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JAEA Reports

Investigation on integrity of JMTR UCL elevated water tank

Kimura, Tadashi; Oto, Tsutomu; Miyauchi, Masaru; Nemoto, Nobuaki; Tobita, Kenji; Fukasaku, Akitomi; Takahashi, Kunihiro

JAEA-Review 2010-001, 27 Pages, 2010/03

JAEA-Review-2010-001.pdf:18.81MB

In order to investigate an integrity of the UCL (Utility Cooling Line) elevated water tank to be used for a long term after the JMTR restart, investigation on the base of the UCL elevated tank, especially for the part which had a significant aged effect, was carried out before the refurbishment work of the JMTR related facilities which had begun in FY2007. In the integrity investigation, it was confirmed that some part of the base bolts had significant aged effects, there were no evidence of crack and false indication in the welding region though thinning were observed in some parts of the base plate and the surrounding plate. After the investigation, repair works such as re-painting of the UCL elevated water tank were carried out from the viewpoint of prevention of flaking off, floating of the painting and the thinning due to corrosion based on the investigation results. In order to maintain the integrity of the UCL elevated tank, the periodical maintenance and the repair works of the base of the UCL elevated tank are important for continuous use of it in future.

JAEA Reports

Annual report on the activities in Safety Administration Department; Report of the fiscal year 2008

Hayashi, Naomi

JAEA-Review 2010-002, 269 Pages, 2010/03

JAEA-Review-2010-002.pdf:25.87MB

The activities of Safety Administration Department covers many fields in Nuclear Fuel Cycle Engineering Laboratories such as the management of a safety and health, the crisis management and the security, and the management of a quality assurance. This report is the summary of the activities of Safety Administration Department since April, 2008 until March 2009.

JAEA Reports

Ex-post evaluation of safety research by technology interaction analysis

Yanagisawa, Kazuaki; Komoda, Fumio*

JAEA-Review 2010-003, 28 Pages, 2010/06

JAEA-Review-2010-003.pdf:0.94MB

By using the database INSPEC, an ex-post evaluation of the safety research was carried out by a technology interaction analysis. Selected institutions were JAERI, ORNL and FZK. As the control term of INSPEC a water-reactor-safety was utilized and studied the established key technologies and the interacted technological elements. (1) For a nuclear safety research JAERI held priority to 22 out of 30 key technologies consisted of the nuclear fuels, the nuclear materials and so on. JAERI contributed much to Japan. For ORNL and FZK, 19 and 20 key technologies were held priorities. ORNL was in the ascendant at the nuclear power plant operation, while FZK held priority to the radiation protection. (2) JAERI and FZK interacted strongly with the accident, the engineering calculation, the fuel cladding and the reactor core cooling. The interaction was enhanced by an international cooperation like LOFT. As for JAERI and ORNL, they interacted strongly with the instruments and the research reactors.

JAEA Reports

Ex-post evaluation on basic science research; Predominance of research, dissemination of achievement and research activeness of laboratory

Yanagisawa, Kazuaki

JAEA-Review 2010-004, 61 Pages, 2010/06

JAEA-Review-2010-004.pdf:1.2MB

For post evaluation, the Department of Material Science was divided into four, namely Region 1 Material Science in Radiation Field, 2 Ultimate Property and New Material Science, 3 Actinide Chemistry and 4 Facility Development and Operation. Obtained results are as follows. (1) For the predominance of the research region, the region 3 (31%) had a predominance. (2) For the dissemination of achievement, the region 1 (28%) had an excellent external networking. (3) For research activeness of a laboratory evaluated by means of the numbers of JAERI original papers, the region 4 or 3 was judged to have predominance. (4) The present results were compared with those obtained from JAERI Pier Review, which was carried out by the outside intellectuals. The conclusion was in a good agreement in terms of the rate of attainability of the goal and the dissemination of achievement and repercussion effect.

JAEA Reports

Research on assurance system of nuclear fuel supply (Contract research)

Kobayashi, Naoki*; Naoi, Yosuke; Wakabayashi, Shuji; Tazaki, Makiko; Senzaki, Masao

JAEA-Review 2010-005, 50 Pages, 2010/08

JAEA-Review-2010-005.pdf:2.73MB

In order to facilitate international discussions on AOS, authors have conducted studies of AOS system based on Japanese Government's proposal "IAEA Standby Arrangement System (INFCIRC/683)". In this paper, we have been able to discuss feasibility of AOS system more specifically by including additional costs and period required for AOS, and to present a system which could work as a practical system. Issues we have tried to tackle here include definitions of AOS, and roles of consumer states, supplier states, IAEA and nuclear industries. We present some solutions including broadening coverage of AOS, declaration by supplier states on AOS, establishing advisory committee in the IAEA on the actual application of AOS, and setting up an IAEA fund for AOS.

JAEA Reports

Proceedings of the Workshop on Leading Edge of Iron-based High-T$$_{c}$$ Superconductor Research; Review and Prospect of the Mechanism and Physical Properties

Shamoto, Shinichi; Kodama, Katsuaki

JAEA-Review 2010-006, 235 Pages, 2010/05

JAEA-Review-2010-006.pdf:37.21MB

The 3rd workshop of the NIMS-RIKEN-JAEA Cooperative Research Program "Quantum Complex Phenomena", entitled "Leading Edge of Iron-based High-T$$_{c}$$ Superconductor Research, -Review and Prospect of the Mechanism and Physical Properties-", was held on November 28, 2009 at Center for Computational Science & e-Systems, Japan Atomic Energy Agency. Eminent researchers in the three institutes, AIST and universities talked and discussed the physical properties, theories, and synthesis of a series of iron-based high-T$$_{c}$$ superconductors which have been synthesized since the discovery of the superconductivity in LaFePO and LaFeAsO$$_{1-x}$$F$$_{x}$$ by Prof. Hosono's group of Tokyo Institute of Technology, including a future prospect of this research area.

JAEA Reports

Verification on reliability of heat exchanger for primary cooling system

Koike, Sumio; Gorai, Shigeru; Onoue, Ryuji; Otsuka, Kaoru

JAEA-Review 2010-007, 36 Pages, 2010/07

JAEA-Review-2010-007.pdf:5.0MB

Prior to the JMTR refurbishment, verification on reliability of the heat exchangers for primary cooling system was carried out to investigate an integrity of continuously use component. From a result of the significant corrosion, decrease of tube thickness, crack were not observed on the heat exchangers, and integrity of heat exchangers were confirmed. In the long terms usage of the heat exchangers, the maintenance based on periodical inspection and a long-term maintenance plan is scheduled.

JAEA Reports

Investigation on integrity of JMTR concrete structure

Miyauchi, Masaru; Kimura, Tadashi; Oto, Tsutomu; Nemoto, Nobuaki; Tobita, Kenji; Fukasaku, Akitomi; Takahashi, Kunihiro

JAEA-Review 2010-008, 106 Pages, 2010/06

JAEA-Review-2010-008.pdf:8.89MB

An integrity investigation was carried out for the JMTR Concrete Structure (Vent Stack, Trench, Canal Building, Filter Bank), which was the concrete structure and would be used for the long-term after JMTR restart, before the repair or replacement work of the JMTR related facilities that had begun in FY2007. In the integrity investigation, the concrete surface deterioration, the rebound number (nondestructive strength test), compressive strength using drilled concrete core test piece, the static modules of elasticity, the carbonation depth, the reinforced bar corrosion and the chloride ion content were investigated respectively and the integrity of concrete was confirmed. After the investigation, repair works such as re-painting of the Vent Stack and Trench were carried out from the viewpoint of prevention of flaking off, floating of the painting and the thinning due to the investigation results. In order to use the JMTR concrete structure continuously for long-term, it is important for maintaining the integrity of a concrete structure by the periodical maintenance and the repairing work including the building outer-wall surface painting that has been conducted up to now.

JAEA Reports

Fast reactor cycle technology development "mid-term technical session of the FaCT Project"; Session report and presentation materials

Advanced Nuclear System Research and Development Directorate

JAEA-Review 2010-009, 115 Pages, 2010/06

JAEA-Review-2010-009-01.pdf:57.37MB
JAEA-Review-2010-009-02.pdf:35.66MB

The Fast Reactor Cycle Technology Development (FaCT) project was launched in 2006 and has since been vigorously promoted. The first milestone of this project aims to decide whether to adopt the innovative technologies in 2010. As part of the mid-term review for this milestone, a technical session was held at Shinsei Bank Hall in Tokyo on August 7, 2009, and more than 200 people attended the session, including delegates from governments, universities, research organizations, electric utilities and atomic industries. In this session, JAEA (Japan Atomic Energy Agency) and MFBR (Mitsubishi FBR systems, Inc.) reported 2006-2008 R&D results of the FaCT project and obtained quite a lot of comments and opinions from the participants. These have now been successfully reflected in the R&D activities. This report hereinafter provides a summary of the session and the presentation materials.

