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JAEA Reports

Annual report of JMTR, No.19, FY2004; April 1, 2004 - March 31, 2005

Department of JMTR

JAEA-Review 2006-001, 63 Pages, 2006/02

JAEA-Review-2006-001.pdf:6.32MB

no abstracts in English

JAEA Reports

Report on the questionnaire about the data of atoms, molecules and atomic nuclei for medicine, 2004

Kobayashi, Toru*; Harata, Yasuo*; Matsufuji, Naruhiro*; Hasegawa, Tomoyuki*; Endo, Akira; Moribayashi, Kengo; Akahane, Keiichi*; Uehara, Shuzo*; Imahori, Yoshio*; Kato, Yo*; et al.

JAEA-Review 2006-002, 101 Pages, 2006/02

JAEA-Review-2006-002.pdf:5.53MB

This report provides an analysis of the results of the survey conducted among field experts regarding the data on atoms, molecules, and atomic nuclei used in medical applications. The important results are summarized as follows: First, the importance of the basic data for disciplines involved in medical research, i.e. physics and engineering, chemistry, pharmacology, biology, and the related data which are applied directly in medicine were identified. The related data are of greater importance in direct medical application compared to conventional basic data. Therefore, the data related to biology should be prepared in consideration of their convenient usage. Second, regarding the fundamental data on atoms, molecules and atomic nuclei related to medicine, the present data was able to approximately cope with the demands of many medical cases that needed data on quality, quantity, precision, etc. However, we found situations particularly in the IT community where comprehensively organized data was urgently needed. The data to be used for practical implementation must contain the specialized data for medical physics and biology. Finally, the significance of the continuity in the planned completion of the basic data was confirmed for the development of the associated fields. The expansion and completion of basic data should be done continuously and effectively while considering the limitation in resources and manpower.

JAEA Reports

Ex-post evaluation by bibliometric method; Institutional comparison between JAERI and 8 resembled foreign research institutes

Yanagisawa, Kazuaki

JAEA-Review 2006-003, 49 Pages, 2006/03

JAEA-Review-2006-003.pdf:6.38MB

By using research papers produced both by the Japan Atomic Energy Research Institute (JAERI) and by 8 resembled foreign research institutes (5 in the U. S. A., 2 in Germany and 1 in France), an institutional comparison was tried personally. A bibliometric method was used together with INIS (owned by IAEA) as a database and and SOCIOECO as an evaluatio tool. (1)A total number of papers produced in the duration of 25 years (1978-2002) were of the order of the Oak Ridge National Laboratory (ORNL) $$>$$ JAERI $$>$$ Brookhaven National Laboratory (BNL) $$>$$ Sandia National Laboratory (SNL) $$>$$ Karlsruhe $$>$$ Argonne National Laboratory (ANL) $$>$$ Jeulich $$>$$ Idaho National Laboratory (INL) $$>$$C adarache. JAERI was in the 2nd position.

JAEA Reports

Summary of fuel safety research meeting 2005; March 2-3, 2005, Tokyo

Fuketa, Toyoshi; Nakamura, Takehiko; Nagase, Fumihisa; Nakamura, Jinichi; Suzuki, Motoe; Sasajima, Hideo; Sugiyama, Tomoyuki; Amaya, Masaki; Kudo, Tamotsu; Chuto, Toshinori; et al.

JAEA-Review 2006-004, 226 Pages, 2006/03

JAEA-Review-2006-004.pdf:34.43MB

Fuel Safety Research Meeting 2005, which was organized by the Japan Atomic Energy Agency was held on March 2-3, 2005 at Toshi Center Hotel, Tokyo. The purposes of the meeting are to present and discuss the results of experiments and analyses on reactor fuel safety and to exchange views and experiences among the participants. The technical topics of the meeting covered the status of fuel safety research activities, fuel behavior under Reactivity Initiated Accident (RIA) and Loss of coolant accident (LOCA) conditions, high fuel behavior, and radionuclide release under severe accident conditions. This summary contains all the abstracts and sheets of viewgraph presented in the meeting.

