, Satoshi; Yamashita, Shinichiro; Ogawa, Ryuichiro; Sekine, Manabu; Endo, Toshiaki; Yamagata, Ichiro; Sekio, Yoshihiro; Tanno, Takashi; Uwaba, Tomoyuki; et al.

JAEA-Research 2013-030, 57 Pages, 2013/11

JAEA-Research-2013-030.pdf:48.2MB

It is necessary to develop the fast reactor core materials, which can achieve high-burnup operation improving safety and economical performance. Ferritic steels are expected to be good candidate core materials to achieve this objective because of their excellent void swelling resistance. Therefore, oxide dispersion strengthened (ODS) ferritic steel and 11Cr-ferritic/martensitic steel (PNC-FMS) have been respectively developed for cladding and wrapper tube materials in Japan Atomic Energy Agency. In this study, the effects of fast neutron irradiation on mechanical properties and microstructure of 9Cr-and 12Cr-ODS steel claddings for fast reactor were investigated. Specimens were irradiated in the experimental fast reactor Joyo using the CMIR-6 at temperatures between 420 and 835$$^{circ}$$C to fast neutron doses ranging from 16 to 33 dpa. The post-irradiation ring tensile tests were carried out at irradiation temperatures.

JAEA Reports

Study on crystalline rock for evaluating method of long-term behavior; FY2012 (Contract research)

Fukui, Katsunori*; Hashiba, Kimihiro*; Tanno, Takeo; Hikima, Ryoichi; Sanada, Hiroyuki; Sato, Toshinori

JAEA-Research 2013-031, 52 Pages, 2013/12

JAEA-Research-2013-031.pdf:4.06MB

It is very important to understand the time-dependent behavior of rock for evaluating long-term mechanical stability. The purpose of this study is determining the mechanisms of time-dependent behavior of rock by the precise test, observation and measurement, to develop methods for evaluating long-term mechanical stability. This report describes the results of the activities in fiscal year 2012. In Chapter 1, we provide an overview and the background to this study. In Chapter 2, the results of a long-term creep test on Tage tuff, started in fiscal year 1997 are described. In Chapter 3, the experimental results concerning the loading-rate dependency of strength were examined to understand the time-dependency of rock. In Chapter 4, the stability of tunnels, around which rock stress is larger than that around a circular tunnel, were examined to obtain useful information on the future plan for ${it in-situ}$ tests in the underground research laboratory.

JAEA Reports

Development of non-destructive inspection method for on-site observation; Preliminary examination for internal visualization of HTTR

Takegami, Hiroaki; Terada, Atsuhiko; Noguchi, Hiroki; Kamiji, Yu; Ono, Masato; Takamatsu, Kuniyoshi; Ito, Chikara; Hino, Ryutaro; Suzuki, Keiichi*; Onuma, Hiroshi*; et al.

JAEA-Research 2013-032, 25 Pages, 2013/12

JAEA-Research-2013-032.pdf:3.56MB

We focused on a non-destructive inspection method using cosmic-ray muons as a candidate method for observation of internal the reactor from the outside of a reactor building. In this study, the applicability of this method for the reactor investigation was confirmed by a preliminary examination with High Temperature Engineering Test Reactor (HTTR). From the results of this examination, it appears that high density structures, such as the core and concrete walls, were able to observe by using muon telescope with coincidence method from the outside of the pressure vessel. Furthermore, we proposed some improvements of this muon inspection system for on-site investigation at the Fukushima Daiichi NPS.

