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JAEA Reports

Outline of safety research on high-level radioactive waste disposal; Background and future study for safety research

Sonobe, Hitoshi

JAEA-Review 2008-001, 37 Pages, 2008/03

JAEA-Review-2008-001.pdf:3.17MB

In the Japan Atomic Energy Agency, it has been conducted aggressively since the previous organization, and the achieved results has been reflected to the documents related to the decision of a basic idea of the safety regulation for disposal of the high-level radioactive waste etc. The Power Reactor and Nuclear Fuel Development Corporation and Japan Nuclear Cycle Development Institute, predecessors of the Japan Atomic Energy Agency, have developed the geological disposal technology of the high-level radioactive waste to contribute the implementation of disposal and the safety regulation. This report presents outline of the safety research conducted up to now: the policy, the plan of the safety research on the high-level radioactive waste disposal, the summary of results, and future studies required.

JAEA Reports

Annual report of R&D activities in Center for Computational Science & e-Systems from April 1, 2006 to March 31, 2007

Center for Computational Science & e-Systems

JAEA-Review 2008-002, 49 Pages, 2008/03

JAEA-Review-2008-002.pdf:20.14MB

This report provides an overview of the research and development activities of the Center for Computational Science & e-Systems (CCSE), JAEA in fiscal year 2006 (April 1, 2006 to March 31, 2007). These research and development activities have been performed by the Simulation Technology Research and Development Office and the Computer Science Research and Development Office. The primary results of the research and development activities are the development of simulation techniques for a virtual earthquake testbed, an intelligent infrastructure for atomic energy research, computational biological disciplines to predict DNA repair function of protein, and material models for a neutron detection device, crack propagation, and gas bubble formation in nuclear fuel.

JAEA Reports

2006 annual report of No.8 sub-group (evaluation and modeling of geochemical mechanisms for long-term dissolution and alteration of waste glass) in the Prioritized Cooperative Research Program

No.8 Sub-group of Prioritized Cooperative Research Program

JAEA-Review 2008-003, 76 Pages, 2008/03

JAEA-Review-2008-003.pdf:36.03MB

This is the 2006 annual report of No.8 sub-group (evaluation and modeling of geochemical mechanisms for long-term dissolution and alteration of waste glass) in the Prioritized Cooperative Research Program (PCRP). Target of the study in this sub-group is improving reliability of radionuclide release from the waste glass as source of long-term behavior. And then elucidating geochemical mechanisms of the waste glass, and making long-term dissolution model are scheduled. In the fiscal year of 2006, the PCRP meeting was held two times. Previous data on dissolution of waste glasses and the recent research results were discussed in these meeting. Documents and the minutes are shown in this report.

JAEA Reports

Progress report on neutron science; April 1, 2006 - March 31, 2007

Quantum Beam Science Directorate; Advanced Science Research Center

JAEA-Review 2008-004, 139 Pages, 2008/03

JAEA-Review-2008-004.pdf:24.48MB

There are 13 research groups in neutron science and technology in the Quantum Beam Science Directorate (QuBS) and Advanced Science Research Center (ASRC) of Japan Atomic Research Agency (JAEA). A wide variety of research is performed by these group: neutron scattering (condensed matter physics, polymer science, biology, and residual stress analysis), prompt $$gamma$$-ray analysis, neutron radiography, neutron optics, and development of a neutron spectrometer, neutron beam handling device and neutron detector. This issue summarizes research progress in neutron science and technology including activities of the Nuclear Science and Engineering Directorate of JAEA, and of the COMMON USE PROGRAM of JAEA utilizing the research reactor JRR-3 during the period between April 1, 2006 and March 31, 2007. This report contains highlights of research by these 13 neutron research groups of QuBS and ASRC, introducing 78 experimental reports.

JAEA Reports

Annual report of Nuclear Technology and Education Center (April 1, 2006 - March 31, 2007)

Nuclear Technology and Education Center

JAEA-Review 2008-005, 98 Pages, 2008/03

JAEA-Review-2008-005.pdf:84.78MB

This annual report summarizes the activities of Nuclear Technology and Education Center (NuTEC) of Japan Atomic Energy Agency (JAEA) in the fiscal year 2006, which has started half a year after the unification of the training sections of JAERI and JNC. During this period, NuTEC has conducted its training activities as planned. The number of trainees completing the domestic training courses was 518, and that for staff technical training was 545. A "Qualification course for the 3rd class radiation protection supervisor" has been newly implemented, and a trial "Preparatory course for qualifying examination for professional engineer in the nuclear and radiation fields" has been held for the staff members. In addition, preparative work has been performed for opening some of the staff training courses to the public. International cooperation was also conducted as scheduled, and setting up new training sites at Ongkharak, Thailand and Dalat, Vietnam has been supported. Cooperation for Nuclear Professional School, School of Engineering, the University of Tokyo which opened in 2005, has been duly continued.

JAEA Reports

Annual report of JMTR, FY2006; April 1, 2006 - March 31, 2007

Department of JMTR Operation

JAEA-Review 2008-006, 41 Pages, 2008/03

JAEA-Review-2008-006.pdf:3.35MB

During the FY2006 (April 2006 to March 2007), the Japan Materials Testing Reactor (JMTR) was operated for three operation cycles from 162nd cycle to 165th cycle. Various irradiation tests and post-irradiation examinations (PIEs) were performed for studies on Irradiation Assisted Stress Corrosion Cracking (IASCC) of light-water-reactor internals, development of the fusion blanket, basic materials researches, radioisotope production, and so on. The operation was stopped by 165th cycle according to schedule. And maintenance work and preservation work of the facilities has been started for the refurbishment of the JMTR. Renewal of equipments and aging management of equipments and reactor facilities were carried out according to long-term maintenance plan which was based on periodical evaluation related to maintenance and safety management of reactor facilities.

JAEA Reports

Annual report of Nuclear Science Research Institute, JFY2006

Nuclear Science Research Institute

JAEA-Review 2008-007, 114 Pages, 2008/03

JAEA-Review-2008-007.pdf:38.66MB

Nuclear Science Research Institute (NSRI) is composed of Planning and Coordination Office and seven departments such as Department of Operational Safety Administration, Department of Radiation Protection, Department of Research Reactor and Tandem Accelerator, Department of Hot Laboratories and Facilities, Department of Criticality and Fuel Cycle Research Facilities, Department of Decommissioning and Waste Management, and Engineering Services Department. This annual report of JFY 2006 summarizes the activities of NSRI and the R&D activities of the Research and Development Directorates at site, and is expected to be referred to and utilized by R&D departments and project promotion sectors at NSRI site for the enhancement of their own research and management activities to attain their goals according to "Middle-term Plan" successfully and effectively.

JAEA Reports

Review of JAEA activities on the IFMIF liquid lithium target in FY2006

Ida, Mizuho; Nakamura, Hiroo; Chida, Teruo*; Miyashita, Makoto; Furuya, Kazuyuki*; Yoshida, Eiichi; Hirakawa, Yasushi; Miyake, Osamu; Hirabayashi, Masaru; Ara, Kuniaki; et al.

JAEA-Review 2008-008, 38 Pages, 2008/03

JAEA-Review-2008-008.pdf:9.37MB

Engineering Validation Design and Engineering Design Activity (EVEDA) of the International Fusion Materials Irradiation Facility (IFMIF) is under going. IFMIF is an accelerator-based Deuterium-Lithium (D-Li) neutron source to produce intense high energy neutrons and a sufficient irradiation volume for testing candidate materials for fusion reactors. To realize such a condition, 40 MeV deuteron beam with a current of 250 mA is injected into high speed liquid Li flow with a speed of 20 m/s. In target system, nuclear heating due to neutron causes thermal stress especially on a back-wall of the target assembly. In addition, radioactive species such as beryllium-7, tritium and activated corrosion products are generated. In this report, thermal stress analyses of the back-wall, mechanical tests on weld specimen made of the back-wall material, estimations of beryllium-7 behavior and worker dose at the IFMIF Li loop and consideration on major EVEDA tasks are summarized.

JAEA Reports

Fast reactor cycle technology development; "FaCT Seminar, R&D for Key Technology of National Importance" conference report and collection of documents

Advanced Nuclear System Research and Development Directorate

JAEA-Review 2008-009, 129 Pages, 2008/03

JAEA-Review-2008-009.pdf:25.81MB

An R&D program on the fast breeder reactor cycle commercialization, the FaCT Project, which was selected as one of the Key Technologies of National Importance, has been conducted at the JAEA for the purposes of resolving the issues of long-term sustainable energy supply and the global warming. The first Seminar of the FaCT Project was held at the Osaka Science and Technology Center on November 30, 2007, to present the progress and status of the Project and exchange opinions among the participants from various sectors. In the Seminar, MEXT, METI and JAEA reported the national nuclear policy, the current status and future plan of the FaCT Project. A special panel session was also held on the approach to international collaboration relevant to the Project, and the importance was stressed on further promoting the international collaboration and keeping the framework of international partnership in this area, while distinguishing the relationship between "cooperation" and "competition".

JAEA Reports

Proceedings of Information and Opinion Exchange Conference on Geoscientific Study, 2006

Nishio, Kazuhisa; Iyatomi, Yosuke; Ogata, Nobuhisa

JAEA-Review 2008-010, 149 Pages, 2008/03

JAEA-Review-2008-010.pdf:71.31MB

Japan Atomic Energy Agency (JAEA) at Tono Geoscience Center (TGC) is conducting a geoscientific studies in order to establish a scientific and technological basis for the geological disposal of HLW. Information and Opinion Exchange Conference on Geoscientific Study has been held by JAEA at TGC annually. The conference provides technical information and an opportunity for peer review and exchange of opinions on the geoscientific studies conducted at TGC. Research specialists and engineers from Japanese universities, research organizations and private companies usually participate the conference. This document collects research presentations, posters of the conference on October 19th to 20th, 2006 at Mizunami.