JAEA Reports

Activity report on the utilization of research reactors; Japanese fiscal year, 2004

Research Reactor Utilization Section

JAEA-Review 2006-005, 400 Pages, 2006/03

JAEA-Review-2006-005.pdf:30.66MB

no abstracts in English

JAEA Reports

Activity report of working party on accelerator-driven transmutation system; October 2003 to March 2005

Division of Nuclear Data and Reactor Engineering, Nuclear Science and Engineering Directorate

JAEA-Review 2006-007, 214 Pages, 2006/03

JAEA-Review-2006-007.pdf:13.06MB

Under the Research Committee on Reactor Physics, the Working Party on Accelerator-Driven Transmutation System (ADS-WP) was set in July 2003 to research the issues related to Accelerator-Driven System (ADS) for Transmutation. The WP, at the first meeting, discussed a guideline of its activity for two years and continued the research activities up to March 2005. The ADS-WP studied about the follows three issues: (1)Examining the effect of the nuclear data to the core characteristics of advanced nuclear systems and summarizing the requirement of the nuclear data for researching the advanced nuclear system, (2)Surveying the current program of the research facilities for ADS (J-PARC, TEF-P, TEF-T, KUCA and overseas facilities), (3)Summarizing the requirements and the proposals to a new critical facility for ADS. This report summarizes the outline and results of the ADS-WP activity.

JAEA Reports

Operation, test, research and development of the High Temperature engineering Test Reactor (HTTR) (FY2004)

Department of HTTR

JAEA-Review 2006-008, 90 Pages, 2006/03

JAEA-Review-2006-008.pdf:5.76MB

The High Temperature Engineering Test Reactor (HTTR) 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 with thermal power of 30MW, which is a graphite-moderated and helium gas-cooled reactor. In April 2004, the HTTR achieved the maximum reactor outlet temperature of 950 degree for the first time in the world. In June 2004, JAEA obtained commissioning license from the MEXT for the operation at 950 degree. This report summarizes activities and results on HTTR operation and maintenance as well as several R&Ds, which were carried out in the fiscal year of 2004.

JAEA Reports

Review of JAEA activities on the IFMIF liquid lithium target in FY2005

Ida, Mizuho; Nakamura, Hiroo; Chida, Teruo; Sugimoto, Masayoshi

JAEA-Review 2006-009, 28 Pages, 2006/03

JAEA-Review-2006-009.pdf:3.95MB

The International Fusion Materials Irradiation Facility (IFMIF) is being jointly planned to provide an accelerator-based Deuterium-Lithium (D-Li) neutron source to produce intense high energy neutrons (2 MW/m$$^{2}$$) up to 200 dpa and a sufficient irradiation volume (500 cm$$^{3}$$) for testing candidate materials and components up to about a full lifetime of their anticipated use in ITER and DEMO. 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, radioactive species such as $$^{7}$$Be, tritium and activated corrosion products are generated. In addition, back wall operates under severe conditions of neutron irradiation damage (about 50 dpa/y). In this paper, the thermal structural analysis and the accessibility evaluation of the IFMIF Li loop are summarized as JAEA activities on the IFMIF target system performed in FY2005.

JAEA Reports

The Approaches of safety design and safety evaluation at HTTR (High Temperature Engineering Test Reactor)

Iigaki, Kazuhiko; Saikusa, Akio; Sawahata, Hiroaki; Shinozaki, Masayuki; Tochio, Daisuke; Homma, Fumitaka; Tachibana, Yukio; Iyoku, Tatsuo; Kawasaki, Kozo; Baba, Osamu*

JAEA-Review 2006-010, 90 Pages, 2006/07

JAEA-Review-2006-010.pdf:5.65MB

Gas Cooled Reactor has long history of nuclear development, and High Temperature Gas Cooled Reactor (HTGR) has been expected that it can be supply high temperature energy to chemical industry and to power generation from the points of view of the safety, the efficiency, the environment and the economy. The HTGR design is tried to installed passive safety equipment. The current licensing review guideline was made for a Low Water Reactor (LWR) on safety evaluation therefore if it would be directly utilized in the HTGR it needs the special consideration for the HTGR. This paper describes that investigation result of the safety design and the safety evaluation traditions for the HTGR, comparison the safety design and safety evaluation feature for the HTGT with it's the LWR, and reflection for next HTGR based on HTTR operational experiment.