JAEA Reports

Report on decontamination pilot projects to establish guidelines for environmental remediation of residential areas contaminated with radioactive materials discharged from the Fukushima Daiichi Nuclear Power Station Accident

Kihara, Shinji; Amazawa, Hiroya; Sakai, Akihiro; Nakata, Hisakazu; Kugo, Teruhiko; Matsuda, Norihiro; Oizumi, Akito; Sasamoto, Hiroshi; Mitsui, Seiichiro; Miyahara, Kaname

JAEA-Research 2013-033, 320 Pages, 2014/07

JAEA-Research-2013-033.pdf:119.17MB

JAEA performed decontamination experiments at two test sites that combined a range of buildings and different types of land use, located in Date and Minami Soma municipalities as field pilot projects in order to accumulate knowledge and data for full-scale decontamination activities performed by local governments. In the pilot projects, we established its plan using practical decontamination methods that can be easily implemented, according to decontamination targets (e.g., forests, agricultural land, residential house and roads) at each site. As a result of the decontamination, the average air dose rates were reduced to approximately one half of the values before decontamination.

JAEA Reports

Research on engineering technology in the full-scale demonstration of EBS and operation technology for HLW disposal; Research report in 2012 (Joint research)

Nakatsuka, Noboru; Sato, Haruo; Tanai, Kenji; Nakayama, Masashi; Sawada, Sumiyuki*; Asano, Hidekazu*; Saito, Masahiko*; Yoshino, Osamu*; Tsukahara, Shigeki*; Hishioka, Sosuke*; et al.

JAEA-Research 2013-034, 70 Pages, 2014/01

JAEA-Research-2013-034.pdf:9.11MB

Japan Atomic Energy Agency (JAEA) and Radioactive Waste Management Funding and Research Center (RWMC) concluded the letter of cooperation agreement on the research and development of radioactive waste disposal in April, 2005, and have been carrying out the collaboration work based on the agreement. JAEA have been carrying out the Horonobe Underground Research Laboratory (URL) Project which is intended for a sedimentary rock in the Horonobe town, Hokkaido, since 2001. In the project, geoscientific research and research and development on geological disposal technology are being promoted. Meanwhile, the government (the Agency for Natural Resources and Energy, Ministry of Economy, Trade and Industry) has been promoting construction of equipments for the full-scale demonstration of engineered barrier system and operation technology for high-level radioactive waste (HLW) disposal since 2008, to enhance public's understanding to the geological disposal of HLW, e.g. using underground facility. RWMC received an order of the project in fiscal year 2012 (2011/2012) continuing since fiscal year 2008 (2008/2009). Since topics in this project are included in the Horonobe URL Project, JAEA carried out this project as collaboration work continuing in fiscal year 2008. This report summarizes the results of engineering technology carried out in this collaboration work in fiscal year 2012. In fiscal year 2012, part of the equipments for emplacement of buffer material was produced and visualization test for water penetration in buffer material were carried out.

JAEA Reports

Study on methodology to estimate isotope generation and depletion for core design of HTGR

Fukaya, Yuji; Ueta, Shohei; Goto, Minoru; Shimakawa, Satoshi

JAEA-Research 2013-035, 84 Pages, 2013/12

JAEA-Research-2013-035.pdf:3.22MB

An investigation on methodology to estimate isotope generation and depletion had been performed in order to improve the accuracy for HTGR core design. Solving the burn-up equations, generating effective cross section and employing nuclide data are the technical problems. Especially for the generating effective cross section, the core burn-up calculation has a technological problem in common with point burn-up calculation. Thus, the investigation had also been performed for the core burn-up calculation to develop new code system in the future. As a result, it was found that the cross section with the extended 108 energy groups structure from the SRAC 107 groups structure to 20 MeV and the cross section collapse using the flux obtained by the deterministic code SRAC is proper for the use. In addition, an investigation on the preparation condition for nuclear data for a safety analysis and a fuel design was also performed. As a result, the needs for the nuclear data ware made clear.