JAEA Reports

Proceedings of the 2nd Workshop on "Elucidation of the Mechanism of High-$$T$$$$_{rm c}$$ Superconductivity by Quantum Beams"; December 14-15, 2007, Izura, Ibaraki, Japan

Shamoto, Shinichi; Arai, Masatoshi

JAEA-Review 2008-011, 195 Pages, 2008/03

JAEA-Review-2008-011-01.pdf:46.79MB
JAEA-Review-2008-011-02.pdf:22.51MB

A workshop entitled "Elucidation of Mechanism of the High-$$T$$$$_{rm c}$$ Superconductivity by Quantum Beams" was held on December 14 and 15, 2007 at Izura, in the north of Ibaraki prefecture. This is the 2nd workshop by Grant-in-Aid for Specially Promoted Research of MEXT, Japan, "Development of the 4 Spaces Access Neutron Spectrometer (4SEASONS) and Elucidation of the Mechanism of Oxide High-$$T$$$$_{rm c}$$ Superconductivity" (FY2005-2009, repr. by M. Arai, JAEA). In the workshop, previous researches on the high-$$T$$$$_{rm c}$$ superconductivity were reviewed, the recent progress was reported, and the future perspectives were discussed by 30 first-class Scientists.

JAEA Reports

Collection of radiation resistant characteristics reports for instruments and materials in high dose rate environment

Kusano, Joichi

JAEA-Review 2008-012, 104 Pages, 2008/03

JAEA-Review-2008-012.pdf:7.9MB

This document presents the collected official reports of radiation irradiation study for the candidate materials to be used in high dose rate environment as J-PARC facility. The effect of radiation damage by loss-beam or secondary particle beam of the accelerators influences the performance and the reliability of various instruments. The knowledge on the radiation resistivity of the materials is important to estimate the life of the equipments, the maintenance interval and dose evaluation for the personnel at the maintenance period. The radiation damage consists with mechanical property, electrical property and gas-evolution property.

JAEA Reports

Electrons in condensed media

Mozumder, A.*; Yokoya, Akinari; Katsumura, Yosuke; Hatano, Yoshihiko

JAEA-Review 2008-013, 37 Pages, 2008/06

JAEA-Review-2008-013.pdf:4.08MB

This document is a summary of the lectures or seminar talks by A.Mozumder and his discussion/information exchanges with Y.Hatano, A.Yokoya, and Y.Katsumura. A.Mozumder is an invited fellow of the JSPS Invitation Fellowship Program for Research in Japan (Short-Term) with the host Y.Hatano, and stays in Japan mainly at Advanced Science Research Center (ASRC) of JAEA. The research in this program is entitled "Charged Particle and Photon Interactions with Matter", from which the authors give the title of this document one of the most important reactive species commonly produced in matter from these interactions. This document contains the annotated materials presented at ten seminars given by A.Mozumder during his stay in Japan in this program at JAEA (Tokai and Takasaki) and also at various universities and research institutes, including invited lectures at the International Symposium of ASR2007 held in Tokai and the Annual Discussion Meeting of Radiation Chemistry held in Kyoto.

JAEA Reports

Implementing of action plans for risk communication on the uranium mining sites remedy at Ningyo-Toge Environmental Engineering Center, 1 (Contract research)

Yabuta, Naohiro*; Kawai, Jun*; Hikawa, Tamae*; Tokizawa, Takayuki; Sato, Kazuhiko; Koga, Osamu

JAEA-Review 2008-014, 133 Pages, 2008/11

JAEA-Review-2008-014.pdf:11.04MB

On the closure of uranium mine site at Ningyo-Toge, the action plans for risk communication with residence and local governments were developed and implemented. Under a practical program of the risk communication, an ethnographical research on Ningyo-toge has been conducted by local high school students. The research was focused on several social groups such as engineers at the Center and residents around Ningyo-toge and described their circumstances from the past to the present. In addition, it should be noted that as a results, the research project led several effects listed below; (1) High school students understood significance of the uranium development projects implemented at Ningyo-toge, (2) Differences of standpoints between local residents and Ningyo-toge became clearer, (3) Foundation to communicate between local communities and Ningyo-toge was found out, (4) The educational program on an ethnographical research was conducted autonomously by local high school students.

JAEA Reports

Implementing of action plans for risk communication on the uranium mining sites remedy at Ningyo-Toge Environmental Engineering Center, 2 (Contract research)

Yabuta, Naohiro*; Kawai, Jun*; Hikawa, Tamae*; Tokizawa, Takayuki; Sato, Kazuhiko; Koga, Osamu

JAEA-Review 2008-015, 92 Pages, 2008/11

JAEA-Review-2008-015.pdf:11.88MB

On the closure of uranium mine site at Ningyo-Toge Environmental Engineering Center Japan Atomic Energy Agency, the action plans for risk communication with residence and local governments were developed and implemented. Under a practical program of the risk communication, an ethnographical research on Ningyo-Toge Environmental Engineering Center has been conducted by local high school students. The research was focused on several social groups such as engineers at the Center and residents around Ningyo-Toge and described their circumstances from the past to the present, since the discovery of the uranium outcrop 1955. In the second year of the program, the results of the research were presented at symposium and the students had opportunities to exchange their views with others from different high schools that held in similar programs. Through those activities, the importance of the program was rediscovered and some new issues were also identified.

JAEA Reports

Minutes of "Technical Committee for Geological Isolation Research and Development (2nd Time)"

Sasaki, Yasuo; Torata, Shinichiro; Numata, Yoshiaki

JAEA-Review 2008-016, 69 Pages, 2008/03

JAEA-Review-2008-016.pdf:7.79MB

In order to plan and conduct a program of research and development (R&D) for geological disposal of high-level radioactive waste in JAEA-Tokai, JAEA decided to receive technical comments and advices from the Technical Committee for geological isolation R&D. This committee, which is constituted of specialists who do not belong to JAEA, has evaluated the program, taking into account of the status of geological disposal technology in Japan as well as foreign countries. This report compiles the minutes of the second meeting held in March 2007.

JAEA Reports

Summary of entire research achievements of creative engineering research program on nuclear fuel cycle

Industrial Collaboration Promotion Department

JAEA-Review 2008-017, 164 Pages, 2008/03

JAEA-Review-2008-017.pdf:47.9MB

Creative Engineering Research Program on Nuclear Fuel Cycle (former In-house Innovative Research Encouraging Program) was implemented from FY 2001 to FY 2007 in order to support the execution of such in-house researches that create innovative new concepts and aim technical break-through. Totally thirty seven applications have been received and fourteen research themes have been accepted and been performed in this program. As for the research achievements of the fourteen research themes, first author papers accepted by scientific journals and by science councils were forty seven and thirty two, respectively, and oral presentations at scientific societies were ninety nine. Furthermore, interpretive articles for scientific journals, requested lectures, patents, and prize winnings were thirteen, thirty, eight, and three, respectively. Consequently, it can be evaluated that the research achievements resulted from this program are generally in high level and that the expectations, at the starting point of this program, to activate the innovative research activities have been accomplished. In this report, the final reports of the fourteen research themes together with the outline of this program are included.

JAEA Reports

Operation, test, research and development of the High Temperature Engineering Test Reactor (HTTR) (FY2006)

Department of HTTR

JAEA-Review 2008-018, 68 Pages, 2008/03

JAEA-Review-2008-018.pdf:17.93MB

The High Temperature Engineering Test Reactor (HTTR) constructed at the Oarai Research and Development Center of the Japan Atomic Energy Agency (JAEA) is the first high-temperature gas-cooled reactor (HTGR) in Japan. The HTTR is a graphite-moderated and helium gas-cooled reactor with 30 MW of thermal power. In fiscal year 2006, periodical inspection, exchange of wide range monitoring neutron detectors and overhaul of a reactivity control system were conducted, and safety demonstration tests were carried out. This report summarizes activities and test results on HTTR operation and maintenance as well as safety demonstration tests and several R&Ds, which were carried out in the fiscal year 2006.

JAEA Reports

Information exchange on HTGR and nuclear hydrogen technology between JAEA and INET in 2007

Fujimoto, Nozomu; Tachibana, Yukio; Sakaba, Nariaki; Hino, Ryutaro; Yu, S.*

JAEA-Review 2008-019, 194 Pages, 2008/06

JAEA-Review-2008-019-01.pdf:39.69MB
JAEA-Review-2008-019-02.pdf:47.74MB

The worldwide interests in the HTGR (High Temperature Gas-cooled Reactor) have been growing because the high temperature heat produced by the reactor can be utilized not only for efficient power generation but also for broad process heat applications, especially for thermo-chemical hydrogen production to fuel a prospective hydrogen economy in future. Presently only two HTGR reactors are operational in the world, including the HTTR (High Temperature Engineering Test Reactor) in Japan Atomic Energy Agency (JAEA) and the HTR-10 in the Institute of Nuclear and New Energy Technology (INET) of Tsinghua University in China. JAEA and INET have cooperated since 1986 in the field of HTGR development, particularly on the HTTR and HTR-10 projects. This report describes the cooperation activities on HTGR and nuclear hydrogen technology between JAEA and INET in 2007.

JAEA Reports

Outline of nuclear fuel cycle

Ojima, Hisao

JAEA-Review 2008-020, 28 Pages, 2008/07

JAEA-Review-2008-020.pdf:4.52MB

The mined uranium ore is refined and becomes a "yellow cake" in which the uranium content is about 60%. Then the yellow cake is converted into UF$$_{6}$$ that is the raw material of uranium enrichment. The content of $$^{235}$$U is enriched usually by means of the centrifuge separation. The enriched uranium is converted into UO$$_{2}$$ and is used for pellet fabrication. Finally, the uranium is used in the LWR plant as nuclear fuel. The uranium and plutonium are recovered from the spent fuel in the reprocessing plan and they are used as nuclear fuel again. As for the method of the reprocessing, the PUREX process using TBP as extractant is a main stream because of its stability and safety in operation. The preprocessing process consists of a head-end process including a shearing process, a dissolution process, and a clarification process, and a chemical process including a solvent extraction process, a concentration process, a denitration process and mixed conversion process. The nitric acid and the solvent are recycled in the plant and high level liquid waste is vitrified into glass form, finally. In Japan, through the experience of the Tokai Reprocessing Plant, the first commercial reprocessing plant, Rokkasho Reprocessing Plant, will start its operation in 2008. The spent fuel from FBR can be reprocessed by the PUREX method taking into account of its characteristics such as high plutonium content rate, high burn-up, and the structure of fuel assembly. Currently, the adoption of a new technology is examined aiming for further economy improvement and the achievement of the reduction of the waste load. The safeguards is the activity to prevent the diversion of nuclear material.