JAEA Reports

Radio-nuclide Migration Datasets (RAMDA) for the safety assessment of TRU waste repositories in Japan

Mihara, Morihiro

JAEA-Review 2006-011, 51 Pages, 2006/03

JAEA-Review-2006-011.pdf:3.52MB

The Federation of Electric Power Companies (FEPC) and the Japan Nuclear Cycle Development Institute (JNC) published a technical report on the safty assessment of TRU waste repositories last September in order to promote the establishment of the regulatory framework and a implementation body in Japan. TRU waste is being generated in a reprocessing plant and a fabrication plant of mixed oxide fuel (UO$$_{2}$$ and PuO$$_{2}$$) for the nuclear power plant. It is categorized as low-level radioactive waste in Japan, however it contains long half-live radio-nuclides such as C-14, I-129, Pu-239 and Np-237. In the technical report, the nuclide migration analyses were performed for the safety assessment of TRU waste repository. RAMDA (Radio-nuclide Migration Datasets) was used in these analyses. In this report, the explanation of RAMDA is described. In addition, the datasets used for the oxidized condition also are reported. The following datasets are shown.-The solubilities of radio-nuclides-The effective diffusion coefficients of radio-nuclides-The distribution coefficients of radio-nuclides on engineered and natural barriers

JAEA Reports

Progress of nuclear safety research, 2005

Editorial Committee on Nuclear Safety Research Results

JAEA-Review 2006-012, 184 Pages, 2006/03

JAEA-Review-2006-012.pdf:16.42MB

The Japan Atomic Energy Research Institute (JAERI), one of the predecessors of the Japan Atomic Energy Agency (JAEA), had conducted nuclear safety research primarily at the Nuclear Safety Research Center in close cooperation with the related departments in accordance with the Long Term Plan for Development and Utilization of Nuclear Energy and Five-Years Program for Safety Research issued by the Japanese government. The fields of conducting safety research at JAERI were the engineering safety of nuclear power plants and nuclear fuel cycle facilities, and radioactive waste management as well as advanced technology for safety improvement or assessment. Also, JAERI had conducted international collaboration to share the information on common global issues of nuclear safety and to supplement own research. Moreover, when accidents occurred at nuclear facilities, JAERI had taken a responsible role by providing technical experts in assistance to conducting accident investigations or emergency responses by the government or local government. These nuclear safety research and technical assistance to the government have been taken over as an important role by JAEA. This report summarizes the nuclear safety research activities of JAERI from April 2003 through September 2005 and utilized facilities.

JAEA Reports

A Semi annual report on the activities in Safety Administration Division; Report of the first half of 2005 (Document on present state of affairs)

Yamamoto, Junta

JAEA-Review 2006-013, 125 Pages, 2006/07

JAEA-Review-2006-013.pdf:13.51MB

The activities of Safety Administration Division covers many fields in Tokai-Works JNC 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 Division since April, 2005 until September, 2005.

JAEA Reports

The Study plan on applicability to actual geological environment conditions of the engineering technology for geological disposal of high level nuclear-waste through the second phases in Horonobe Underground Research Project

Aoyanagi, Shigeo; Yui, Mikazu; Tanai, Kenji; Kawakami, Susumu; Fujita, Tomoo; Taniguchi, Naoki; Shibata, Masahiro; Konishi, Kazuhiro; Nishimura, Mayuka; Kikuchi, Hirohito*; et al.