JAEA Reports

JAEA thermodynamic database for performance assessment of geological disposal of high-level and TRU wastes; Selection of thermodynamic data of molybdenum

Kitamura, Akira; Kirishima, Akira*; Saito, Takumi*; Shibutani, Sanae*; Tochiyama, Osamu*

JAEA-Review 2010-010, 75 Pages, 2010/06

JAEA-Review-2010-010.pdf:1.27MB

Within the scope of the JAEA thermodynamic database project for performance assessment of geological disposal of high-level radioactive and TRU wastes, the selection of the thermodynamic data on the inorganic compounds and complexes of molybdenum were carried out. We focused to select thermodynamic data of aquous species and compounds which could form under repository conditions for the disposal of radioactive wastes, i.e. relatively low concentration of molybdenum and from near neutral through alkaline conditions. Selection of thermodynamic data was based on the guidelines by the Nuclear Energy Agency in the Organisation for Economic Co-operation and Development (OECD/NEA). Extensive literature survey was performed and all the obtained articles have been carefully reviewed to select the thermodynamic data for molybdenum. Thermodynamic data at 25 $$^{circ}$$C and zero ionic strength were determined from accepted thermodynamic data which were considered to be reliable. We especially paid attention to select formation constant of molybdate ion with hydrogen ion.

JAEA Reports

Survey on current status of international organizations and foreign countries for emergency preparedness and response and consider technical issues on guideline for nuclear emergency preparedness

Kimura, Masanori; Sato, Sohei; Ishikawa, Jun; Homma, Toshimitsu

JAEA-Review 2010-011, 147 Pages, 2010/06

JAEA-Review-2010-011.pdf:1.66MB

The review report describes survey results of nuclear emergency preparedness and response in international organizations and foreign countries, and consideration results of technical issues on the "Guideline for Nuclear Emergency Preparedness" issued by the NSC. In order to respond to nuclear emergency more effectively, the guideline should show the basic concept of emergency preparedness and response for the period between the beginning of the nuclear accident and the termination of early protective measurements. In order to introduce these new concepts to the guideline, all necessary issues should be arranged and considered in reference to the recent trend for the concept of nuclear emergency preparedness and response in international organizations and foreign countries.

JAEA Reports

Operation, test, research and development of the High Temperature Engineering Test Reactor (HTTR) (FY2008)

Department of HTTR

JAEA-Review 2010-012, 91 Pages, 2010/06

JAEA-Review-2010-012.pdf:3.76MB

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 30MW of thermal power. In fiscal year 2008, a operation for periodical inspections was planned. However, the operation was postponed because of small leakage at stand-pipe closure. For maintenance work, a reactor protection system was modified for new safety demonstration tests. Assembling and storage of secondary fuel were performed. Other maintenance works were also carried out. This report summarizes activities and results of HTTR operation, maintenance, and several R&Ds, which were carried out in the fiscal year 2008.

JAEA Reports

Ex-post evaluation; Research independency of the basic science study of JAERI

Yanagisawa, Kazuaki; Takahashi, Shoji*

JAEA-Review 2010-013, 29 Pages, 2010/06

JAEA-Review-2010-013.pdf:1.15MB

A research independency was defined here as the continuity of the research and the development of a corresponded field with the evolution of history. The three parameters considered were actinides, positron and neutron. The year was covered from 1978 to 2002. INIS was used as the tool. The authors revealed that important factors that led the sustainable success of the research independency of the basic science study were the constant efforts to accomplish his mission, the education of their successors to instructing the explicit and tacit research findings and the construction of intellectual networking with learned circles and industries, who were in good collaboration with JAERI. These were quantitatively clarified by our bibliometric study. The research independency experienced the time-dependent stage of germination, development and declination due to the interaction between development and impeded factors.

JAEA Reports

Mizunami Underground Research Laboratory Project, Annual report for fiscal year 2008

Takeuchi, Shinji; Kunimaru, Takanori; Mikake, Shinichiro; Nishio, Kazuhisa; Tsuruta, Tadahiko; Matsuoka, Toshiyuki; Hayano, Akira; Takeuchi, Ryuji; Saegusa, Hiromitsu; Oyama, Takuya; et al.

JAEA-Review 2010-014, 110 Pages, 2010/07

JAEA-Review-2010-014.pdf:27.34MB

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 I), Construction Phase (Phase II) and Operation Phase (Phase III). Currently, the project is under the Construction Phase. This document presents the following results of the research and development performed in fiscal year 2008, as a part of the Construction Phase based on the MIU Master Plan updated in 2002, (1) Investigation at the MIU Construction Site and the Shobasama Site, (2) Construction at the MIU Construction Site, (3) Research Collaboration.

JAEA Reports

History of the Research ad hoc committee on "Dissemination of information" and the Special ad hoc committee on "Dissemination of information" of the Atomic Energy Society of Japan

Itabashi, Keizo

JAEA-Review 2010-015, 313 Pages, 2010/06

JAEA-Review-2010-015.pdf:1.95MB

The Research ad hoc committee on "Dissemination of information" of the Atomic Energy Society of Japan was held 15 times from October 1970 to March 1973. After that, The Special ad hoc committee on "Dissemination of information" of the Atomic Energy Society of Japan was held 115 times from April 1973 to March 2009. The history of these two committees is described. Activity report is arranged including the information on change of the member and topics of the meeting, and minutes. Furthermore, the document list on International Nuclear Information System (INIS) from Japan is included.

JAEA Reports

Master plan of the Mizunami Underground Research Laboratory Project

Tono Geoscientific Research Unit, Geological Isolation Research and Development Directorate

JAEA-Review 2010-016, 37 Pages, 2010/06

JAEA-Review-2010-016.pdf:5.8MB

The Japan Atomic Energy Agency is implementing scientific studies of the deep geological environment and development of technologies to enhance the reliability of geological disposal technology ('geoscientific research') at Mizunami Underground Research Laboratory (MIU). The aims of the MIU Project are to establish techniques for investigation, analysis and assessment of the deep geological environment, and to develop a range of engineering techniques for deep underground application, with main focus on the crystalline rock with fresh ground-water condition. The master plan of the MIU project has been revised several times since 1996, reflecting the revision of "Long-term plan for Research, Development and Utilization of Nuclear Energy" and relocation of the research site. In 2009, revisions of the basic policy about fundamental strategy for geological disposal have resulted in the extension of the time range to reach the milestone on the establishment of methodologies for the detailed investigation. On the other hand, increasing role of the underground research facility as a platform for achieving the public acceptance of the geological disposal has been recognized. Thus JAEA has intended to construct an additional research gallery at a depth of 300m of the MIU and to revise the master plan therein. In this revision, major results of the Phase I(surface-based investigation) have highlighted and investigations for the Phase II (construction) and Phase III (operation) are restructured from the view point of their relative importance to the implementation of the geological disposal programme.

JAEA Reports

Investigation on integrity of canal expanded joint

Oto, Tsutomu; Kimura, Tadashi; Miyauchi, Masaru; Nemoto, Nobuaki; Tobita, Kenji; Fukasaku, Akitomi; Takahashi, Kunihiro

JAEA-Review 2010-017, 21 Pages, 2010/07

JAEA-Review-2010-017.pdf:7.68MB

An integrity investigation of a Canal Expanded Joint was carried out as one of the integrity investigation of the JMTR reactor building related facilities and components, before the repair or replacement work of the JMTR related facilities that had begun in FY2007. The Canal Expanded Joint will be used for long-term after the JMTR restart. In the integrity investigation, the visual inspection, the performance test (Surface observations, Durometer hardness test) were investigated respectively and the integrity of the Canal Expanded Joint was confirmed. In order to use the Canal Expanded Joint continuously for long-term, it is important for maintaining the integrity of the Canal Expanded Joint by the periodical maintenance and the repairing work including that has been conducted up to now.

JAEA Reports

Investigation on integrity of the surge tank, the degas tank and the purify water tank for the primary cooling system of JMTR

Nemoto, Hiroyoshi; Ebisawa, Hiroyuki; Ogasawara, Yasushi; Echigoya, Shinichi

JAEA-Review 2010-018, 32 Pages, 2010/07

JAEA-Review-2010-018.pdf:2.07MB

An integrity investigation was carried out for the JMTR reactor installations, which were the primary cooling system tanks (the surge tank, the degas tank and the purify water tank) and they would be used for the long term after JMTR restart, before the renewal work for the JMTR on FY2007. The visual inspection and the liquid penetrate test (PT) were carried out as the integrity investigation to confirm the integrity of primary cooling system tanks. In order to use the surge tank, the degas tank and the purify water tank continuously for long term, it is important for maintaining the integrity of the surge tank, the degas tank and the purify water tank by the periodical maintenance and the repairing work.

JAEA Reports

Inspection of JMTR secondary cooling system; Secondary cooling system piping and cooling tower

Watahiki, Shunsuke; Asano, Norikazu; Hanawa, Yoshio; Gorai, Shigeru; Nishiyama, Yutaka; Tsuboi, Kazuaki

JAEA-Review 2010-019, 65 Pages, 2010/07

JAEA-Review-2010-019.pdf:7.25MB

JMTR secondary cooling system piping and a cooling tower were inspected from the view point of long term utilization before the renewal work for the secondary cooling system of the JMTR on FY 2008. As the result, it was confirmed that crack, swelling, and exfoliations in inner of piping lining, and decay and dryness of wood in the upper part of the cooling tower. From the result of this inspection some facilities and machinery were repaired or replaced from the view point of preventive maintenance.