JAEA Reports

Survey on usage of electronic journals in Japan Atomic Energy Agency

Ishikawa, Masashi; Fukazawa, Takeyasu

JAEA-Review 2008-021, 50 Pages, 2008/05

JAEA-Review-2008-021.pdf:2.3MB

Survey on usage of electronic journals was performed quantitatively by analyzing downloads accesses data to the 1,783 journals titles published by Elsevier in Japan Atomic Energy Agency (JAEA), 2006. Although JAEA researchers are interested in 1,028 journal titles among physics, chemistry, engineering, medicine, social sciences etc., it is found that 80% of total downloads was occupied by only 102 journal titles. To satisfy researcher's needs for electronic journals effectively, identification the core journals by librarians based on user's needs is rational way in cost.

JAEA Reports

Collection of radiation irradiation study reports for the candidate materials and instruments in the J-PARC

Kusano, Joichi

JAEA-Review 2008-022, 134 Pages, 2008/03

JAEA-Review-2008-022-1.pdf:46.12MB
JAEA-Review-2008-022-2.pdf:40.74MB

This document presents the collected reports of radiation irradiation study for the candidate materials and instruments to be used in the High Intensity Proton Accelerator Facility, J-PARC. The examinations were executed at the $$gamma$$-ray irradiation facility in JAEA Takasaki Institute. The effect of radiation damage by loss-beam or secondary particle beam of the accelerators influences the performance and the reliability of various instruments. The knowledge on the radiation resistivity of the materials is important to estimate the life of the equipments, the maintenance interval and dose evaluation for the personnel at the maintenance period. The radiation damage consists with mechanical property, electrical property and gas-evolution property. This report shows the subject of the instruments or the materials in the J-PARC facility, the theme of the irradiation study, the results of examination and the selected decision of the policy for usage.

JAEA Reports

Inspection of secondary cooling system piping of JMTR

Hanawa, Yoshio; Izumo, Hironobu; Fukasaku, Akitomi; Nagao, Yoshiharu; Kawamura, Hiroshi

JAEA-Review 2008-023, 55 Pages, 2008/06

JAEA-Review-2008-023.pdf:5.63MB

Piping condition was inspected form the view point of confirmation of long term utilization before renewal work of secondary cooling system in the JMTR on FY 2008. As the result, it was confirmed that crack, swelling and exfoliation in inner lining of piping could be observed, and corrosion in piping could hardly be observed. Repair of inner lining of piping during refurbishment of the JMTR is necessary to long term utilization of secondary cooling system after restart of the JMTR. In addition, periodic inspection of inner lining condition is necessary after repair of secondary cooling system piping.

JAEA Reports

Examination and application of parameters for evaluating internal dose at high-energy accelerator facilities, J-PARC

Yokoyama, Sumi

JAEA-Review 2008-024, 29 Pages, 2008/06

JAEA-Review-2008-024.pdf:4.27MB

At high-energy accelerator facilities, various radionuclides were formed by irradiation of high-energy proton beams. To estimate internal dose suitably, it is important to get information on the physicochemical properties of airborne radionuclides such as the particle size distribution of radioactive aerosols and chemical form of radioactive gases in the air of the facilities. In this report, the study related to internal dose assessment is summarized and the effect on a dose when these results were applied to the dose estimation at the high-energy accelerator facility such as J-PARC facilities is discussed.

JAEA Reports

Time-resolved spectroscopy of solid-state materials using an X-ray laser (Thesis)

Tanaka, Momoko

JAEA-Review 2008-025, 47 Pages, 2008/06

JAEA-Review-2008-025.pdf:5.39MB

X-ray laser is expected as a source of EUV lithography research because it is a characteristic source with short pulse duration of several pico-seconds, narrow spectral width, and high coherence. However, the study of spectroscopy excited with X-ray laser is few. In this study, the beam divergence of X-ray laser was improved and applied to measurement of time resolved emission spectroscopy of a solid-state material. The beam divergence of the X-ray laser is improved to be 0.20 mrad by double target configuration using two gain media. As an application of the X-ray laser, the UV emission of a ZnO single crystal excited by 13.9 nm X-ray laser was observed and evaluated for EUV scintillator. It is also shown that the X-ray laser is an excellent tool for time-resolved spectroscopy.

JAEA Reports

Proceedings of Information and Opinion Exchange Conference on Geoscientific Study, 2007

Nishio, Kazuhisa; Iyatomi, Yosuke; Ogata, Nobuhisa

JAEA-Review 2008-026, 103 Pages, 2008/05

JAEA-Review-2008-026.pdf:4.64MB

The Tono Geoscience Center (TGC) of Japan Atomic Energy Agency (JAEA) has been conducting a geoscientific studies in order to establish a scientific and technological basis for the geological disposal of HLW. Information and Opinion Exchange Conference on Geoscientific Study has been held by TGC annually. The conference provides technical information and an opportunity for peer review and exchange of opinions on the geoscientific studies conducted at TGC. Research specialists and engineers from Japanese universities, research organizations and private companies usually participate the conference. This document collects research presentations, posters of the conference on October 19th, 2007 at Mizunami.

JAEA Reports

Research on evacuation planning as nuclear emergency preparedness, 2; Reflex action phase and evacuation in France and examples of evacuation time estimation models

Yamamoto, Kazuya

JAEA-Review 2008-027, 54 Pages, 2008/06

JAEA-Review-2008-027.pdf:0.82MB

Reflex action phase introduced in France is a prompt sheltering in place is requested in the case of accidents liable to cause radioactive release within a short period. Subsequent evacuation is conducted after the passage of the radioactive plume. Pre-distribution of stable iodine tablets to the populations living in this area is a condition for this. Evacuees is transported to public reception centers by buses in France. The public reception center is selected from facilities where are outside of 10km radius from the plant. According to examples of evacuation time estimation (ETE) report in U.S., ETE have to be conduct for conditions, season, day of week, time of day, weather, and large events. It is very important for ETE to consider a portion of the population outside the impacted region will elect to voluntary evacuate. Traffic simulation technology development for large network of main and small roads is very important in Japan.

JAEA Reports

Overview of irradiation technology in OPAL reactor

Hosokawa, Jinsaku; Izumo, Hironobu; Ishitsuka, Etsuo

JAEA-Review 2008-028, 39 Pages, 2008/06

JAEA-Review-2008-028.pdf:10.72MB

For the purpose of advanced technology developments on new irradiation facilities installed in the JMTR, the $$^{99}$$Mo production facility for medical RI, silicon semiconductor production facility, pneumatic irradiation facilities, RI handling facilities in the OPAL were investigated. In this paper, basic structure and the safety design concepts for these irradiation facilities are reported.

JAEA Reports

Review of severe accidents and the results of accident consequence assessment in different energy system (Contract research)

Matsuki, Yoshio*; Takahara, Shogo; Homma, Toshimitsu; Muramatsu, Ken

JAEA-Review 2008-029, 111 Pages, 2008/05

JAEA-Review-2008-029.pdf:5.68MB

In this report, we have researched frequency and consequences of Severe Accidents in the Energy sector based on the data base of Paul Scherrer Institute which is associated with Energy-related Severe Accident. In addition, to assess the impact of severe accident in nuclear power plant such as Chernobyl accident, we used the information of IAEA and the U.S.A. President Commission reports which assess the cost and the possibility of occurrence of nuclear severe accident using the probabilistic safety assessment. We have reviewed these references, and analyzed the results of investigations from aspects of the Cost and number of Fatality, Injury and Evacuee caused by severe accidents. From these results, it is pointed out that the costs caused by the severe accident in nuclear energy tend to be higher than the other energy sectors. On the other hand, from aspects of the fatality and injury, the impacts of Chernobyl accident doesn't have distinctive features.

JAEA Reports

Survey of educational curriculum for nuclear engineering of University in Japan (Contract research)

Sato, Koichi; Kato, Hiroshi; Ishikawa, Fumitaka; Hasegawa, Makoto; Nakazaki, Masayoshi*

JAEA-Review 2008-030, 112 Pages, 2008/09

JAEA-Review-2008-030.pdf:7.53MB

Japan Atomic Energy Agency has been advancing the construction of Japan Nuclear Education Network aiming at the human resources development. Japan Nuclear Education Network executes the practical training and the remote education system. The purpose of the survey is to grasp the present status of educational curriculum for nuclear engineering of University in Japan, and to be helpful for our activities to extend JNEN in future. The present survey leads to the following conclusions. About 80% of seventeen universities hope the cooperation with another university and related institutions to maintain and continue the educational curriculum systematically of nuclear engineering. Their universities request the practical training for nuclear engineering, the dispatch of lecturers each other, the remote educational system in case of participation.