JAEA Reports

Chemical composition of artificial seawater after leaching tests of irradiated fuel

Tanaka, Kosuke; Suto, Mitsuo; Onishi, Takashi; Akutsu, Yoko; Yoshitake, Tsunemitsu; Yamashita, Shinichiro; Sekioka, Ken*; Ishigamori, Toshio*; Obayashi, Hiroshi; Koyama, Shinichi

JAEA-Research 2013-036, 31 Pages, 2013/12

JAEA-Research-2013-036.pdf:3.31MB

In the accident of Fukushima Daiichi NPPs, the water ingress was performed in order to decrease the reactor temperature. At that time, sea water was temporarily used as a coolant and the water contacted with nuclear fuel directly. It can be supposed that fission products (FP) were easily migrated from the fuel to sea water in this situation and that affect the water quality. The knowledge of leaching behavior, therefore, is necessary for evaluating the integrity of reactor component materials such as steels for pressure containment vessel and for reactor vessel. In order to obtain the fundamental knowledge for leaching behavior of FP in the hot sea water, the leaching tests of irradiated fuel were performed and the leachates were subjected to chemical analysis. It is found that he leaching rate of each nuclides obtained in this study were similar to that of the leaching results simulating the underground water.

JAEA Reports

Enhancement of the methodology of repository design and post-closure performance assessment for preliminary investigation stage, 2; Progress report on NUMO-JAEA collaborative research in FY2012 (Joint research)

Shibata, Masahiro; Sawada, Atsushi; Tachi, Yukio; Hayano, Akira; Makino, Hitoshi; Wakasugi, Keiichiro; Mitsui, Seiichiro; Oda, Chie; Kitamura, Akira; Osawa, Hideaki; et al.

JAEA-Research 2013-037, 455 Pages, 2013/12

JAEA-Research-2013-037.pdf:42.0MB

Following FY2011, 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 stage. With regard to (1) study on rock suitability in terms of hydrology, the tree diagram of methodology of groundwater travel time has been extended for crystalline rock, in addition, tree diagram for sedimentary rock newly has been organized. With regard to (2) study on scenario development, the existing approach has been improved in terms of a practical task, and applied and tested for near field focusing on the buffer. In addition, the uncertainty of some important processes and its impact on safety functions are discussed though analysis. With regard to (3) study on setting radionuclide migration parameters, the approaches for parameter setting have been developed for sorption for rocks and solubility, and applied and tested through parameter setting exercises for key radionuclides.

JAEA Reports

Main generation pathways of activation products for in-core structure materials (Joint research)

Yamamoto, Kento; Okumura, Keisuke; Kojima, Kensuke; Okamoto, Tsutomu

JAEA-Research 2013-038, 88 Pages, 2014/02

JAEA-Research-2013-038.pdf:3.15MB

Accurate information on main generation pathways of activation products is important to improve the accuracy of predicting the concentrations of activation products. Using ORIGEN2 and ORLIBJ40, which is a set of the cross section libraries based on JENDL-4.0, the initial compositions and the cross sections which influence on the concentrations of activation products were clarified by executing the sensitivity analyses on them. Activations of cladding tubes, end-plugs and spacers of fuel assemblies and channel boxes, which were composed of Zircaloy, SUS304, and Inconel-718, were analyzed. The main generation pathways of some significant activation products were summarized from the results of sensitivity analyses.

JAEA Reports

Evaluation on BDI of large diameter pin bundles by out-of-pile bundle compression test

Uwaba, Tomoyuki; Ichikawa, Shoichi; Katsuyama, Kozo

JAEA-Research 2013-039, 25 Pages, 2014/02

JAEA-Research-2013-039.pdf:19.15MB

Bundle-Duct Interaction (BDI) in core fuel subassemblies in FBRs is a limiting factor for fuel burnup. Thus, BDI is an important evaluation item in the upgraded core of the Monju prototype FBR and the demonstration FBR studied in the FaCT project because the fuel subassemblies are to be used to high burnup condition. Since fuel subassemblies of these FBRs consists of large diameter fuel pins, the out-of-pile bundle compression test with large diameter pins was performed to evaluate their BDI bundle. In the compression test, bundle cross-sectional images (CT images) were obtained by using the X-ray computer tomography. The CT images were numerically analyzed to evaluate the deformation of pin bundles due to BDI. The evaluation results revealed that deformation of large diameter pin bundles are controlled by pin bowing and cladding oval-distortion the same as in the case of currently used small diameter pin bundles.