JAEA Reports

Annual report for FY2008 on the activities of Department of Decommissioning and Waste Management (April 1, 2008 - March 31, 2009)

Department of Decommissioning and Waste Management

JAEA-Review 2010-020, 93 Pages, 2010/06

JAEA-Review-2010-020.pdf:3.78MB

This reports described the activities of Department of Decommissioning and Waste Management in Nuclear Science Research Institute in the period from April 1, 2008 to March 31, 2009. In this period, 519 m$$^{3}$$ of solid wastes and 314 m$$^{3}$$ of liquid wastes were treated. Then 2,391 waste packages were generated and total accumulated waste packages amounted to 136,971. Development of record keeping system for land burial and design of new management system for mid-level waste packages were conducted. Decommissioning plan for the JAEA's Reprocessing Test Facility (JRFT), the Ceramic Fuel Laboratory, the Plutonium Laboratory No.2, the Metallurgical Laboratory, Isotope Separation Laboratory and Reprocessing Test Laboratory were carried out. Studies were conducted on radiochemical analyses of wastes, JRFT decommissioning technologies and waste volume reduction. The method of nuclide measuring for the clearance was approved. And removing of liquid waste pipeline was started.

JAEA Reports

Survey on Emergency Action Levels in the United States of America

Kimura, Masanori; Watanabe, Norio; Homma, Toshimitsu

JAEA-Review 2010-021, 54 Pages, 2010/06

JAEA-Review-2010-021.pdf:1.01MB

International Atomic Energy Agency (IAEA) emphasizes the importance of emergency planning and requires the development of emergency response to implement effectively protective measures in IAEA Safety requirement GS-R-2. In the United States of America (USA), Nuclear Regulatory Commission (NRC) requires licensees, as a condition of licensing, the development of emergency planning including emergency classification and Emergency Action Levels (EALs) scheme. In order to consider incorporating emergency classification and EALs scheme into emergency preparedness and response in Japan, we surveyed the EALs scheme in the USA. This report provides the outline of EALs guideline, NEI99-01 "Methodology for Development of Emergency Action Levels", developed by Nuclear Energy Institute (NEI) and the brief descriptions on 8 accidents where an emergency was declared in the USA. As well, the findings from the survey are summarized.

JAEA Reports

Study on radiological protective actions in the long-term exposure situation

Takahara, Shogo; Kimura, Masanori; Homma, Toshimitsu

JAEA-Review 2010-022, 87 Pages, 2010/06

JAEA-Review-2010-022.pdf:1.34MB

The long-term exposure situations in case of nuclear emergencies are caused by the controllable and non-regulated radiation sources. The protective systems which are recommended by the 1990 recommendation of ICRP do not consider such radiation exposure situations. In order to investigate the response frameworks for the long-term exposure situation, we have summarized the 2007 recommendation and investigate the lessons learned from Chernobyl accident. The long-term exposure situation can not describe and response using general method. A decision making related to the protective actions in the long-term exposure situation can not be always justified in terms of scientific and quantitative basis. One of the methods to justify the decision making in the long-term exposure situation is procedural approach such as stakeholder participation.

JAEA Reports

Information exchange on HTGR and nuclear hydrogen technology between JAEA and INET in 2009

Fujimoto, Nozomu; Wang, H.*

JAEA-Review 2010-023, 11 Pages, 2010/07

JAEA-Review-2010-023.pdf:1.68MB

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 2009.

JAEA Reports

Annual report of Nuclear Science Research Institute, JFY2008

Nuclear Science Research Institute

JAEA-Review 2010-024, 125 Pages, 2011/01

JAEA-Review-2010-024.pdf:3.72MB

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 2008 summarizes the activities of NSRI, the R&D activities of the Research and Development Directorates and human resources development at site, and is expected to be referred to and utilized by R&D departments and project promotion sectors at NSRI site for the enhancement of their own research and management activities to attain their goals according to "Middle-term Plan" successfully and effectively.

JAEA Reports

Activities of Research-Reactor-Technology Project in FNCA from FY2005 to FY2007; Sharing neutronics calculation technique for core management and utilization of research reactors

Research-Reactor-Technology Project Group, Forum for Nuclear Cooperation in Asia (FNCA)

JAEA-Review 2010-025, 197 Pages, 2010/07

JAEA-Review-2010-025.pdf:4.65MB

RRT project (Research-Reactor-Technology Project) was carried out with the theme of "sharing neutronics calculation technique for core management and utilization of research reactors" in the framework of FNCA (Forum for Nuclear Cooperation in Asia) from FY2005 to FY2007. The objective of the project was to improve and equalize the level of neutronics calculation technique for the reactor core management among participating countries to assure the safe and stable operation of research reactors and the promotion of the effective utilization. SRAC code system and MVP code were adopted as common codes. Participating countries succeeded in applying the common codes to analyzing the core of each domestic research reactor. Some participating countries succeeded in applying the common codes to analyzing for utilization of own research reactors. Activities of RRT project have improved and equalized the level of neutronics calculation technique among participating countries.

JAEA Reports

The Production of the messages for risk communication by collaborating with local residents

Yonezawa, Rika; Ayame, Junko

JAEA-Review 2010-026, 150 Pages, 2010/08

JAEA-Review-2010-026.pdf:20.47MB

We produced the messages for risk communication by working in conjunction with local residents. The purpose of this activity is to make the messages easier for the local residents to understand. The messages were created from the viewpoint of the residents by working in close collaboration with us. As a result of those collaborations, we were able to produce several messages about radiation, environmental monitoring and the nuclear fuel cycle. This report includes all produced messages and evaluates the effects of the activities. Future development of our activities is also described.

JAEA Reports

Proceedings of the Workshop on "Possible Scientific View from New Neutron Spectroscopy Opportunities in J-PARC"; 8-9 July 2009, Ibaraki Quantum Beam Research Center, Multi-Purpose Hall, Tokai Plaza Caf$'e$, Tokai, Ibaraki, Japan

Nakajima, Kenji; Shibata, Kaoru; Kajimoto, Ryoichi

JAEA-Review 2010-027, 140 Pages, 2010/08

JAEA-Review-2010-027.pdf:22.01MB

At Materials and Life Science Facility (MLF) at J-PARC, three chopper spectrometers, AMATERAS, 4SEASONS and HRC have been constructed and a near-backscattering spectrometer, DNA is under construction. By combination of a high intensity neutron source at MLF and advanced technologies equipped, these spectrometers are expected to open new possibilities in scientific research using neutron inelastic and quasi-elastic scattering methods. In such circumstances, the workshop entitled "Possible Scientific View from New Neutron Spectroscopy Opportunities in J-PARC" was held on 8-9, July 2009 at Ibaraki Quantum Beam Research Center. The purpose of the workshop is to discuss the recent hot research topics and possible investigations utilizing the novel spectrometers at MLF in the wide range of the research field. This report includes abstracts and materials of the presentations in the workshop.

JAEA Reports

Review of technical basis for formulating performance goals for nuclear fuel facilities

Subcommittee of Research on Performance Goals for Nuclear Fuel Facilities

JAEA-Review 2010-028, 52 Pages, 2010/10

JAEA-Review-2010-028.pdf:1.57MB

A lot of efforts have been made recently for researches on development of PSA methodology, its applications, and trials of risk-informed operation and maintenance in nuclear fuel facilities in Japan. Quantitative performance criteria consistent with nuclear safety goals, which is essential for risk-informed decision making, however, have not been discussed yet for those nuclear installations. A subcommittee under the Nuclear Safety Research Committee has been organized by Nuclear Safety Research Center of Japan Atomic Energy Agency to prepare the technical basis and a typical procedure to derive the quantitative performance goals for further discussions by the regulatory bodies to establish the objectives. The activities in 2008 and 2009 fiscal year have been summarized and the procedure to formulate performance goals is proposed in this report carried out by the subcommittee of research on performance goals for nuclear fuel facilities.

JAEA Reports

Mizunami Underground Research Laboratory Project Plan for fiscal year 2010

Takeuchi, Shinji; Kunimaru, Takanori; Mikake, Shinichiro; Nishio, Kazuhisa; Tsuruta, Tadahiko; Matsuoka, Toshiyuki; Hayano, Akira; Takeuchi, Ryuji; Saegusa, Hiromitsu; Oyama, Takuya; et al.

JAEA-Review 2010-029, 28 Pages, 2010/08

JAEA-Review-2010-029.pdf:3.43MB

Japan Atomic Energy Agency (JAEA) at Tono Geoscience Center (TGC) is pursuing a geoscientific research and development project namely the Mizunami Underground Research Laboratory (MIU) project in crystalline rock environment in order to construct scientific and technological basis for geological disposal of High-level Radioactive Waste (HLW). Geoscientific research and the MIU project is planned in three overlapping phases; Surface-based investigation phase (Phase1), Construction phase (Phase2) and Operation phase (Phase3). The project is currently under the construction phase, and the operation phase starts in 2010. This document introduces the research and development activities planned for 2010 fiscal year plan based on the MIU master plan updated in 2010, (1) Investigation plan, (2) Construction plan, (3) Research collaboration plan, etc.

JAEA Reports

Research on geosphere stability for long-term isolation of radioactive waste; Scientific programme for fiscal years 2010-2014

Umeda, Koji; Ishimaru, Tsuneari; Yasue, Kenichi; Asamori, Koichi; Yamada, Kunimi; Kokubu, Yoko; Hanamuro, Takahiro; Tanikawa, Shinichi; Kusano, Tomohiro

JAEA-Review 2010-030, 48 Pages, 2010/09

JAEA-Review-2010-030.pdf:1.42MB

The concept of geological disposal of HLW in Japan is based on a multibarrier system which combines a stable geological environment with an engineered barrier system. Potential geological host formations and their surroundings are chosen, in particular, for their long-term stability, taking into account the fact that Japan is located in a tectonically active zone. This report is to outline 5 years plan (fiscal years 2010-2014) of research and development (R&D) for geosphere stability for long-term isolation of the high-level radioactive waste in JAEA. Background of this research are clarified with the necessity and the significance, and the past progresses in this report. The objectives, outline, contents and schedule during the next 5 years are described in detail. In addition, the plan framework is structured into the following categories: (1) Development and systematization of investigation techniques, (2) Development of models for long-term estimation and effective assessment, (3) Development of dating techniques.