JAEA Reports

Proceedings of the International Workshop on Structural Analyses Bridging over between Amorphous and Crystalline Materials (SABAC2008); January 10-11, 2008, Tokai-mura, Naka-gun, Ibaraki-ken, Japan, Techno Community Square "RICOTTI"

Shamoto, Shinichi; Kodama, Katsuaki

JAEA-Review 2008-031, 320 Pages, 2008/07

JAEA-Review-2008-031-01.pdf:8.43MB
JAEA-Review-2008-031-02.pdf:46.83MB
JAEA-Review-2008-031-03.pdf:42.54MB
JAEA-Review-2008-031-04.pdf:36.46MB
JAEA-Review-2008-031-05.pdf:42.24MB

International workshop entitled "Structural Analyses Bridging over between Amorphous and Crystalline Materials" (SABAC2008) was held on January 10 and 11, 2007 at Techno Community Square "RICOTTI" in Tokai. Amorphous and crystalline materials are studied historically by various approaches. Recent industrial functional materials such as optical memory material, thermoelectric material, hydrogen storage material, and ionic conductor have intrinsic atomic disorders in their lattices. These local lattice disorders cannot be studied by conventional crystal structure analyses such as Rietveld analysis. Similar difficulty also exists in the structure analysis of nanomaterials. In this workshop, new approaches to the structural analysis on these materials were discussed. This report includes abstracts and materials of the presentations in the workshop.

JAEA Reports

Brief report on the research by JAEA Postdoctoral Fellows for 2007

Research Cooperation Section

JAEA-Review 2008-032, 32 Pages, 2008/07

JAEA-Review-2008-032.pdf:0.66MB

This report includes a summary of the results of the research on five themes performed by JAEA Postdoctoral Fellows in the fiscal year 2007.

JAEA Reports

Inventory of safeguards software

Suzuki, Mitsutoshi; Horino, Koichi*

JAEA-Review 2008-033, 22 Pages, 2009/03

JAEA-Review-2008-033.pdf:0.43MB

Based on the Japan/US GNEP Action Plan, Safeguards and Physical Protection Working Group (SGPPWG) has surveyed an existing software in individual country. The purpose of this survey will serve as a basis for determining what needs may exist in this arena for development of next-generation safeguards systems and approaches. Exchanging information regarding software tools for safeguards and discussing about a next research and development program of developing a general-purpose safeguards tool should be beneficial to a safeguards system design and indispensable to evaluate a safeguards system for future nuclear fuel facilities.

JAEA Reports

Study of waste acceptance criteria for low-level radioactive waste from medical, industrial, and research facilities (Contract research)

Koibuchi, Hiroto; Dohi, Terumi; Ishiguro, Hideharu*; Hayashi, Masaru*; Senda, Masaki*

JAEA-Review 2008-034, 59 Pages, 2008/12

JAEA-Review-2008-034.pdf:10.61MB

Japan Atomic Energy Agency (JAEA) is supposed to draw up the plan for the disposal program of the very low-level radioactive waste and low-level radioactive waste generated from medical, industrial and research facilities. For instance, there are these facilities in JAEA, universities, private companies, and so on. JAEA has to get to know about the waste and its acceptance of other institutions described above because it is important for us to hold the licenses for the disposal program regarding safety assessment. This report presents the basic data concerning radioactive waste of research institutes etc. except RI waste, domestic and foreign information related to acceptance criteria for disposal of the low-level radioactive waste, the current status of foreign medical waste management, waste acceptance, and such. In this report, Japan's acceptance criteria were summarized on the basis of present regulation. And, the criteria of foreign countries, United States, France, United Kingdom and Spain, were investigated by survey of each reference. In addition, it was reported that the amount of waste from laboratories etc. for near-surface disposal and their characterization in our country. The Subjects of future work, the treatment of hazardous waste, the problem of the double-regulation (the Nuclear Reactor Regulation Law and the Law Concerning Prevention from Radiation Hazards due to Radioisotopes and Others) and the possession of waste were discussed here.

JAEA Reports

Investigation of sub-surface disposal concept; The Cases of Finland and Sweden (Contract research)

Koibuchi, Hiroto; Dohi, Terumi; Nakagoshi, Akio*; Amemiya, Kiyoshi*

JAEA-Review 2008-035, 21 Pages, 2009/02

JAEA-Review-2008-035.pdf:1.28MB

Sub-surface disposal is one of the disposal methods for low-level radioactive waste in Japan. It will operate below the generally used depth domestically. The waste disposed by this method is assumed to be core internals and part of TRU (the transuranium elements) waste from reprocessing and MOX (mix oxide fuel) fuel fabrication facilities. These contain the waste generated as a result of research activities, too. In order to establish a safety regulation for the disposal, a case study of the overseas disposal is useful. The similar disposal plan of Japan has been considered or already operated especially in Finland and Sweden. Therefore, in this study, we investigated current status and concept of appropriate sub-surface disposal in both countries as below. In Finland, waste management and disposal methods are regulated by Nuclear Energy Act and national policy. Low and intermediate level wastes are disposed into the cave in bedrock at each nuclear power plant site. In Sweden, safety handling and disposal of waste are regulated by Act on Nuclear Activities. The disposal of low and intermediate level wastes has been operated under the seabed. This operation is carried out by a joint company which the nuclear companies have formed. In addition, we reported a site selection, burial depth and financial plan etc. in both nations.

JAEA Reports

Proceedings of the International Advisory Committee on "Biomolecular Dynamics Instrument DNA" and the Workshop on "Biomolecular Dynamics Backscattering Spectrometers"; February 27-29, 2008, J-PARC Center, Japan Atomic Energy Agency, Tokai, Ibaraki, Japan

Arai, Masatoshi; Aizawa, Kazuya; Nakajima, Kenji; Shibata, Kaoru; Takahashi, Nobuaki

JAEA-Review 2008-036, 162 Pages, 2008/08

JAEA-Review-2008-036.pdf:38.32MB

A workshop entitled "Biomolecular Dynamics Backscattering Spectrometers" was held on February 27th - 29th, 2008 at J-PARC Center, Japan Atomic Energy Agency. This workshop was planned to be held for aiming to realize an innovative neutron backscattering instrument, namely DNA, in the MLF and thus four leading scientists in the field of neutron backscattering instruments were invited as the International Advisory Committee (IAC member: Dr. Dan Neumann (Chair); Prof. Ferenc Mezei, Dr. Hannu Mutka; Dr. Philip Tregenna-Piggott) for DNA from institutes in the United States, France and Switzerland, where backscattering instruments are in-service. It was therefore held in the form of lecture anterior and then in the form of the committee posterior. This report includes the executive summary of the IAC and materials of the presentations in the IAC and the workshop.

JAEA Reports

Handbook on process and chemistry of nuclear fuel reprocessing, 2

Research Group for Aqueous Separation Process Chemistry

JAEA-Review 2008-037, 702 Pages, 2008/10

JAEA-Review-2008-037.pdf:16.98MB
JAEA-Review-2008-037(errata).pdf:0.27MB

"Wet-type" nuclear fuel reprocessing technology, based on PUREX technology, has wide applicability as the principal reprocessing technology of the first generation, and relating technologies, waste management for example, are highly developed, too. It is quite important to establish a database summarizing fundamental information about the process and the chemistry of "wet-type" reprocessing, because it contributes to establish and develop fuel reprocessing technology and nuclear fuel cycle treating high burn-up UO$$_{2}$$ fuel and spent MOX fuel, and to utilize "wet-type" reprocessing technology much widely. This handbook is the second edition of the first report, which summarizes the fundamental data on process and chemistry, which was collected and examined by "Editing Committee of Handbook on Process and Chemistry of Nuclear Fuel Reprocessing" from FY 1993 until FY 2000.

JAEA Reports

Systemization of burnup sensitivity analysis code, 2 (Contract research)

Tatsumi, Masahiro*; Hyodo, Hideaki*

JAEA-Review 2008-038, 95 Pages, 2008/08

JAEA-Review-2008-038.pdf:2.09MB

The analysis of burnup characteristics is needed to effectively use burnup characteristics data in the actual cores based on the cross-section adjustment method. So far, development of an analysis code for burnup sensitivity, SAGEP-BURN, has been done and confirmed its effectiveness. However, there is a problem that analysis sequences become inefficient because of a big burden to user due to complexity of the theory of burnup sensitivity and limitation of the system. It is also desired to rearrange the system for future revision since it is becoming difficult to implement new functionalities in the existing large system. Therefore, systemization of the burnup sensitivity analysis code has been done with an object-oriented scripting language. (NB: This document is a translation of JNC TJ9410 2004-002 published in February 2005.)

JAEA Reports

Study plan for research on long-term stability of geological environments in FY2008

Nakatsuka, Noboru; Nohara, Tsuyoshi; Umeda, Koji; Ishimaru, Tsuneari; Hanamuro, Takahiro; Saito, Tatsuo; Yasue, Kenichi; Niwa, Masakazu

JAEA-Review 2008-039, 19 Pages, 2008/09

JAEA-Review-2008-039.pdf:4.95MB

The Japanese islands are located in the tectonically active Circum-Pacific Mobile Belt. As a result, Japan has a high frequency of earthquakes and eruptions. Special consideration is given to the long-term stability of the geological environment, taking into account volcanism, faulting, uplift, denudation, climatic change and sea-level change in Japan. Development of research/prediction technologies for geotectonic events has been carried out to evaluate the long-term stability of the geological environment in Japan. During fiscal year 2008, research/prediction about the following items will be carried out. Concerning earthquake and fault movement, we continue to develop research techniques for evolutional history and activity of fault, and carry out case studies for development of effective assessment model in the fault zones will be carried out. For volcanological and geothermal studies, we are planning to provide an integrated approach for detecting crustal magma and/or geothermal fluid in deep underground using geophysical and geochemical data, and models assessing the likelihood of future volcanism and its influence on geological environment. Concerning uplift, denudation, climatic change and sea-level change, we plan to arrange research techniques for reconstruction of paleo-topography and paleo-climate, and to establish a simulation model for landform development. Concerning a general evaluation study about the long-term stability of the geological environment, information maintenance about a change of geological environment with hydrothermal activity, and development of simulation techniques for groundwater flow related by crustal movement, climatic change will be carried out. In addition, maintenance of development of analytical methods to perform the data acquisition that is necessary for these studies will be carried out.