JAEA Reports

Study of specific energy for evaluation of in situ rock mass properties (Joint research)

Hikima, Ryoichi*; Hirano, Toru*; Yamashita, Masayuki*; Ishiyama, Koji*; Tanno, Takeo*; Sanada, Hiroyuki; Sato, Toshinori

JAEA-Research 2013-040, 51 Pages, 2014/03

JAEA-Research-2013-040.pdf:6.86MB

For the research and development about high-level radioactive waste disposal, it is important to evaluate the mechanical stability of the excavation and the long-term behavior of in situ rock. However, from the limited information such as the bowling core before the excavation, it is difficult to evaluate the mechanical properties of in situ rock containing cracks. For this reason, evaluation of rock properties based on Specific Energy using mechanical data from an excavation machine is carried out. This report describes the results of the joint research carried out in FY 2010 to FY 2012.

JAEA Reports

Long term performance of radial shielding subassemblies with zirconium hydride in sodium cooled fast reactor core; Hydrogen release into primary coolant and helium production in cladding tube steels

Inoue, Masaki; Kaito, Takeji

JAEA-Research 2013-041, 69 Pages, 2014/01

JAEA-Research-2013-041.pdf:4.61MB

Long term performance of radial shielding subassemblies with zirconium hydride, which is one of the key technologies to reduce reactor vessel radius, was evaluated for the demonstration fast breeder reactor core. Hydrogen permeation through cladding tube wall and release into primary coolant is essential to design cold traps and shielding performance. Also, higher thermal neutron fluence produces larger helium in cladding tube steels, and may degrade mechanical properties and dimensional stability. A new model was established to quantitatively calculate hydrogen release and helium production under steep gradient of neutron and $$gamma$$ ray fluxes in outer core region. Austenitic stainless steel (PNC316) and ferritic/martensitic steel (PNC-FMS) will not be capable for 60 years because of large helium production and high permeability, respectively. In contrast, dual wall tube combining PNC-FMS with surface oxidized Fe-18Cr-2Al alloy will be applicable for 60 years in case that manufacturing process is successfully developed.

JAEA Reports

An Investigation for long-term storage of a spent zeolite adsorption vessel; Estimation of washing out salt component in a spent zeolite adsorption vessel, 1

Sato, Hiroyuki; Terada, Atsuhiko; Hayashida, Hitoshi; Kamiji, Yu; Kobayashi, Jun; Yamagishi, Isao; Morita, Keisuke; Kato, Chiaki

JAEA-Research 2013-042, 25 Pages, 2014/03

JAEA-Research-2013-042.pdf:5.13MB

Spent zeolite adsorption vessels in the Fukushima No.1 nuclear power plant are kept for long-term with washing out with fresh water for prevention of corrosion remaining salt component in vessel. However, corrosion result is concerned by residual concentration of salt component, washing out experiment is carried out using actual and unspent adsorption vessel (KURION). KURION adsorption vessel is filled with 1,650 ppm of sodium chloride (1,000 ppm of chloride ion) and washed out with pure water for estimating washing effect in this experiment. Pure water is streamed with volume flow rate 4.5 m$$^{3}$$/h, chloride concentration in vessel is measured with drainage sample water. 1,000 ppm of chloride concentration is decreased till 0.5 ppm and below by washing out with about double pure water volume of adsorbing material filling volume in vessel, washing out is more effective in KURION adsorption vessel.

JAEA Reports

Research for spectroscopy of fuel debris using superconducting phase transition edge sensor microcalorimeter; Measurement experiment and simulated calculation (Joint research)

Takasaki, Koji; Yasumune, Takashi; Onishi, Takashi; Nakamura, Keisuke; Ishimi, Akihiro; Ito, Chikara; Osaka, Masahiko; Ono, Masashi*; Hatakeyama, Shuichi*; Takahashi, Hiroyuki*; et al.