JAEA Reports

Champion comparison of prestigious nuclear research institutes by thirty-year research papers written in nuclear advanced countries

Yanagisawa, Kazuaki

JAEA-Review 2010-031, 43 Pages, 2010/08

JAEA-Review-2010-031.pdf:0.94MB

A champion of research paper at JAERI and those of foreign prestigious nuclear research institutes was studied taking the timeframe as long as 30 years (1978-2007) Tools were INIS, ECD, WOS and SCOPUS. (1) INIS judged that JAERI (32,859 papers) was the champion. ECD judged that the ORNL (36,608 papers) was the champion. WOS coincided with that of ECD. SCOPUS judged that ORNL (32,728 papers) was the champion. (2) Different characteristics exhibited by individual databases can sometimes generate conflicting bibliometric results. This was true among INIS, ECD, WOS and SCOPUS when looking at trends between 5-year periods. It implies that results from analytical tools used in bibliometric studies should be viewed with careful consideration to learn of any influencing factors. (3) Users from developed and developing countries assigned as the Member State IAEA would be better served using INIS and ECD. As the recent trend, the use of WOS and SCOPUS has tended to grow worldwide.

JAEA Reports

Revaluation of $$^{99}$$Mo production by (n,$$gamma$$) method at HANARO

Jun, B. J.; Lee, B. C.*; Kimura, Akihiro; Hori, Naohiko; Izumo, Hironobu; Tsuchiya, Kunihiko

JAEA-Review 2010-032, 26 Pages, 2010/07

JAEA-Review-2010-032.pdf:2.52MB

After the feasibility study on $$^{99}$$Mo production by (n,$$gamma$$) method at HANARO was published by a KAERI report, worldwide supply of $$^{99}$$Mo became worse and a need for early available alternative $$^{99}$$Mo became stronger. Previous study indicated that the (n,$$gamma$$)$$^{99}$$Mo has a potential to be an alternative mass $$^{99}$$Mo available earlier than those by any other methods. It can be realized when radioisotope industry of each country accepts the use of (n,$$gamma$$)$$^{99}$$Mo for a meaningful portion of national demand. A good backup supply system among high flux reactors in the region is a prerequisite to guarantee a stable and sufficient availability of the (n,$$gamma$$)$$^{99}$$Mo for the region, for which active collaboration among reactors is essential. As the initial stage of collaboration between HANARO and JMTR for the (n,$$gamma$$)$$^{99}$$Mo supply, the specific experience and $$^{99}$$Mo production capability in HANARO have been discussed and revisited on the base of the previous report.

JAEA Reports

In-core integrity of the 4.8gU/cc silicide fuels fabricated by B&W and CERCA

Yanagisawa, Kazuaki

JAEA-Review 2010-033, 26 Pages, 2010/09

JAEA-Review-2010-033.pdf:4.31MB

The silicide fuel fabricated by B&W (one TC) and that fabricated by CERCA (no TC) was pulsed with the reactivity of 1.43 dollar ($). The energy deposition was 115 cal per gram for the former and 98 cal per gram for the latter. In core transient fuel performance of the two was directly compared, using the data obtained from 4.8g/cc silicide fuels as the references. (1) The onset of DNB temperature for the B&W fuel was 154 $$^{circ}$$C, which was the lowest among the references. (2) During the quenching, the B&W fuel had 269 $$^{circ}$$C for the temperature difference (94 $$^{circ}$$C for failure) and 0.079s for the time to quench (0.13s for failure). This situation brought the quench failure to the fuel. The failure mode was the through plate cracking. The CERCA fuel did not fail not telling the details due to the no in-core instrument.

JAEA Reports

Research plan on geosphere stability for long-term isolation of radioactive waste; Scientific programme for fiscal years 2010

Yasue, Kenichi; Asamori, Koichi; Yamada, Kunimi; Kokubu, Yoko; Yamasaki, Seiko; Kurosawa, Hideki; Tanikawa, Shinichi; Negi, Tateyuki; Kusano, Tomohiro; Hanamuro, Takahiro; et al.

JAEA-Review 2010-034, 42 Pages, 2010/09

JAEA-Review-2010-034.pdf:1.15MB

The concept of geological disposal of HLW in Japan is based on a multibarrier system which combines a stable geological environment with an engineered barrier system. Potential geological host formations and their surroundings are chosen, in particular, for their long-term stability, taking into account the fact that Japan is located in a tectonically active zone. This report is a plan of research and development (R&D) for geosphere stability for long-term isolation of HLW in JAEA, in fiscal year 2010. The objectives and contents in fiscal year 2010 are described in detail based on the outline of 5 years plan (fiscal years 2010-2014). In addition, the plan framework is structured into the following categories: (1) Development and systematization of investigation techniques, (2) Development of models for long-term estimation and effective assessment, (3) Development of dating techniques.

JAEA Reports

Brief report of the JAEA cooperative research (A) on the nuclear fuel cycle for 2009

Research Cooperation Section

JAEA-Review 2010-035, 185 Pages, 2010/08

JAEA-Review-2010-035-01.pdf:50.05MB
JAEA-Review-2010-035-02.pdf:34.4MB

This report includes a summary of the results of the research carried out in fiscal year 2009 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; eleven of which ended in 2009.

JAEA Reports

Experience of secondary cooling system modification at prototype fast breeder reactor MONJU (Translated document)

Kisohara, Naoyuki; Sakamoto, Yoshihiko

JAEA-Review 2010-036, 26 Pages, 2010/09

JAEA-Review-2010-036.pdf:3.05MB

The prototype fast breeder reactor MONJU has been shut down since the secondary sodium leak accident that occurred in December 1995. After the accident, an investigation into the cause and a comprehensive safety review of the plant were conducted, and various countermeasures for sodium leak were examined. Modification work commenced in September 2005. Since sodium is used as coolant in MONJU, the modification work required work methods suitable for the handling of sodium. From this perspective, the use of a plastic bag when opening the sodium boundary, oxygen concentration control in a plastic bag, slightly-positive pressure control of cover gas in the systems, pressing and cutting with a roller cutter to prevent the incorporation of metal fillings, etc. were adopted. Owing to these work methods, the modification work proceeded close to schedule without incident.

JAEA Reports

Annual report of Nuclear Emergency Assistance and Training Center (April 1, 2009 - March 31, 2010)

Kanamori, Masashi; Shirakawa, Yusuke; Yamashita, Toshiyuki; Okuno, Hiroshi; Terunuma, Hiroshi; Ikeda, Takeshi; Sato, Sohei; Terakado, Naoya; Nagakura, Tomohiro; Fukumoto, Masahiro; et al.

JAEA-Review 2010-037, 60 Pages, 2010/09

JAEA-Review-2010-037.pdf:3.11MB

When a nuclear emergency occurs in Japan, the Japan Atomic Energy Agency (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 national government and municipal office. NEAT provide various lectures and training course concerning nuclear disaster prevention for those personnel taking an active part in emergency response organizations at normal time. And NEAT researches on nuclear disaster prevention and also cooperate with international organizations. This annual report summarized the activities of JAEA/NEAT in the fiscal year 2009.

JAEA Reports

Decommissioning five facilities in Nuclear Science Research Institute

Terunuma, Akihiro; Naito, Akira; Nemoto, Koichi; Usami, Jun; Tomii, Hiroyuki; Shiraishi, Kunio; Ito, Shinichi

JAEA-Review 2010-038, 96 Pages, 2010/09

JAEA-Review-2010-038.pdf:5.9MB

Japan Atomic Energy Agency (JAEA) has midterm plan for decommissioning the facilities being finished their role and the facilities that became unnecessary by shifting their functions to other facilities. In the first midterm plan (from the latter half of fiscal year 2005 to fiscal year 2009), decommissioning of five facilities (Ceramic Research Facility, Plutonium Research Facility No.2, Metallurgy Research Facility, Isotope Separation Research Facility and Reprocessing Test Facility) had been carried out in order to release controlled area and dismantle the facilities in Nuclear Science Research Institute (NSRI), JAEA. The decommissioning activity for each facility had been reported to the regulatory body and municipalities. On this report, we summarize the each activity for five facilities by reviewing the reports to the regulatory body and municipalities. We also added the knowledge obtained through the activity.

JAEA Reports

Horonobe Underground Research Laboratory Project; Investigation report for the 2009 fiscal year

Nakayama, Masashi; Sano, Michiaki; Sanada, Hiroyuki; Sugita, Yutaka

JAEA-Review 2010-039, 67 Pages, 2010/10

JAEA-Review-2010-039.pdf:18.17MB

The Horonobe Underground Research Laboratory Project is planned to extend over a period 20 years. The investigations will be conducted in three phases, namely "Phase 1: Surface-based investigations", "Phase 2: Construction Phase" (investigations during construction of the underground facilities) and "Phase 3: Operation phase" (research in the underground facilities). This report summarizes the results of the investigations for the 2009 fiscal year (2009/2010). The investigations, which are composed of "Geoscientific research" and "R&D on geological disposal technology", were carried out according to "Horonobe Underground Research Laboratory Project Investigation Program for the 2009 Fiscal year". The results of these investigations, along with the results which were obtained in other departments of Japan Atomic Energy Agency (JAEA), are properly offered to the implementations and the safety regulations. For the sake of this, JAEA has proceeded with the project in collaboration with experts from domestic and overseas research organisations.