JAEA Reports

Studies of super-critical CO$$_{2}$$ gas turbine power generation fast reactor(Contract research, Translated document)

Kisohara, Naoyuki; Kotake, Shoji; Sakamoto, Yoshihiko

JAEA-Review 2008-040, 67 Pages, 2008/08

JAEA-Review-2008-040.pdf:3.93MB

(1) Preliminary design of an SFR that adopts a super-critical CO$$_{2}$$ turbine has been made. This SFR system eliminates secondary sodium circuits. The power generation efficiency of the SFR is 42%. Compared to a SFR that adopts a steam cycle with secondary sodium circuits, the reactor building volume of the SC-CO$$_{2}$$ SFR is reduced by 20%. (2) A super-critical CO$$_{2}$$ cycle test loop was fabricated. The high efficiency of a compressor is confirmed near the super-critical region. The temperature efficiencies of PCHE recuperators are 98-99% (hot leg). No flow instability is observed in the loop operation. (3) Na/CO$$_{2}$$ Reaction tests were executed. Continuous reaction occurs more than 570-580$$^{circ}$$C. Reaction products are Na$$_{2}$$CO$$_{3}$$ and CO. The reaction heat is 50-75kJ/Na-mol. (4) Safety calculation was done for 1 DEG tube failure in Na/CO$$_{2}$$ heat exchanger. The maximum pressure in the primary circuit is below the allowed level. The void reactivity of the reactor core also has no affect. The reaction product brought no sodium flow blockage in fuel assemblies. (5) After an exposure of 600$$^{circ}$$C-5000 hours in super-critical CO$$_{2}$$ environment, the corrosion of 12Cr steel and 316FR were 170g/m$$^{2}$$ and 5g/m$$^{2}$$, respectively. 316 FR shows a good corrosion proof property.

JAEA Reports

Present status of technology development on decommissioning and waste management in Nuclear Cycle Backend Directorate; Progress in 2007

Editorial Committee of R&D Results

JAEA-Review 2008-041, 59 Pages, 2008/07

JAEA-Review-2008-041.pdf:12.49MB

It is an important issue for Japan Atomic Energy Agency to take measures against the matters on decommissioning of retired nuclear facilities and management of low-level radioactive waste, and the measures must be taken with rational way by ensuring the safety. As the development, improvement and proper deployment of technologies will be key factors, a technology development program is under way in Nuclear Cycle Backend Directorate. The technology development items are selected from the viewpoint of cost reduction; these include the development of computer systems for planning and evaluation of decommissioning programs, calcination method for pretreatment of waste for disposal, supercritical CO$$_{2}$$ fluid leaching method for decontamination, rapid and simplified radiation measurement, evaluation of radioactive characteristics of waste and so on. This report describes outline and progress of the technology development program conducted in FY2007 far by the research and development unit.

JAEA Reports

Brief report of the JAEA cooperative research (A) on the nuclear fuel cycle for 2007

Research Cooperation Section

JAEA-Review 2008-042, 184 Pages, 2008/10

JAEA-Review-2008-042.pdf:7.06MB

This report includes a summary of the results of the research carried out in fiscal year 2007 on 32 research collaboration subjects for preceding basic engineering research related to fast breeder reactors, the nuclear fuel cycle, radiation safety and geological disposal/geoscience.

JAEA Reports

Annual report on major results and progress of Fusion Research and Development Directorate of JAEA from April 1, 2006 to March 31, 2007

Fusion Research and Development Directorate

JAEA-Review 2008-043, 116 Pages, 2008/08

JAEA-Review-2008-043.pdf:50.83MB

This annual report provides an overview of major results and progress on research and development (R&D) activities at Fusion Research and Development Directorate of Japan Atomic Energy Agency (JAEA) from April 1, 2006 to March 31, 2007, including those performed in collaboration with other research establishments of JAEA, research institutes, and universities.

JAEA Reports

Environmental monitoring for discharge of low level liquid waste from the Tokai Reprocessing Plant to the marine environment; Evaluation for influence of released radionuclides in the marine environment from the hot-test to the end of contract based reprocessing

Takeishi, Minoru; Nakano, Masanao; Kokubun, Yuji; Kono, Takahiko; Maejima, Kyoko*

JAEA-Review 2008-044, 93 Pages, 2008/10

JAEA-Review-2008-044.pdf:9.23MB

The Tokai Reprocessing Plant (TRP) was designed for commercial Light Water Reactor (LWR) power station as the first reprocessing plant in Japan. The TRP had been processed over 1000 tons of spent fuels up to 2006 through the hot test operation since 1977 and the routine operations since 1981. Almost of radioactive materials in the liquid waste were removed out by the process using multiple evaporators. However, low level liquid effluents were discharged to the sea through a long pipeline after confirmation of concentration of radionuclides beneath the limits by the Safety regulation of the TRP. The environmental monitoring had confirmed whether an unexpected release caused an influence to the environment. The environmental monitoring for seawater, sea sediments and marine products such as fishes, shellfish and seaweeds had been carried out offshore the Tokai-mura since 1977. This report reviewed comprehensively the all data obtained marine environmental monitoring since 1977.

JAEA Reports

Review of JT-60U experimental results in 2005 and 2006

JT-60 Team

JAEA-Review 2008-045, 142 Pages, 2008/10

JAEA-Review-2008-045.pdf:22.52MB

The results from the JT-60U experiments in 2005 and 2006 are reviewed. In this experimental campaign, significant progress has been made in development of steady-state advanced tokamak scenarios leading to realization of fusion reactors and establishment of the physics basis for ITER. Ferritic steel tiles have been installed to reduce the toroidal field ripple and reduce fast ion losses. Thus high normalized beta ($$beta$$$$_{rm N}$$$$sim$$4.2) exceeding the no-wall ideal limit has been achieved. High normalized beta ($$beta$$$$_{rm N}$$$$sim$$2.3) together with high confinement (HH$$_{98(rm y,2)}$$$$sim$$1) has been sustained for 23.1s. On the other hand, in high-density ELMy H-mode discharges, the density control for $$sim$$ 30s without the wall pumping has been successfully demonstrated by the divertor pumping.

JAEA Reports

A Semi annual report on the activities in Safety Administration Department; Report of the first half of 2007

Hayashi, Naomi

JAEA-Review 2008-046, 182 Pages, 2008/10

JAEA-Review-2008-046.pdf:10.21MB

This report is the summary of the activities of Safety Administration Department since April, 2007 until September, 2007.

JAEA Reports

Preparation of computer codes for analyzing sensitivity coefficients of burnup characteristics, 2 (Contract research, Translated Document)

Hanaki, Hiroshi*; Sanda, Toshio*; Ohashi, Masahisa*

JAEA-Review 2008-047, 266 Pages, 2008/10

JAEA-Review-2008-047.pdf:62.06MB

It is thought to improve the prediction accuracy for burnup characteristics using many burnup data of "Joyo" effectively. It is thought the best way to adjust cross-sections using sensitivity coefficients of burnup characteristics to utilize burnup data of "Joyo". Therefore in this work computer codes for analyzing sensitivity coefficients of burnup characteristics had been prepared since 1992. The results are as follows: (1) The computer codes which could analyze sensitivity coefficients of burnup characteristics taking into consideration plural cycles and refueling were prepared, therefore it came to be able to adjust cross-sections using burnup data and to estimate the accuracy for design of large LMFBR cores. (2) The adequacy of prepared codes was made sure by comparing with direct calculations. (NB: This document is a translation of PNC TJ9124 94-007 Vol.2 published in March 1997.)

JAEA Reports

Report on the risk communication activities

Takashita, Hirofumi; Yonezawa, Rika; Shobu, Nobuhiro; Ayame, Junko; Gunji, Ikuko; Asanuma, Misuzu

JAEA-Review 2008-048, 204 Pages, 2008/10

JAEA-Review-2008-048.pdf:33.22MB

This report summarizes the risk communication activities of Nuclear Fuel Cycle Engineering Laboratories conducted by mainly Risk Communication Study Office. The activities are classified into three categories: research and study on risk communication, message design and development of information transmission tools, and implementation of risk communication. This report shows those activities, and discusses the effect and evaluation of the activities. Future development of our risk communication activities is also described.

JAEA Reports

Operation, test, research and development of the High Temperature Engineering Test Reactor (HTTR) (FY2007)

Department of HTTR

JAEA-Review 2008-049, 132 Pages, 2008/10

JAEA-Review-2008-049.pdf:31.87MB

The High Temperature Engineering Test Reactor (HTTR) constructed at the Oarai Research and Development Center of the Japan Atomic Energy Agency (JAEA) is the first high-temperature gas-cooled reactor (HTGR) in Japan. The HTTR is a graphite-moderated and helium gas-cooled reactor with 30 MW of thermal power. In fiscal year 2007, we have carried out long-term (30 days) operation to accumulate operational data for HTGR developments. Periodical inspections, exchange of filter of primary gas circulators and in-service inspection of the reactor pressure vessel were also conducted, and manufacturing of control rod for exchange was started. This report summarizes activities and results of HTTR operation, maintenance, and several R&Ds, which were carried out in the fiscal year 2007.

JAEA Reports

Review of the studies on the effect of ionizing radiation for redox front migration in HLW repository

Yamaguchi, Makoto; Yui, Mikazu

JAEA-Review 2008-050, 61 Pages, 2009/01

JAEA-Review-2008-050.pdf:3.67MB

Studies on the effect of ionizing radiation for redox front migration in HLW repository were reviewed. The concept of the redox front by groundwater radiolysis around HLW was proposed by Neretnieks in 1982, and it was employed in the performance assessment of spent fuel disposal system executed by Swedish regulatory organization (SKI) in early 90s. With very conservative assumption that all the radiolytic oxidants diffuse into engineered barrier, the redox front reached the bedrock after several hundred years after canister failure, which increased the dose rate of redox-sensitive radioactive elements. However, dissolution tests of spent fuels under various redox conditions indicated that dissolved hydrogen strongly suppress the oxidative dissolution of UO$$_{2}$$ matrix and redox front migration by radiolytic oxidants has not been mentioned in performance assessments since late 90s.