JAEA-Research 2013-043, 33 Pages, 2014/01

JAEA-Research-2013-043.pdf:13.81MB

In the Fukushima Daiichi Nuclear Power Plant, it is assumed that the core fuels melted partially or wholly, and the normal technique of accounting for a fuel assembly is not applicable. Therefore, it is necessary to develop the transparent and rational technique of accounting in the process of collection and storage of fuel debris. In this research, an application of the superconducting phase Transition Edge Sensor microcalorimeter (TES microcalorimeter) is studied for the accounting of nuclear materials in the fuel debris. It is expected that the detailed information of nuclear materials and fission products in fuel debris is obtained by using a high-resolution characteristic of TES microcalorimeter. In this report, the principle of TES microcalorimeter, the measurement experiment using TES in JAEA, and the simulated calculation using the EGS5 code system are summarized.

JAEA Reports

Mizunami Underground Research Laboratory Project; Rock mechanical investigations in situ stress measurements and laboratory tests using core on the GL.-300m and GL.-400m level of research galley

Tanno, Takeo*; Sato, Toshinori; Sanada, Hiroyuki; Hikima, Ryoichi*

JAEA-Research 2013-044, 257 Pages, 2014/02

JAEA-Research-2013-044.pdf:44.45MB

In the rock mechanical investigations, the research aims at "Characterization of geological environment in the Excavation Disturbed Zone (EDZ)" from the viewpoint of safety assessment. For the research, the specific data of the EDZ. The research also aims at "Characterization of geomechanical stability around tunnel " from the viewpoint of design and construction of underground facilities. This report presents the results of following rock mechanical investigations conducted at the GL.-300m and GL.-400m Level of Research Galley. (1) Laboratory tests using core and block samples obtained at the GL.-300m and GL.-400m Level of Research Galley, (2) Measurement of Compact Conical-ended Boerhole Overcoring (CCBO) method at the GL.-300m Level of Research Galley, (3) In-situ stress measurements using core-based methods at the GL.- 300m Stage.

JAEA Reports

Theoretical study of rock for estimating long-term behavior; FY2012 (Contract research)

Ichikawa, Yasuaki*; Kimoto, Kazushi*; Sato, Toshinori; Tanno, Takeo; Hikima, Ryoichi; Sanada, Hiroyuki

JAEA-Research 2013-045, 69 Pages, 2014/03

JAEA-Research-2013-045.pdf:9.51MB

Rock mass is a complex material including several classes of discontinuities and inhomogeneous/anisotropic minerals. If observing rock samples, we know that crystalline rock is a complex of minerals, grain boundaries and microcracks. In this study, the series of experiments were managed by a flow-through type changing temperature, pH and applied stress. Attenuation of ultrasonic waves in rock is investigated experimentally using an intact but coarse-grained granite core sample. For ultrasonic measurements, piezoelectric transducers are used in a through-transmission mode. With the estimated response function, phase and amplitude spectra of the transmitted ultrasonic waves are investigated quantitatively to evaluate the attenuation and change in travel time.

JAEA Reports

Study to improve recriticality evaluation methodology after severe accident (Joint research)

Kugo, Teruhiko; Ishikawa, Makoto; Nagaya, Yasunobu; Yokoyama, Kenji; Fukaya, Yuji; Maruyama, Hiromi*; Ishii, Yoshihiko*; Fujimura, Koji*; Kondo, Takao*; Minato, Hirokazu*; et al.