JAEA Reports

Review and analysis of Japan's efforts to ensure nuclear non-proliferation; Significant elements in terms of winning trust for the peaceful nature of the nuclear energy use and future challenges

Yamamura, Tsukasa; Matsushima, Hideya; Otsuka, Naoto*; Tazaki, Makiko; Mizuma, Hideki*; Kadota, Koshu*; Kimoto, Toru

JAEA-Review 2010-040, 180 Pages, 2010/09

JAEA-Review-2010-040.pdf:4.84MB

Japan initiated a program of peaceful use of nuclear energy in 1950s. Since that time, Japan has made it clear that the program is carried out strictly for peaceful purposes in a transparent manner, implementing measures to win trust from international community. In this report, we review, analyze and evaluate Japan's efforts to ensure nuclear non-proliferation, deviding them into seven categories. Through such review, analysis and evaluation, the significant elements in terms of wining the trust for the peaceful nature of the nuclear energy use and future challenges have been identified for each category stated above. We expect this report to contribute to the discussion on the policy of peaceful use of nuclear energy and nuclear non-proliferation within the Atomic Energy Commission of Japan and to be any use for the states which plan to initiate nuclear energy use program on a significant scale including the deployment of nuclear power plants.

JAEA Reports

Horonobe Underground Research Laboratory Project; Investigation program for the 2010 fiscal year

Nakayama, Masashi; Sanada, Hiroyuki; Sano, Michiaki; Sugita, Yutaka

JAEA-Review 2010-041, 26 Pages, 2010/10

JAEA-Review-2010-041.pdf:3.2MB

As part of the research and development program on geological disposal of high-level radioactive waste (HLW), the Horonobe Underground Research Center, a division of the JAEA is implementing the Horonobe URL Project with the aim at investigating sedimentary rock formations. According to the research plan described in the Midterm Plan of JAEA, geological investigations are to be carried out during the drilling of a shaft down to around 350 m depth, while research and development in the areas of engineering technology and safety assessment are to be promoted by collaboration with other research organizations. The results of the R&D activities will be systematized as a "knowledge base" that supports a wide range of arguments related to the safety of geological disposal. The Horonobe URL Project is planned to extend over a period of 20 years. The investigations will be conducted in three phases, namely "Phase 1: Surface-based investigations", "Phase 2: Construction phase" (investigations during construction of the underground facilities) and "Phase 3: Operation phase" (research in the underground facilities). This report summarizes the investigation program for the 2010 fiscal year (2010/2011). In the 2010 fiscal year, investigations in "geoscientific research", including "development of techniques for investigating the geological environment", "development of techniques for long-term monitoring of the geological environment", "development of engineering techniques for use in the deep underground environment" and "studies on the long-term stability of the geological environment", are continuously carried out. Investigations in "research and development on geological disposal technology", including "improving the reliability of disposal technologies" and "enhancement of safety assessment methodologies", are also continuously carried out. Construction of the underground facilities is ongoing at Access Shaft (East) and 250 m depth drift.

JAEA Reports

Report on the cooperating researches utilizing fusion engineering facilities completed in the fiscal year 2009 (Joint research)

Division of Fusion Energy Technology

JAEA-Review 2010-042, 64 Pages, 2010/10

JAEA-Review-2010-042.pdf:14.2MB

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 six fusion engineering facilities; Caisson Assembly for Tritium Safety Study (CATS), Fusion Neutronics Source (FNS), JAEA Electron Beam Irradiation System (JEBIS), RF Test Stand (RFTS), MeV Test Facility (MTF) and Divertor Acceptance Test Stand (DATS). In the fiscal year 2009 (from April 1, 2009 to March 31, 2010), 20 activities were carried out as the cooperating researches. This report reviews the results of 5 activities completed in the fiscal year 2009.

JAEA Reports

Review on technical evaluation of aging of JMTR reactor facility

Ide, Hiroshi; Tobita, Kenji; Endo, Yasuichi; Hori, Naohiko

JAEA-Review 2010-043, 80 Pages, 2010/10

JAEA-Review-2010-043.pdf:34.97MB

"Regulations Concerning the Installment, Operation, etc. of Research Reactors" was revised in February 2004. Based on the regulations, the reactor owner must perform the technical evaluation on aging if reactor operation is over 30 years. Moreover, based on the evaluation, the reactor owner must make the 10 years maintenance program concerning the action to maintain the reactor facility. Result of the technical evaluation on aging and the maintenance plan of JMTR reactor facility were reported to the MEXT in March 2005. In response to the report, the advisor meeting was held by the MEXT to evaluate the result of technical evaluation on aging and the maintenance plan. Corresponding to the meeting, we reviewed the technical evaluation result on aging and the maintenance program of JMTR reactor facility. This report summarized the review on the technical evaluation of aging of JMTR reactor facility and so on corresponding to the advisor meeting.

JAEA Reports

Horonobe Underground Research Laboratory Project; Investigation program for the 2008 fiscal year (Translated document)

Nakayama, Masashi; Sanada, Hiroyuki; Yamaguchi, Takehiro*; Sugita, Yutaka

JAEA-Review 2010-044, 39 Pages, 2010/11

JAEA-Review-2010-044.pdf:6.68MB

The Horonobe URL Project is planned to extend over a period of 20 years. The investigations will be conducted in three phases, namely "Phase 1: Surface-based investigations", "Phase 2: Construction phase" (investigations during construction of the underground facilities) and "Phase 3: Operation phase" (research in the underground facilities). This report summarizes the investigation program for the 2008 fiscal year (2008/2009), the 4th year of the Phase 2 investigations.

JAEA Reports

Present status of technology development on decommissioning and waste management in Nuclear Cycle Backend Directorate; Progress in 2009

Editorial Committee of R&D Results

JAEA-Review 2010-045, 82 Pages, 2010/11

JAEA-Review-2010-045.pdf:2.52MB

It is an important issue to take measures against the matters on decommissioning of retired nuclear facilities and management of low-level radioactive wastes, 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 taking account of these matters. The technology development items are selected from the viewpoints of systematic implementation of measures; these include the development of computer systems for planning and evaluation of decommissioning programs, supercritical CO$$_{2}$$ fluid leaching method for decontamination, nitrate-ion degradation method, simple and rapid determination method for radioactivity, safety assessment for waste disposal and so on. This report describes outline and progress of the technology development program conducted in FY2009 by the research and development unit.

JAEA Reports

Development of measuring instruments for material irradiation tests

Kitagishi, Shigeru; Tanimoto, Masataka; Iimura, Koichi; Inoue, Shuichi; Saito, Takashi; Omi, Masao; Tsuchiya, Kunihiko

JAEA-Review 2010-046, 19 Pages, 2010/11

JAEA-Review-2010-046.pdf:2.51MB

The Japan Materials Testing Reactor (JMTR) has been utilized for the various neutron irradiation tests of fuels and materials, as well as for radioisotope production since achieving the first criticality in March 1968. The operation of JMTR was halted for the refurbishment in August 2006. The new JMTR is expected to contribute to many fields: the lifetime extension of LWRs and the expansion of industry use. To meet a wide range of users' needs, the development of new irradiation technologies has been carried out for the new JMTR. This report summarizes the present conditions of the development of FP gas pressure gauges, multi-paired thermocouples, ECP and ceramics sensors.

JAEA Reports

Dismantlement technique of irradiation facilities in JMTR

Onuma, Yuichi; Okada, Yuji; Hanawa, Hiroshi; Tsuchiya, Kunihiko; Kanno, Masaru

JAEA-Review 2010-047, 27 Pages, 2010/11

JAEA-Review-2010-047.pdf:3.0MB

The Japan Materials Testing Reactor (JMTR) has been refurbished to re-operate from 2011. As a part of the establishment of new irradiation facilities, technology development for the dismantling and removing of irradiation facilities such as OWL-1 (Oarai Water Loop No.1), OWL-2 (Oarai Water Loop No.2) and IASCC (Irradiation Assisted Stress Corrosion Cracking) facility installed in the JMTR loop cubicles has been performed. By using developed methods, techniques for the dismantling and removing of the irradiation facilities were established.

JAEA Reports

Document collection of 2009 Debriefing Session for Nuclear Cycle Backend Operation

Planning Committee of the 2009 Debriefing Session or Nuclear Cycle Backend Operation

JAEA-Review 2010-048, 140 Pages, 2010/11

JAEA-Review-2010-048.pdf:20.95MB

The Debriefing Session for Backend Operation was held by Backend Technology Development Unit of Nuclear Cycle Backend Directorate. The objective is information exchange about current state of technological development in nuclear cycle backend field. In this debriefing session, 15 announcements were made in three sessions, that is, radioactive waste characterization technology, radioactive waste treatment and disposal technology, and decommissioning technology. After debriefing session, poster round-table discussion was held and significant discussion was generated. The debriefing session participants were 82 people in total, and poster round-table discussion participants were 35 people. The present report compiles abstracts and presentation materials submitted by the speakers.