JAEA Reports

Investigation on high availability-factor achievement of JMTR; How to achieve 60% availability-factor

Takemoto, Noriyuki; Izumo, Hironobu; Inoue, Shuichi; Abe, Shinichi; Naka, Michihiro; Akashi, Kazutomo; Omi, Masao; Miyazawa, Masataka; Baba, Osamu*; Nagao, Yoshiharu

JAEA-Review 2008-051, 36 Pages, 2008/10

JAEA-Review-2008-051.pdf:3.14MB

The JMTR has been refurbished to restart operation in FY2011. The restarted JMTR plays roles of (1) measures for long-term operation of light water reactors, (2) improvement in scientific technique, (3) increase of industrial use, (4) training of human resources, etc. It is needed to operate the restarted JMTR safety and stably and maintain high available factor (50$$sim$$70%) because of increasing of irradiation utilization demand. In this report, measures for training of reactor operators, organization for operating, etc were proposed to operate reactor safety and smoothly. And also reactor operation procedure was examined to improve available factor up to world level for materials testing reactor. As a result, it was turned out to be possible to realize stably 210 days operation per year (available factor: 60%).

JAEA Reports

Report on the cooperating researches utilizing fusion engineering facilities completed in the fiscal year 2007 (Joint research)

Division of Fusion Energy Technology

JAEA-Review 2008-052, 91 Pages, 2008/11

JAEA-Review-2008-052.pdf:16.85MB

The Division of Fusion Energy Technology of the Fusion Research and Development Directorate is carrying out cooperating researches with universities, research institutes and industries using five fusion engineering facilities; Caisson Assembly for Tritium Safety Study (CATS), Fusion Neutronics Source (FNS), MeV Test Facility (MTF), JAEA Electron Beam Irradiation System (JEBIS), RF Test Stand (RFTS). In the fiscal year 2007 (from April 1, 2007 to March 31, 2008), 24 activities were carried out as the cooperating researches. This report reviews the results of 8 activities which were completed in the fiscal year 2007.

JAEA Reports

Summaries of research and development activities by using JAEA computer system in FY2007 (April 1, 2007 - March 31, 2008)

Information Technology Systems' Management and Operating Office

JAEA-Review 2008-053, 213 Pages, 2008/11

JAEA-Review-2008-053.pdf:47.69MB

To support research and development activities in Japan Atomic Energy Agency (JAEA), Center for Promotion of Computational Science and Engineering (CCSE) operates and manages the computer systems including super-computers and network system. CCSE operates and manages the computer system and network system. This report presents usage records of the JAEA computer system and the big users' research and development activities by using the computer system in FY2007 (April 1, 2007 - March 31, 2008).

JAEA Reports

JAEA-Tokai tandem annual report 2007; April 1, 2007 - March 31, 2008

Department of Research Reactor and Tandem Accelerator

JAEA-Review 2008-054, 149 Pages, 2008/11

JAEA-Review-2008-054.pdf:21.68MB

The JAEA-Tokai tandem accelerator facility has been used in various fields of heavy ion nuclear science and material science not only by JAEA personnel but also by researchers from universities, institutes and companies. This annual report describes a summary of research activities carried out in the period between April 1, 2007 and March 31, 2008. The forty-nine summary reports from users were categorized into seven research/development fields: (1) accelerator operation and development, (2) nuclear structure, (3) nuclear reaction, (4) nuclear chemistry, (5) nuclear theory, (6) atomic physics and solid state physics, (7) radiation effects in materials. Also contained are lists of publications, meetings, technical staff, researchers in JAEA and cooperative researchers with universities.

JAEA Reports

JAEA Takasaki annual report 2007

Tanaka, Shigeru

JAEA-Review 2008-055, 229 Pages, 2008/11

JAEA-Review-2008-055.pdf:49.3MB

JAEA Takasaki annual report 2007 describes research and development activities performed from April 1, 2007 to March 31, 2008 with Takasaki Ion Accelerators for Advanced Radiation Application (TIARA, four ion accelerators), and electron/$$gamma$$-ray irradiation facilities (an electron accelerator and three $$^{60}$$Co $$gamma$$-ray irradiation facilities) at Takasaki Advanced Radiation Research Institute, Japan Atomic Energy Agency (JAEA Takasaki). These activities are classified into four research fields: (1) space, nuclear and energy engineering, (2) environmental conservation and resource security, (3) biotechnology and medical application, and (4) advanced materials, analysis and novel technology. This annual report contains 174 reports consisting of 166 research papers and 8 status reports on operation/maintenance of the irradiation facilities described above, and a list of publications, related press-releases, TV programs, patents, and the type of research collaborations as Appendices.

JAEA Reports

Proceedings of the Workshop on Multiple Prompt gamma-ray Analysis; Tokai, February 19, 2008

Ebihara, Mitsuru*; Hatsukawa, Yuichi; Oshima, Masumi

JAEA-Review 2008-056, 65 Pages, 2009/01

JAEA-Review-2008-056.pdf:15.01MB

The workshop on "Multiple Prompt Gamma-ray Analysis" was held on February 19, 2008 at Tokai. It is based on a project, "Development of real time, non destructive ultra sensitive elemental analysis using multiple gamma-ray detections and prompt gamma-ray analysis and its application to real samples", one of the High Priority Cooperative Research Programs performed by Japan Atomic Energy Agency and the University of Tokyo. This report presents the papers and the materials of 9 presentations in the workshop.

JAEA Reports

Annual report on the environmental radiation monitoring around the Tokai Reprocessing Plant FY2007

Takeishi, Minoru; Matsuura, Kenichi; Watanabe, Hitoshi; Nakano, Masanao; Takeyasu, Masanori; Isozaki, Hisaaki; Isozaki, Tokuju; Morisawa, Masato; Fujita, Hiroki; Kokubun, Yuji; et al.

JAEA-Review 2008-057, 155 Pages, 2008/11

JAEA-Review-2008-057.pdf:2.15MB

Environmental radiation monitoring around the Tokai Reprocessing Plant has been performed by the Nuclear Fuel Cycle Engineering Laboratories, based on "Safety Regulations for the Reprocessing Plant of JAEA, Chapter IV; Environmental Monitoring". This annual report presents the results of the environmental monitoring and the dose estimation to the hypothetical inhabitant due to the radioactivity discharged to the atmosphere and the sea during April 2007 to March 2008. Appendices present comprehensive information, such as monitoring program, monitoring methods, monitoring results and its trends, meteorological data and discharged radioactive wastes.

JAEA Reports

Annual report of Nuclear Emergency Assistance and Training Center (April 1, 2006 - March 31, 2008)

Nuclear Emergency Assistance and Training Center

JAEA-Review 2008-058, 86 Pages, 2008/12

JAEA-Review-2008-058.pdf:34.72MB

When a nuclear emergency occurs in Japan, JAEA provides technical support to the National government, local governments, police, fire station and license holder etc. They are Designated Public Organizations conforming to the Basic Law on Emergency Preparedness and the Basic Plan for Disaster Countermeasures. The Nuclear Emergency Assistance & Training Center (NEAT) of JAEA provides a comprehensive range of technical support activities to an off-site center in case of a nuclear emergency. Specifically, NEAT gives technical advice and information, provides for the dispatch of specialist as required, supplies emergency equipments and materials to the Joint Council of Nuclear Disaster Countermeasures, which meets at the off-site center. This annual report summarized the activities of JAEA/NEAT in the fiscal year 2006 and 2007.

JAEA Reports

The First Studsvik AB - JAEA meeting for cooperation in nuclear energy research and development; July 18, 2008, JAEA-Oarai

Ishihara, Masahiro; Yanagihara, Satoshi; Karlsson, M.*; Stenmark, A.*

JAEA-Review 2008-059, 81 Pages, 2009/01

JAEA-Review-2008-059.pdf:13.68MB

Based on the implemental agreement between the Studsvik AB and the Japan Atomic Energy Agency (JAEA) for cooperation in nuclear energy research and development, the first annual meeting was held at Oarai Research and Development Center, Japan Atomic Energy Agency. In this meeting, information exchange on two cooperation areas, "Radioactive waste treatment technology including recycling of materials" and "Technical developments for the neutron irradiation experiments in materials testing reactors", was carried out, and future plan in cooperation was discussed. This report describes contents of information exchange and discussions in two cooperation areas.

JAEA Reports

Annual report on the effluent control of low level liquid waste in Nuclear Fuel Cycle Engineering Laboratories FY2007

Takeishi, Minoru; Matsuura, Kenichi; Watanabe, Hitoshi; Nakano, Masanao; Kono, Takahiko; Hiyama, Yoshinori; Fujii, Jun*; Kikuchi, Masaaki*; Sagawa, Fumiaki*; Otani, Kazunori*

JAEA-Review 2008-060, 131 Pages, 2008/12

JAEA-Review-2008-060.pdf:13.33MB

Based on the regulations (the safety regulation of Tokai reprocessing plant, the safety regulation of nuclear fuel material usage facilities, radiation safety rule, the regulation about prevention from radiation hazards due to radioisotopes, which are related with the nuclear regulatory acts, and the local agreement concerning with safety and environment conservation around nuclear facilities, the water pollution control law, and byelaw of Ibaraki prefecture), this report describes the effluent control results of liquid waste discharged from the JAEA's Nuclear Fuel Cycle Engineering Laboratories in the fiscal year 2007, from 1st April 2007 to 31st March 2008. In this period, the concentrations and the quantities of the radioactive materials discharged from the reprocessing plant, the plutonium fuel fabrication facilities, and the other facilities were much lower than the authorized limits of the above regulations.