JAEA-Research 2013-046, 53 Pages, 2014/03

JAEA-Research-2013-046.pdf:4.42MB

The present report summarizes the results of a 2-year cooperative study between JAEA and Hitachi-GE in order to contribute to the settlement of the Fukushima-Daiichi Nuclear Power Plants which suffered from the severe accident on March 2011. In the present study, the possible scenarios to reach the recriticality events in Fukushima-Daiichi were investigated first. Then, the analytical methodology to evaluate the time-dependent recriticality events has been developed by modelling the reactivity insertion rate and the possible feedback according to the recriticality scenarios identified in the first step. The methodology developed here has been equipped as a transient simulation tool, PORCAS, which is operated on a multi-purpose platform for reactor analysis, MARBLE. Finally, the radiation exposure rates by the postulated recriticality events in Fukushima-Daiichi were approximately evaluated to estimate the impact to the public environment.

JAEA Reports

Annual report for research on geosphere stability for long-term isolation of radioactive waste in fiscal years 2012

Yasue, Kenichi; Asamori, Koichi; Niwa, Masakazu; Hanamuro, Takahiro; Kokubu, Yoko; Sueoka, Shigeru; Makuuchi, Ayumu; Ikuta, Masafumi; Matsubara, Akihiro; Tamura, Hajimu; et al.

JAEA-Research 2013-047, 109 Pages, 2014/03

JAEA-Research-2013-047.pdf:6.81MB

This annual report documents the progress of R&D in the 3rd fiscal year during the JAEA 2nd Midterm Plan (FY 2010 - 2014) to provide the scientific base for assessing geosphere stability for long-term isolation of the high-level radioactive waste. The planned framework is structured into the following categories: (1) development and systematization of investigation techniques for selecting suitable sites in geosphere stability, (2) development, application and verification of prediction models for evaluating the changes of geological environment in thermal, hydraulic, mechanical and geochemical conditions for a long period of time, and (3) development of new dating techniques for providing information about geologic history and the timing of geologic events. In this paper, the current status of R&D activities with previous scientific and technological progress is summarized.

JAEA Reports

Study on calculation method of the number of measurement points and procedure of decision-making for site release verification

Ishigami, Tsutomu; Shimada, Taro

JAEA-Research 2013-048, 40 Pages, 2014/03

JAEA-Research-2013-048.pdf:2.84MB

In the field of safety regulation system for nuclear facilities after the permanent shutdown of their operations, a verification method of site release in confirmation of decommissioning completion which is a final stage of decommissioning and its specific procedure are important technical issues. On the assumption that decision-making on site release would be made based on measurement results of radioactive concentrations of soils at tens of points, we studied a calculation method of the number of measurement points and a procedure of decision-making for site release. We derived an equation to calculate the number of measurement points that gives the minimum expected cost of site release verification in ensuring safety of the public, taking into account probabilities of decision errors, scenarios of decision-making to site release, and cost of verification. We also developed a specific procedure of decision-making for site release based on the way of scenarios of decision-making.

JAEA Reports

Radiation monitoring using the unmanned helicopter after the accident of the nuclear power plant

Sanada, Yukihisa; Nishizawa, Yukiyasu; Yamada, Tsutomu; Ikeda, Kazutaka*; Matsui, Masashi*; Tsuchida, Kiyofumi; Sato, Yoshiharu; Hirayama, Hirokatsu; Takamura, Yoshihide; Nishihara, Katsuya; et al.

JAEA-Research 2013-049, 129 Pages, 2014/03

JAEA-Research-2013-049.pdf:15.5MB

By the nuclear disaster of Fukushima Daiichi Nuclear Power Plant (NPP), Tokyo Electric Power Company (TEPCO), caused by the East Japan earthquake and the following tsunami occurred on March 11, 2011, a large amount of radioactive materials was released from the NPP. In recent years, technologies for autonomous unmanned helicopters (AUHs) have been developed and applied to natural disasters. In expectation of the application of the AUHs to aerial radiation monitoring, we had developed a remote radiation monitoring system. Then, we measured the radiation level by using unmanned helicopter in soil contaminated areas by radioactive cesium emitted from the NPP to evaluate ambient dose-rate distribution around the areas and to investigate the decontamination effect by the measurements before and after decontamination treatment. Here, we reports on the measurement technique and the result.

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