JAEA Reports

Nondestructive testing by three-dimensional X-ray radiography

Yonekawa, Minoru; Sozawa, Shizuo; Kato, Yoshiaki; Shibata, Akira; Nakagawa, Tetsuya; Kusunoki, Tsuyoshi

JAEA-Review 2010-049, 18 Pages, 2010/11

JAEA-Review-2010-049.pdf:2.09MB

The hot laboratory (JMTR-HL) was founded to examine the objects mainly irradiated in the JMTR (Japan Materials Testing Reactor), and has been operated since 1971. The JMTR has been stopped from FY2006 for the refurbishment and will be re-started from FY2011. The post irradiation examination for high burn up fuels and large specimen will be carried out in the restarted JMTR. The JMTR-HL plans to put a three dimensional X-ray Computerized Tomography (CT) inspection system in place until the restart of JMTR in order to satisfy the requirement of valuable irradiation data for safety and plant life time management of nuclear power plants in the future. The three dimensional X-ray CT inspection system is able to observe a defect geometry closely and visually compared with a two dimensional system. In this paper, system design, production, installation and performance tests of an X-ray CT inspection system in a hot cell are reported. The X-ray CT inspection system consists of a computed tomography scanner, an X-ray source, a movable sample positioned, an X-ray detector, a collimator, and so on. After installation of apparatus, performance tests using irradiated fuel rods and radioisotopes were carried out to confirm the influence of $$gamma$$ rays and transmission X-ray property. By this development of the X-ray CT inspection system, it became possible to provide data with high technical value for post irradiation examination of high burn-up fuels and large type specimens.

JAEA Reports

Proceedings of ACROSS Workshop on "Current state of ACROSS technology and view in the future"

Asai, Hideaki; Hasegawa, Ken

JAEA-Review 2010-050, 222 Pages, 2010/11

JAEA-Review-2010-050.pdf:25.5MB

ACROSS (Accurately Controlled Routinely Operated Signal System) has developed to acquire the detailed information on the tectonically active zone. We considered the ACROSS technology may apply to the engineering technology of the MIU project, for example monitoring of the change of the geological environment around shafts and also the strength of the shaft concrete itself. It was planned that the examination for three years will be made from fiscal year 2007. We held ACROSS Workshop "Current state of ACROSS technology and view in the future" on February 24 and 25, 2010 at Mizunami. The purpose of the ACROSS Workshop was to introduce our current result of the ACROSS research, to introduce the research of the ACROSS technology to external specialists, and to discuss the view of the ACROSS technology in the future. This report is collection of the documents used in the ACROSS Workshop.

JAEA Reports

The International Nuclear Information System; The First forty years 1970-2010 (Translated document)

Itabashi, Keizo

JAEA-Review 2010-051, 149 Pages, 2010/10

JAEA-Review-2010-051.pdf:1.35MB

The Statute of the IAEA that came into force in July 1957. It was with the desire to more adequately fulfill the statutory function that during the 1960's the Agency began exploring the possibility of establishing a scheme that would provide computerized access to a comprehensive collection of references to the world's nuclear literature. The outcome of these efforts was the establishment of the International Nuclear Information System (INIS) and produced its first products in May 1970. The system was designed as an international cooperative venture. It started operations with 25 members and the present membership is 146. The report describes the road that led to the creation of INIS. It also describes the present operation of the system, the current methods used to collect and process the data on nuclear literature and the various products and services that the system places at the disposal of its users. Furthermore, it gives insights into current thinking for future developments.

JAEA Reports

Annual report of JMTR FY2009

Department of JMTR Operation

JAEA-Review 2010-052, 34 Pages, 2010/11

JAEA-Review-2010-052.pdf:1.84MB

JMTR has been stopped since its 165th cycle operation was finished, and the JMTR is advancing its refurbishment works aiming at the restart from FY2011. Regarding the management and operation of the JMTR, the periodical inspection of facilities based on the law, maintenance and partial renewal works of facilities and the transportation of the spent fuels to U.S were carried out, and the fabrication of the fuel for restart has been started. As for the management and operation of irradiation facilities, maintenance and partial renewal works of facilities were also carried out. In the hot laboratory, post-irradiation examinations of irradiated materials and fuels were carried out. As for the radiation control at the JMTR facility, irradiation facility and hot laboratory facility, the limit of the radiation exposure dose defined by the safety regulation works were carried out safely under far below. This report describes the FY2009 activities relating to above mentions.

JAEA Reports

Development of $$^{rm 99m}$$Tc extraction techniques from $$^{99}$$Mo by (n,$$gamma$$) reaction

Kimura, Akihiro; Hori, Naohiko; Tsuchiya, Kunihiko; Ishihara, Masahiro; Yamabayashi, Hisamichi*; Tanase, Masakazu*; Fujisaki, Saburo*; Sato, Yuichi*

JAEA-Review 2010-053, 23 Pages, 2010/11

JAEA-Review-2010-053.pdf:2.52MB

Production techniques of $$^{99}$$Mo, parent nuclide of $$^{rm 99m}$$Tc, have been developed for the industrial utilization as medical diagnosis medicine after the JMTR refurbishment. The (n,$$gamma$$) method is proposed in JMTR because of low-amount radioactive wastes and easy $$^{rm 99m}$$Tc production process. In this study, the production of the high-density MoO$$_{3}$$ pellet and concentration techniques of $$^{rm 99m}$$Tc solution were developed. As the trial test, the MoO$$_{3}$$ pellets with high density were produced by the SPS (Spark Plasma Sintering) method. On the other hands, it was possible to concentrate $$^{rm 99m}$$Tc solution by the solvent extraction using Methyl Ethyl Ketone (MEK). From the result, the $$^{rm 99m}$$Tc concentrating device with more than 80% concentration efficiency, was performed successfully.

JAEA Reports

Failure mechanism of Nb$$_{2}$$O$$_{5}$$ doped PWR fuels under power transient

Yanagisawa, Kazuaki

JAEA-Review 2010-054, 109 Pages, 2010/11

JAEA-Review-2010-054.pdf:36.09MB

(1) The niobia doped PWR fuel (test specimen) did not fail below 260 cal/g defined as the failure threshold for RIA. (2) The fuel failure occurred by the cladding melt-brittle mechanism irrespective to the doping. (3) The test specimen caused a significant axial PCMI to the magnitude of 18%. (4)Above 276 cal/g, the test specimen restructured and formed the bonding, the small radial cracks, the metallic agglomeration and inclusion at the very narrow ring area. The grain size of the test specimen at the ring was reduced from original 31 to 10-21 microns. Meanwhile, undoped fuel grew the grain size from original 9 to 60 microns at the similar ring because of the recrystallization.

JAEA Reports

Operation, test, research and development of the High Temperature Engineering Test Reactor (HTTR) (FY2009)

Department of HTTR

JAEA-Review 2010-055, 114 Pages, 2010/11

JAEA-Review-2010-055.pdf:7.19MB

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 2009, the HTTR carried out 50 days operation with high temperature test operation mode. In the operation, many kinds of data such as core burnup characteristics, helium purification performance, performance of high temperature components, data related to integrity of core components, etc. have been accumulated. Moreover, it is demonstrated that HTGRs could be utilized as a heat source for thermo-chemical hydrogen production system. This report summarizes activities and results of HTTR operation, maintenance, and several R&Ds, which were carried out in the fiscal year 2009.

JAEA Reports

JAEA-Tokai tandem annual report 2009; April 1, 2009 - March 31, 2010

Department of Research Reactor and Tandem Accelerator

JAEA-Review 2010-056, 163 Pages, 2010/12

JAEA-Review-2010-056.pdf:4.92MB

The JAEA-Tokai tandem accelerator complex has been used in various research fields such as nuclear science and material science by researchers not only of JAEA but also from universities, research institutes and industrial companies. This annual report covers development and research activities carried out using the tandem accelerator, superconducting booster and radioactive ion beam accelerator, from April 1, 2009 to March 31, 2010. Fifty-seven summary reports were categorized into seven research/development fields:(1)accelerator operation and development, (2) nuclear structure, (3) nuclear reaction, (4) nuclear chemistry, (5) nuclear theory, (6) atomic physics and solid state physics, (7) radiation effect in materials. This report also lists publications, meetings, committee members, cooperative researches and common use programs.

JAEA Reports

Proceedings of the 4th Seminar of R&D on Advanced ORIENT, Strategy and technical requirement for new resource of noble metals in advanced atomic energy science; Swany Hall, Rokkasho-Mura, on July 30th, 2010

Sasaki, Yuji; Koyama, Shinichi; Ozawa, Masaki

JAEA-Review 2010-057, 124 Pages, 2010/12

JAEA-Review-2010-057.pdf:38.56MB

The 4th Seminar of R&D on advanced ORIENT, Strategy and technical requirement for new resource of noble metals in advanced atomic energy science, was held in Swany hall, Rokkasho-Mura, on July 30th, 2010 organized by Japan Atomic Energy Agency. Spent nuclear fuel should be recognized as 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. In this seminar, there are many poster presentation included, and the useful discussion with many students are performed.

JAEA Reports

Summaries of research and development activities by using JAEA computer system in FY2009 (April 1, 2009 - March 31, 2010)

Information Technology Systems' Management and Operating Office

JAEA-Review 2010-058, 209 Pages, 2010/11

JAEA-Review-2010-058.pdf:19.12MB

Center for Computational Science & e-Systems (CCSE) of Japan Atomic Energy Agency (JAEA) installed large computer systems including super-computers in order to support research and development activities in JAEA. This report presents usage records of the JAEA computer system and the big users' research and development activities by using the computer system in FY2009 (April 1, 2009 - March 31, 2010).