JAEA Reports

Annual report of Fusion Research and Development Directorate of JAEA from April 1, 2007 to March 31, 2008

Fusion Research and Development Directorate

JAEA-Review 2008-061, 119 Pages, 2009/01

JAEA-Review-2008-061-1.pdf:29.12MB
JAEA-Review-2008-061-2.pdf:23.72MB

This annual report provides an overview of major results and progress on research and development activities at Fusion Research and Development Directorate of Japan Atomic Energy Agency (JAEA) from April 1, 2007 to March 31, 2008, including those performed in collaboration with other directorates of JAEA, research institutes, and universities. In October 2007, ITER Agreements entered into force and JAEA was designated as the Japanese Domestic Agency by Japanese Government. In June 2007, JAEA was assigned as the Implementing Agency for the Broader Approach Activities. The JT-60U operation regime was extended toward the long sustainment of high normalized beta ($$beta_N$$) with good confinement ($$beta_N = 2.6 times 28 s$$). In fusion reactor technologies, a steady state operation of the 170 GHz gyrotron up to 800 s with 1 MW was demonstrated for ITER. In addition, theoretical and analytical researches on fusion plasmas and design study on DEMO reactor were progressed substantially.

JAEA Reports

Recent progress of analytical methods of spent nuclear fuel, Review

Yoshida, Zenko; Watanabe, Kazuo; Ito, Mitsuo; Ueno, Takashi; Takeshita, Hidefumi

JAEA-Review 2008-062, 34 Pages, 2009/01

JAEA-Review-2008-062.pdf:4.07MB

Analytical methods for the spent nuclear fuel (SF) have been greatly innovated recently. This methodological innovation is mainly caused by rapid and remarkable progress of induced coupled plasma-mass spectrometry (ICP-MS) which is utilized for the isotopic analysis of actinoid elements (U, Np, Pu, Am, Cm) and fission product elements in the SF samples. The quantity of the objective element as well as the volume of the sample solution needed for the ICP-MS measurement are, in principle, much less than those required for the measurement by other analytical methods. ICP-MS makes it possible to reduce the radiation dose of the operator and to minimize the amount of the radioactive wastes generated from the analytical work. For the precise and accurate isotopic analysis of the objective element in the SF sample by mass spectrometry, the interfering element having isobars needs to be separated prior to the measurement. This review highlights the development of the separation methods and isotopic analysis methods for the analysis of the SF based on more than 50 recent publications and the future problems to be solved and prospects are discussed.

JAEA Reports

Annual report for FY2007 on the activities of radiation control in Nuclear Science Research Institute etc. (April 1, 2007 - March 31, 2008)

Department of Radiation Protection, Nuclear Science Research Institute; Safety Section, Department of Administrative Services, Takasaki Advanced Radiation Research Institut; Safety Section, Department of Administrative Services, Kansai Photon Science Institute; Operation Safety Administration Section, Mutsu Office

JAEA-Review 2008-063, 161 Pages, 2009/01

JAEA-Review-2008-063.pdf:10.56MB

This annual report describes the activities of Radiation Protection Sector in Department of Radiation Protection in Nuclear Science Research Institute, Safety Section in Takasaki Advanced Radiation Research Institute, Safety Section in Kansai Photon Science Institute and Operation Safety Administration Section in Aomori Research and Development Center.

JAEA Reports

Study on irradiation assisted stress corrosion cracking of austenitic stainless steels in nuclear energy environments (Thesis)

Nakano, Junichi

JAEA-Review 2008-064, 175 Pages, 2009/01

JAEA-Review-2008-064.pdf:19.16MB

Irradiation assisted stress corrosion cracking (IASCC) is known as a degradation phenomenon that is caused by synergistic effects of neutron /$$gamma$$ irradiation, stress/strain and high temperature water on structural materials. It is important to investigate stress corrosion cracking (SCC) and IASCC mechanisms from the viewpoint of the safety and reliability improvement in the nuclear energy system. To evaluate the influence of minor additional elements, heat treatment, cold working and neutron fluence on IASCC behavior, a slow strain rate technique facility for irradiated specimens has been developed and post irradiation examinations have been conducted. Based on results obtained from the IASCC studies, discussion regarding IASCC susceptibility, crack initiation and growth behaviors are described comprehensively in this paper.

JAEA Reports

Report on the observation of IAEA international emergency response exercise ConvEx-3(2008)

Yamamoto, Kazuya; Sumiya, Akihiro

JAEA-Review 2008-065, 95 Pages, 2009/02

JAEA-Review-2008-065.pdf:8.46MB

The International Atomic Energy Agency (IAEA) carried out a large-scale international emergency response exercise under the designated name of ConvEx-3(2008), accompanying the national exercise of Mexico in July 2008. This review report summarizes two simultaneous observations of the exercises in Mexico and the IAEA headquarter during ConvEx-3(2008).

JAEA Reports

Report on JAEA's Reimei Research Program

Ikezoe, Hiroshi

JAEA-Review 2008-066, 55 Pages, 2009/02

JAEA-Review-2008-066.pdf:6.37MB

The summaries of the 9 research subjects conducted through the Reimei Research Program are published for the growth and development of the new researches.

JAEA Reports

Activity report on the utilization of research reactors (JRR-3 and JRR-4); Japanese fiscal year, 2006

Research Reactor Utilization Section

JAEA-Review 2008-067, 482 Pages, 2009/01

JAEA-Review-2008-067.pdf:43.49MB

The volume contains 294 activity reports, which are categorized into the fields of neutron scattering (11 subcategories), neutron radiography, neutron activation analyses, RI productions, prompt $$gamma$$-ray analyses, and others submitted by the users in JAEA and from other organizations.

JAEA Reports

Practices for scientific communication on nuclear waste disposal towards the future generation

Sasaki, Yasuo; Numata, Yoshiaki; Torata, Shinichiro

JAEA-Review 2008-068, 23 Pages, 2009/02

JAEA-Review-2008-068.pdf:2.73MB

The nuclear waste disposal is still in discussion as one of the key issue while we continue the sustainable atomic energy use, and it has been taking with much of the viewpoint of the social acceptance. In addition it may be said that it is the problem that the long term necessity to promote the disposal arise the subjects of the security of people who take charge of the disposal project. Also the management of knowledge with technical information between generations would become another subject in the future. To find the way out of these concerns, the practices having been tryed by the researcher group towards the student generation are reviewed in this report. The results of the opinion exchange and scientific communication with the people in the educational institution by the disposal research scientists are reviewed based on the questionnaire and discussion at a practice of schooling and lecture at high schools and universities.

JAEA Reports

Annual report on operation and management of Hot Laboratories and Facilities; From April 1, 2007 to March 31, 2008

Department of Hot Laboratories and Facilities

JAEA-Review 2008-069, 92 Pages, 2009/02

JAEA-Review-2008-069.pdf:25.49MB

This is an annual report in a fiscal year 2007 that describes activities of the Reactor Fuel Examination Facility (RFEF), the Waste Safety Testing Facility (WASTEF), the Research Hot Laboratory (RHL) and the other research hot facilities in the Department of Hot Laboratories and Facilities.

JAEA Reports

Review of research on simulation engineering in FY2007

Center for Computational Science & e-Systems

JAEA-Review 2008-070, 43 Pages, 2009/02

JAEA-Review-2008-070.pdf:3.0MB

Research on simulation engineering for nuclear applications, based on "the plan for meeting the mid-term goal of the Japan Atomic Energy Agency", has been performed at Center for Computational Science & e-Systems, Japan Atomic Energy Agency (CCSE/JAEA). CCSE established the committee consisting outside experts and authorities which does research evaluation and advices for the assistance of the research and development. This report summarizes the result of the evaluation by the committee on the research on simulation engineering performed at CCSE/JAEA in FY2007.

JAEA Reports

Annual report on the present state and activities of the Radiation Protection Department, Nuclear Fuel Cycle Engineering Laboratories in fiscal 2007

Radiation Protection Department

JAEA-Review 2008-071, 144 Pages, 2009/02

JAEA-Review-2008-071.pdf:5.57MB

This annual report summarizes the various activities on radiation control at the nuclear fuel cycle facilities in Nuclear Fuel Cycle Engineering Laboratories, which were undertaken by the Radiation Protection Department in fiscal 2007.

JAEA Reports

Mizunami Underground Research Laboratory Project Plan for fiscal year 2008

Nishio, Kazuhisa; Oyama, Takuya; Mikake, Shinichiro; Mizuno, Takashi; Saegusa, Hiromitsu; Takeuchi, Ryuji; Amano, Kenji; Tsuruta, Tadahiko; Hama, Katsuhiro; Seno, Yasuhiro; et al.

JAEA-Review 2008-072, 28 Pages, 2009/02

JAEA-Review-2008-072.pdf:11.8MB

Japan Atomic Energy Agency (JAEA) at Tono Geoscience Center (TGC) 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 the MIU project is planned to be carried out in three phases over a period of 20 years; Surface-based Investigation Phase (Phase 1), Construction Phase (Phase 2) and Operation Phase (Phase 3). Currently, the project is under the Construction Phase. This document presents the following 2008 fiscal year plan based on the MIU Master Plan updated in 2002, (1) Investigation Plan, (2) Construction Plan, (3) Research Collaboration Plan, etc.

JAEA Reports

Mizunami Underground Research Laboratory Project, Annual report for fiscal year 2005

Nishio, Kazuhisa; Matsuoka, Toshiyuki; Mikake, Shinichiro; Tsuruta, Tadahiko; Amano, Kenji; Oyama, Takuya; Takeuchi, Ryuji; Saegusa, Hiromitsu; Hama, Katsuhiro; Yoshida, Haruo*; et al.

JAEA-Review 2008-073, 99 Pages, 2009/03

JAEA-Review-2008-073-1.pdf:37.33MB
JAEA-Review-2008-073-2.pdf:37.16MB

Japan Atomic Energy Agency (JAEA) at Tono Geoscience Center (TGC) is developing a geoscientific research project named 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 over a period of 20 years; Surface-based Investigation Phase (Phase 1), Construction Phase (Phase 2) and Operation Phase (Phase 3). Currently, the project is under the Construction Phase. This document presents the following results of the research and development performed in 2005 fiscal year, as a part of the Construction Phase based on the MIU Master Plan updated in 2002, (1) Investigation at the MIU Construction Site, (2) Construction at the MIU Construction Site, (3) Research Collaboration.