JAEA Reports

Investigation on integrity of heat exchanger and tanks in primary cooling system of JMTR

Onoue, Ryuji; Ebisawa, Hiroyuki; Fukasaku, Akitomi; Kusunoki, Tsuyoshi

JAEA-Review 2010-059, 19 Pages, 2010/12

JAEA-Review-2010-059.pdf:4.07MB

The JMTR is a light water moderated and cooled tank-type reactor. First criticality was achieved in March 1968. The refurbishment of JMTR is scheduled from the beginning of FY2007 to the end of FY2010. An investigation on aged components was carried out since the beginning of FY2007. In this paper, the aged-investigations for heat exchangers and tanks in the primary cooling system are presented. The integrity of three heat exchangers was confirmed by the eddy current testing for heat exchanger tubes, visual observation using endoscope, liquid penetration test of tube plates and thickness measurement of the main body. The visual inspection test and liquid penetration test were carried out to confirm the integrity of tanks in the primary cooling system. The heat exchangers and tanks in the primary cooling system will be continuously used in the future operation of the JMTR by appropriate maintenance activities based on the long-term maintenance program.

JAEA Reports

Methodology for comparative assessment of various electricity generation systems using health and environmental impacts as the indicators

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

JAEA-Review 2010-060, 73 Pages, 2010/12

JAEA-Review-2010-060.pdf:1.52MB

This report describes the procedure and the results of the comparative risk assessment which are implemented using the Impact Pathway Approach. This approach is known as a popular method and characterized as the methodology that considers the emissions from the emission sources, the dispersions of those pollutants, and then the impacts to the recipients of the pollutants. This approach was examined at the CRP of the IAEA. Upon the results of the assessments made by the CRP and the Extern E, it is concluded that the impacts of the fossil fuel chains are relatively larger than of the other fuel chains, especially when the secondary chemical transformation of the pollutants and the effects of global warming are considered. On the contrary, the impacts of nuclear fuel chains are smaller than of the fossil fuel chains'. We still needs for further studies on the risks of the severe accidents and on the impacts of long-lived radio-nuclides spreading on the global level.

JAEA Reports

Excavation of shafts and research galleries at the Mizunami Underground Research Laboratory (MIU); Construction progress report, fiscal year 2008

Geoscience Facility Construction Section, Tono Geoscience Center

JAEA-Review 2010-061, 156 Pages, 2011/01

JAEA-Review-2010-061-01.pdf:21.82MB
JAEA-Review-2010-061-02.pdf:48.81MB

This progress report presents an outline compilation of construction activities, primary tasks performed, construction progress and problems reported, in fiscal year 2008. The outline of construction activities is a summary based on the scope of work planned in 2008: the main activities are based on the Tono Geoscience Center weekly reports; and the construction progress is based on the planned and actual schedules and the Tono Geoscience Center weekly reports. The problems reported are based on accident reports, natural disasters, nonconformance and defects recording by the safety manager of the Geoscience Facility Construction Section. Regarding the plan and actual performance of MIU construction project No.3 (March 16, 2008 - March 15, 2010) performance carried out until March 31, 2009 is described in this report and rest of the performance started from April 1, 2009 is supposed to be described in construction progress report from fiscal year 2009 onward.

JAEA Reports

Annual report on the activities in Safety Administration Department; Report of the fiscal year 2009

Hayashi, Naomi

JAEA-Review 2010-062, 399 Pages, 2011/01

JAEA-Review-2010-062.pdf:18.79MB

The activities of Safety Administration Department covers many fields in Nuclear Fuel Cycle Engineering Laboratories such as the management of the occupational safety and health, the crisis management, the security, and the management of a quality assurance. This report is the summary of the activities of Safety Administration Department since April, 2009 until March, 2010.

JAEA Reports

Proposed plan for a JAEA Internationalization Initiative (JII) (Contract research)

Bolton, P.; Mizuki, Junichiro; Kawanishi, Shunichi

JAEA-Review 2010-063, 22 Pages, 2011/01

JAEA-Review-2010-063.pdf:0.95MB

Concepts for a JAEA Internationalization Initiative, JII are presented. Following a general discussion of issues and recommendations for JII, a "fast startup JII" is proposed in the form of fast start action items (FSAI). The FSAI represent a clear set of action items that can be implemented at the KPSI/PMRC site which would serve as a seed site for test and evaluation. A JAEA Internationalization Initiative that is guided by evaluation and tailored for JAEA as a whole can be established with appropriate oversight and tracking at each JAEA site by local JII teams. In addition to recommendations for the KPSI/PMRC seed site, the roles of the Quantum Beam Science Directorate (QuBS) leadership and the International Affairs Department (IAD) of JAEA are also discussed. Current KPSI/PMRC activities that are consistent with a JII are briefly presented.

JAEA Reports

The Capacity of fuel cycle facilities and its coherence in France; The Status of nuclear fuel cycle industry in France

Ojima, Hisao

JAEA-Review 2010-064, 27 Pages, 2011/01

JAEA-Review-2010-064.pdf:1.98MB

This report summarizes the feature of nuclear fuel cycle facilities, such as the process adopted or nominal capacity, in France, according to disclosed materials, basically. It was confirmed that the capacity of French facility is coherent well each other. Recycling aspect of chemical reagent used in the cycle, especially the fluorine, has been investigated, as well as nuclear materials. Based on the known plans about renewal of current facilities, a preliminary study on a possibility of step-up in production has been conducted. As facilities locate all over the land in France, the transportation of nuclear materials is an essential work. Focusing on the uranium and plutonium recovered in the reprocessing plant, the status and supposed subjects of their transportation are mentioned.

JAEA Reports

JAEA Takasaki annual report 2009

Tanaka, Shigeru

JAEA-Review 2010-065, 217 Pages, 2011/01

JAEA-Review-2010-065.pdf:15.99MB

JAEA Takasaki annual report 2009 describes research and development activities performed from April 1, 2009 to March 31, 2010 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 facility) 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 165 reports consisting of 157 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

Investigation on integrity of JMTR reactor building

Oto, Tsutomu; Kimura, Tadashi; Fukasaku, Akitomi; Kusunoki, Tsuyoshi

JAEA-Review 2010-066, 22 Pages, 2011/01

JAEA-Review-2010-066.pdf:3.94MB

The refurbishment of JMTR is scheduled from the beginning of FY 2007 to the end of FY 2010. An integrity investigation for concrete structures of the JMTR buildings was carried out in early phase of the refurbishment. This paper describes investigated results and repair work of the vent stack, trenches, canal building and the filter bank. Investigated items were the concrete surface deterioration, rebound number (nondestructive estimation of strength), comprehensive strength using drilled concrete core test piece, carbonation depth, reinforced bar corrosion and chloride ion content. The integrity of these concrete structures was confirmed by these investigations. Based on the investigation results, repair works such as re-painting were carried out from the viewpoint of preventive maintenance for the vent stack, trenches and canal building.

JAEA Reports

Environmental performance data in Environmental Report 2010

Environmental Management Section, Safety Administration Department

JAEA-Review 2010-067, 179 Pages, 2011/02

JAEA-Review-2010-067.pdf:7.57MB

In July, 2010 Japan Atomic Energy Agency published the Environmental Report 2010 concerning the activities of FY 2009 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 2009 as the base of the Environmental Report 2010. This report would not only ensure traceability of the data in order to enhance the reliability of the environmental report, but also make useful measures for promoting activities of environmental considerations in JAEA.

JAEA Reports

Study on in-core behavior of PWR fuel under power transient; Influence of waterside corrosion

Yanagisawa, Kazuaki

JAEA-Review 2010-068, 34 Pages, 2011/01

JAEA-Review-2010-068.pdf:9.37MB

(1)The waterside corrosion for the pressurized PWR fuel had no effect on the fuel failure occurred by the ballooned/rupture mechanism but that for the unpressurized PWR fuel had a significant effect to preventing the fuel from the failure occurred by the melt/brittle mechanism. The corroded film tended to minimize the temperature gradient across the cladding, to prevent the additional oxide formation and to reduce the hoop stress raised during the quench. As a result, the failure threshold of the corroded fuel was higher than that of the standard fuel. (2) The peak axial strain for the pressurized fuel increased with the increase of the oxide film, where the maximum was 4% for the 40 micron oxide film. However, the peak axial strain for the unpressurized fuel was within 1% irrespective to the oxide film thickness.

JAEA Reports

Proceedings of Information and Opinion Exchange Conference on Geoscientific Study, 2010

Nishio, Kazuhisa; Iyatomi, Yosuke; Shimada, Akiomi

JAEA-Review 2010-069, 131 Pages, 2011/02

JAEA-Review-2010-069-01.pdf:33.23MB
JAEA-Review-2010-069-02.pdf:27.08MB

Japan Atomic Energy Agency (JAEA) at Tono Geoscience Center (TGC) has been conducting a geoscientific studies in order to establish a scientific and technological basis for the geological disposal of HLW. Information and Opinion Exchange Conference on Geoscientific Study has been held by TGC annually. The conference provides technical information and an opportunity for peer review and exchange of opinions on the geoscientific studies conducted at TGC. Research specialists and engineers from Japanese universities, research organizations and private companies usually participate in the conference. This document compiles research presentations, posters of the conference at Mizunami on October 19th, 2010.

JAEA Reports

In-core behavior of silicide fuel; Power transient by abnormal control rod withdrawal and cold coolant induction

Yanagisawa, Kazuaki

JAEA-Review 2010-070, 18 Pages, 2011/01

JAEA-Review-2010-070.pdf:7.93MB

The safety study of the silicide fuel for the use in the Japan Materials Testing Reactor (JMTR) under the power transient was carried out. (1) It was revealed from the experimental tests that the peak cladding surface temperature (PCST) for the abnormal control rod withdrawal (ACRW) during the reactor start-up was 137$$^{circ}$$C and that for the cold coolant induction (CCI) at the secondary loop was 111$$^{circ}$$C. The values were higher than those of the EUREKA-2 code calculation used for the JMTR licensing. (2) The PCST of the two tests did not exceed the minimum DNBR and the fuel integrity of them was kept without causing any fuel damage. Consequently, experimental results cleared the judging criteria for safety of ACRW and CCI. These experimental facts lead that the predictions made by the code for ACRW and CCI is safe enough.

JAEA Reports

Reports of JAEA's Reimei Research Program; April 1, 2009 - March 31, 2010

Nagame, Yuichiro

JAEA-Review 2010-071, 47 Pages, 2011/02

JAEA-Review-2010-071.pdf:2.56MB

The summaries of the 8 research projects conducted through the Reimei Research Program are published for the growth and development of the new researches.

JAEA Reports

Annual report on the effluent control of low level liquid waste in Nuclear Fuel Cycle Engineering Laboratories FY2009

Sumiya, Shuichi; Matsuura, Kenichi; Watanabe, Hitoshi; Nakano, Masanao; Fujita, Hiroki; Kono, Takahiko; Hiyama, Yoshinori; Yoshii, Hideki*; Fujii, Jun*; Kikuchi, Masaaki*; et al.

JAEA-Review 2010-072, 115 Pages, 2011/02

JAEA-Review-2010-072.pdf:2.1MB

Based on the regulations (the safety regulation of Tokai reprocessing plant, the safety regulation of nuclear fuel material usage facilities, the radiation safety rule, the regulation about prevention from radiation hazards due to radioisotopes, which are related with the nuclear regulatory acts, and the local agreement concerning with safety and environment conservation around nuclear facilities, the water pollution control law, and byelaw of Ibaraki prefecture), this report describes the effluent control results of liquid waste discharged from the JAEA's Nuclear Fuel Cycle Engineering Laboratories in the fiscal year 2009, from 1st April 2009 to 31st March 2010. In this period, the concentrations and the quantities of the radioactivity in liquid waste discharged from the reprocessing plant, the plutonium fuel fabrication facilities, and the other facilities were much lower than the authorized limits of the above regulations.

JAEA Reports

CoolRep H22; Synthesis report on R&D results on geological disposal up to 2009

Umeki, Hiroyuki; Hioki, Kazumasa; Osawa, Hideaki; Fujita, Tomoo; Shibata, Masahiro; Makino, Hitoshi; Iwatsuki, Teruki; Takeuchi, Shinji; Ishimaru, Tsuneari

JAEA-Review 2010-073, 255 Pages, 2011/02

JAEA-Review-2010-073.pdf:4.19MB

The Japan Atomic Energy Agency (JAEA) has been performing research and development on geological disposal technology of high level radioactive waste. At the end of fiscal year 2009, the Geological Isolation Research and Development Directorate of JAEA made publicly available the "CoolRep H22", which is a web-based report that summarizes the R&D results, on its website. This document reports the contents of CoolRep H22.

JAEA Reports

Annual report for FY2009 on the activities of radiation safety in Nuclear Science Research Institute etc. (April 1, 2009 - March 31, 2010)

Department of Radiation Protection, Nuclear Science Research Institute; Safety Section, Department of Administrative Services, Takasaki Advanced Radiation Research Institut; Safety Section, Department of Administrative Services, Kansai Photon Science Institute; Operation Safety Administration Section, Mutsu Office, Aomori Research and Development Center; Safety Section, Department of Administrative Services, Naka Fusion Institute

JAEA-Review 2010-074, 168 Pages, 2011/01

JAEA-Review-2010-074.pdf:5.82MB

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

JAEA Reports

Study plan on biosphere assessment for geological disposal of radioactive waste; 5-year plan for fiscal years 2010-2014

Kato, Tomoko; Itazu, Toru; Suzuki, Yuji*

JAEA-Review 2010-075, 42 Pages, 2011/02

JAEA-Review-2010-075.pdf:4.11MB

As the biosphere assessment of geological disposal covers an extremely long time period, it is difficult to predict the future human environment and lifestyles. IAEA-TECDOC addresses that a stylized approach is proposed for selecting critical groups and biospheres in future situations where human behaviour or biosphere conditions cannot be known with any certainty, although it is possible to construct biosphere models based on the characteristics and evolution of the surface environment at the actual site in shorter time period. BIOMASS methodology is especially effective for treating uncertainty of biosphere in these situations. To address the approaches of biosphere modelling, time period after closure of repository was divided; period 0 to 100 years, 100 years to 10,000 years and beyond them. Critical issues of biosphere modelling were specified through summarising the past progresses in domestic and foreign institutes. Based on the critical issues specified, 5-year research plan on biosphere assessment were identified.

JAEA Reports

Annual report on operation and management of Hot Laboratories and Facilities; From April 1, 2009 to March 31, 2010

Department of Hot Laboratories and Facilities

JAEA-Review 2010-076, 96 Pages, 2011/03

JAEA-Review-2010-076.pdf:3.78MB

This is an annual report in a fiscal year 2009 that describes activities of RFEF, WASTEF, RHL and the other research hot facilities controlled by the Department of Hot Laboratories and Facilities. In RFEF, various PIEs were performed related to the Advanced LWR fuel Performance and Safety research program, and the development of vessel material for spallation target of neutron scattering facility. In WASTEF, The examination for the investigation of the IASCC of nuclear power plant materials, corrosion test for structural materials of nuclear plant under $$gamma$$ ray irradiation condition and the various examination of miner actinoid doped fuel. The several examinations were performed ordered from the safety research center in JAEA as the trustee agreement with JNES and NISA and from J-PARC the development program of vessel material for spallation target of neutron scattering facility. In RHL, To progress the decommissioning plan of fiscal year 2009, the decontamination of lead cells and dismantlement of incidental equipment and the review were performed about the basic vision and dismantling and decontamination procedure for release in the regulation of controlled area In addition, managements of the other research hot facilities were carried out.

JAEA Reports

Annual report of Department of Research Reactor and Tandem Accelerator, JFY2009; Operation, utilization and technical development of JRR-3, JRR-4, NSRR and Tandem Accelerator

Department of Research Reactor and Tandem Accelerator

JAEA-Review 2010-077, 201 Pages, 2011/06

JAEA-Review-2010-077.pdf:6.16MB

The Department of Research Reactors and Tandem Accelerator is in charge of the operation, utilization and technical development of JRR-3, JRR-4, NSRR and Tandem Accelerator. This annual report describes a summary of activities of services and technical developments carried out in the period between April 1, 2009 and March 31, 2010. The activities were categorized into five service/development fields: (1) Operation and maintenance of research reactors and tandem accelerator, (2) Utilization of research reactors and tandem accelerator, (3) Upgrading of utilization techniques research reactors and tandem accelerator, (4) Safety administration for research reactors and tandem accelerator, (5) International cooperation. Also contained are lists of publications, meetings, granted permissions on lows and regulations concerning atomic energy, commendation, outcomes in service and technical developments and so on.

JAEA Reports

Application of micro-PIXE and imaging technology to life science (Joint research)

Sato, Takahiro; Ishii, Keizo*

JAEA-Review 2010-078, 45 Pages, 2011/03

JAEA-Review-2010-078.pdf:3.92MB

The joint research on "Application of micro-PIXE and imaging technology to life science" supported by the Inter-organizational Atomic Energy Research Program, had been performed for three years, from 2006FY to 2009FY. Aiming to apply in-air micro-PIXE analytical system to life science, the research was consisting of 7 collaborative themes related to beam engineering for micro-PIXE and applied technology of element mapping in biological/medical fields. The system, so-called micro-PIXE camera, to acquire spatial element mapping in living cells was originally developed by collaborative research between the JAEA and the department of engineering of Tohoku University. This review covers these research results.

JAEA Reports

Operation and management of the Back-end Cycle Key Elements Research Facility; From April 1, 2005 to March 31, 2010

Tagami, Susumu; Shimizu, Osamu; Sano, Naruto; Imaizumi, Akiko; Tobita, Hiroshi; Nagasaki, Yosuke; Kurobane, Shiro

JAEA-Review 2010-079, 90 Pages, 2011/03

JAEA-Review-2010-079.pdf:3.02MB

The Back-end Cycle Key Elements Research Facility (BECKY) was installed in the Nuclear Fuel Cycle Safety Engineering Research Facility (NUCEF) in 1994 for the safety and basic studies of the nuclear fuel cycle and radioactive waste. BECKY consists of three alpha/$$gamma$$ concrete cells, three alpha/$$gamma$$ steel cells, thirty glove boxes and twenty hoods. Operation, maintenance and management are in execution based on the operational safety programs. And we also execute application about amendment of the permission and approval for the purpose of support R&D. This report describes the operation, maintenance and management from April 1, 2005 to March 31, 2010 for the purpose of keeping the performance of BECKY.

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