JAEA Reports

Present status and future plan of research and development in JAEA on partitioning and transmutation technology for long-lived nuclides

Nuclear Science and Engineering Directorate; Advanced Nuclear System Research and Development Directorate; J-PARC Center

JAEA-Review 2008-074, 246 Pages, 2009/03

JAEA-Review-2008-074-1.pdf:39.05MB
JAEA-Review-2008-074-2.pdf:42.72MB

The Japan Atomic Energy Agency has been conducting research and development (R&D) on partitioning and transmutation (P&T) technology for long-lived nuclides in accordance with the Atomic Energy Commission's "Research and Development of Technologies for Partitioning and Transmutation of Long-lived Nuclides-Status and Evaluation Report" issued in 2000. The present report reviews the progress of the investigation on the benefit and the cost of the P&T technology, the international trend of R&D, the progress and the future plan of R&D on the partitioning process and the transmutation cycle technology, together with the necessary infrastructure improvement including the Transmutation Experimental Facility as the Phase-II of the Japan Proton Accelerator Research Complex (J-PARC).

JAEA Reports

Environmental performance data in Environmental Report 2008

Environmental Management Section, Safety Administration Department

JAEA-Review 2008-075, 149 Pages, 2009/02

JAEA-Review-2008-075.pdf:19.81MB

Japan Atomic Energy Agency published the Environmental Report 2008 concerning the activities of FY 2007 in August, 2008 under "Law Concerning the Promotion of Business Activities with Environmental Consideration by Specified Corporations, etc, by Facilitating Access to Environmental Information, and Other Measures". This Report has been edited to show detailed environmental performance data in FY 2007 as the background of the Environmental Report would not only ensure traceability of the data in order to enhance the reliability of the environmental report, but also make useful measures for promoting activities of environmental considerations in JAEA.

JAEA Reports

Review on conformance of JMTR reactor facility to safety design examination guides for water-cooled reactors for test and research in JMTR reactor facility

Ide, Hiroshi; Naka, Michihiro; Sakuta, Yoshiyuki; Hori, Naohiko; Matsui, Yoshinori; Miyazawa, Masataka

JAEA-Review 2008-076, 442 Pages, 2009/03

JAEA-Review-2008-076.pdf:8.3MB

The safety design examination guides for water-cooled reactors for test and research was gathered in safe examination of the licensing as the purpose of showing the basics when the validity of the design is judged about from the viewpoint of keeping safety. For the confirmation of the JMTR reactor facility conforming the current guides, the check of the items mentioned in the licensing documents, annexes of licensing documents and related documents were carried out. As the result of check, there was the mention about conformity in licensing and so on. And the constructs, systems and devices which have safety functions have been produced under authorization of regulating authority. Therefore it was confirmed that the licensing were conformed to guides and the JMTR has enough performance.

JAEA Reports

Annual report of Nuclear Technology and Education Center (April 1, 2007 - March 31, 2008)

Nuclear Technology and Education Center

JAEA-Review 2008-077, 94 Pages, 2009/03

JAEA-Review-2008-077.pdf:5.34MB

This annual report summarizes the activities of Nuclear Technology and Education Center (NuTEC) of Japan Atomic Energy Agency (JAEA) in the fiscal year 2007. During this period, the number of trainees completing the domestic training courses was 466, and that for staff technical training was 694. Three prep-examination training courses for "1st class radiation protection supervisor", "Nuclear fuel protection supervisor" and "Professional engineer on nuclear and radiation" which were opened only for staff members were newly opened to the public. JAEA continued its cooperative activities with universities; cooperation with graduate school of University of Tokyo, cooperative graduate school program with 14 graduate schools and 1 under-graduate school, and Nuclear HRD Program initiated by MEXT and METI implemented since 2007. Joint course has started networking 3 universities utilizing the Japan Nuclear Education Network, and trial experimental courses for students from newly participating universities were offered. International cooperation was also conducted as scheduled. Joint training course and Instructor training program were carried out bilaterally with Indonesia, Thailand and Vietnam. Human Resources Development Workshop under the Forum for Nuclear Cooperation in Asia was arranged, and Asian Nuclear Training and Education Program to enhance the matching of the needs and available training program of the participating countries were discussed.

JAEA Reports

Minutes of the 3rd Meeting of "Technical Committee for Geological Isolation Research and Development"

Sasaki, Yasuo; Torata, Shinichiro; Numata, Yoshiaki

JAEA-Review 2008-078, 51 Pages, 2009/03

JAEA-Review-2008-078.pdf:5.57MB

JAEA organizes the "Technical Committee for Geological Isolation Research & Development", which consists of specialists in relevant fields at universities and institutes, in order to facilitate planning and conducting of a program of research and development (R&D) for geological disposal of high-level radioactive waste and TRU waste at JAEA-Tokai, through reflecting technical advices and comments made from them into the program. This report presents the minutes of the third meeting held in March 2008.

JAEA Reports

Annual report of JMTR FY2007

Department of JMTR Operation

JAEA-Review 2008-079, 27 Pages, 2009/03

JAEA-Review-2008-079.pdf:3.09MB

As for the refurbishment, the Japan Materials Testing Reactor (JMTR) has been stopping since JMTR 165th cycle operation was finished, and the JMTR is advancing its refurbishment to restart from FY2011. Regarding the management and operation of JMTR, inspection based on the law, maintenance and preservation work of facilities were carried out. Moreover, for the irradiation facility, maintenance and preservation works on the management and operation were also carried out. In the hot laboratory, post irradiation examinations using irradiated specimens in the JMTR were carried out. In addition, maintenance and preservation works of facilities were also carried out. This report describes the FY2007 activities relating to above mentions.

JAEA Reports

Investigation waste disposal procedure of spent ion exchange resin using overseas consignment

Kimura, Tadashi; Oto, Tsutomu; Izumo, Hironobu; Nagao, Yoshiharu; Kawamura, Hiroshi

JAEA-Review 2008-080, 16 Pages, 2009/03

JAEA-Review-2008-080.pdf:3.11MB

The ion exchange resin is used for the purification system of the primary cooling water and the pool canal water in the JMTR. The spent ion exchange resin is stored in the liquid waste tank. The amount of the spent ion exchange resin in the liquid waste tank increases with reactor operation. The possibility of the spent ion exchange resin processing for oversea processing facilities was examined as a procedure for processing of the spent ion exchange resin. As the results, technical, regulations, and social issues were extracted from the procedure of spent ion exchange resin processing at oversea processing facilities. Furthermore, the conditions of oversea processing were indicated.

JAEA Reports

Annual report of the Neutron Irradiation and Testing Reactor Center FY2007

Neutron Irradiation and Testing Reactor Center

JAEA-Review 2008-081, 30 Pages, 2009/03

JAEA-Review-2008-081.pdf:9.32MB

The Japan Materials Testing Reactor (JMTR), after first achieving criticality in March 1968, has used in testing the durability and integrity of reactor fuels and components, basic nuclear research, the production of radioisotopes (RIs), and other purposes. The JMTR, however, was halted in August 2006 after its 165th operation cycle, and is currently going through partial renewal of the apparatus and development of new irradiation equipment, geared toward being restarted in 2011. In addition, to cope with the strong requests of users for improved usability and accessibility with the JMTR, efforts are being made to increase reactor operating efficiency, shorten the turnaround time for producing results, and other necessary tasks for JMTR to commence reoperation. The present report summarizes the work carried out in 2007 for the refurbishment and restart of JMTR.

JAEA Reports

Annual report of the Neutron Irradiation and Testing Reactor Center FY 2007; April 1, 2007 - March 31, 2008

Neutron Irradiation and Testing Reactor Center

JAEA-Review 2008-082, 30 Pages, 2009/03

JAEA-Review-2008-082.pdf:7.82MB

The Japan Materials Testing Reactor (JMTR), achieving first criticality in March 1968, has been used in testing the durability and integrity of reactor fuels and components, basic nuclear research, the production of radioisotopes (RIs), and other purposes. The JMTR, however, was halted in August 2006 after its 165th cycle operation, and is currently going partial renewal of the apparatus and installation of new irradiation equipment, geared toward being restarted in 2011. In addition, to cope with the strong requests from users for improved usability of the JMTR, efforts are being made to increase reactor operating efficiency, shorten the turnaround time for obtaining results, and conduct other necessary tasks for JMTR to commence reoperation. The present report summarizes the activities carried out in 2007 for the refurbishment and restart of JMTR.

JAEA Reports

Proceedings of the 2nd Seminar of R&D on Advanced ORIENT; Ricotte, on November 7th, 2008

Sasaki, Yuji; Yamagishi, Isao; Ozawa, Masaki

JAEA-Review 2008-083, 182 Pages, 2009/03

JAEA-Review-2008-083.pdf:21.72MB

The 2nd Seminar of R&D on advanced ORIENT seminar was held on November 7th, 2008 at Ricotte, Japan Atomic Energy Agency. The first meeting of this seminar was held on Oarai, Ibaraki on May, 2008, and more than fifty participants including related researchers and general public people were attended to this seminar. The second seminar has headed by Nuclear Science and Engineering Directorate, JAEA on Tokai, Ibaraki with 63 participants. Spent nuclear fuel should be recognized not only mass of radioactive elements but also potentially useful materials including platinum metals and rare earth elements. Taking the cooperation with universities related companies and research institutes, into consideration, we aimed at expanding and progressing the basic researches. This report records abstracts and figures submitted from the oral speakers in this seminar.

JAEA Reports

Report on activities of "Technical Committee for Reducing Water Inflow into the Deep Shafts at the Mizunami Underground Research Laboratory (2006-FY2007)"

Geoscience Facility Construction Section, Tono Geoscience Center

JAEA-Review 2008-084, 82 Pages, 2009/03

JAEA-Review-2008-084.pdf:1.07MB

This technical committee was established for the purpose of obtaining technical comments and recommendations from specialists belonging to Universities and research institutes, and for deliberating on specific matters concerning the measures for reducing water inflow into the deep shafts at the Mizunami Underground Research Laboratory. This report presents an outline compilation of the minutes of meetings held in 2006-FY2007.

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