JAEA-Review 2006-014, 61 Pages, 2006/03

JAEA-Review-2006-014.pdf:5.03MB

no abstracts in English

JAEA Reports

Study plan for performance assessment of HLW geological disposal, 5-year plan

Miyahara, Kaname; Yoshikawa, Hideki; Oi, Takao; Shibata, Masahiro; Sawada, Atsushi; Sasamoto, Hiroshi; Iijima, Kazuki; Maekawa, Keisuke; Kawamura, Makoto; Kato, Tomoko; et al.

JAEA-Review 2006-015, 29 Pages, 2006/03

JAEA-Review-2006-015.pdf:4.58MB

This report is to outline a 5-year plan of research and development (R&D) for performance assessment of geological disposal of high-level radioactive waste in JAEA. This 5-year plan is based on JAEA's mid-term plan which follows the R&D policy specified in "Framework for Nuclear Energy Policy" issued by Japan Atomic Energy Commission. Moreover, research plans for safety regulation issued by Nuclear Safety Commission of Japan should be taken into account. The contents of this 5-year plan follows a framework of R&D issues for performance assessment field established in "the R&D map", i.e. the mid and long term R&D plan for geological disposal of high-level radioactive waste, developed by JNC (predecessor of JAEA) and other relevant R&D organizations. In each research plan, objectives based on the necessity and the significance of the research plan are clarified in the section of "Objectives and the past progresses", with summarizing the progresses of H12: Project to establish the scientific and technical basis for HLW disposal in Japan (Second Progress Report), and H17: Development and management of the technical knowledge base for the geological disposal of HLW (H17 report). In addition, next five year plan is described in the section of "5-year plan (up to Fiscal year Heisei-22)".

JAEA Reports

Information exchange mainly on HTGR operation and maintenance technique between JAEA and INET in 2005

Tachibana, Yukio; Hino, Ryutaro; Yu, S.*

JAEA-Review 2006-016, 27 Pages, 2006/06

JAEA-Review-2006-016.pdf:4.34MB

no abstracts in English

JAEA Reports

Development of high thermal conductive SiC fiber reinforced SiC matrix composites for fusion reactors (Thesis)

Taguchi, Tomitsugu

JAEA-Review 2006-017, 213 Pages, 2006/07

JAEA-Review-2006-017.pdf:23.62MB

A 3 dimensional model (after cubic model) was developed to quantitively predict the thermal conductivity of SiC fiber-reinforced SiC matrix (SiC/SiC) composites. The cubic model showed that thermal conductivity of the composites increased by decreasing the porosity and ensphering the shape of pore. The SiC/SiC composites were fabricated by chemical vapor infiltration (CVI) and reaction bonding (RB) processes. The thermal conductivity of the composites by RB process was higher than that by CVI process. The reason is that the porosity of the composites by RB process was lower than that by CVI process and the shape of pore in the composites by RB process was almost sphere. The thermal conductivity of the SiC/SiC composite by RB process was consistent with the estimated value by the cubic model. The cubic model also showed that the thermal conductivity of the composites increased by introducing a high thermal conductive new phase parallel to the direction of heat flow. To verify the prediction, a SiC/SiC composite with carbon nano-fiber (CNF) were fabricated by RB process. The thermal conductivity of the SiC/SiC composite with CNF was approximately 90 W/mK at room temperature. The thermal conductivity of the SiC/SiC composite was coincided with the estimated value by the cubic model. They concluded that the cubic model was useful for predicting the thermal conductivity of fiber-reinforced composites.

JAEA Reports

Voluntary research results for five years along the master plan on nuclear safety research (FY 2001-2005)

Safety Section, Safety Administration Department

JAEA-Review 2006-018, 234 Pages, 2006/05

JAEA-Review-2006-018.pdf:22.91MB

Safety Research has been conducted from FY 2001 to FY 2005 according to the Master Plan on Nuclear Safety Research (FY 2001-2005) in Japan Atomic Energy Agency which took over former Japan Nuclear Cycle Development Institute. This report shows the voluntary research results for five years conducted from FY 2001 to FY 2005 according to the Master Plan on Nuclear Safety Research (FY 2001-2005).

JAEA Reports

Development of environmental conservation technology and its transfer to society; The Report of the Subcommittee on Material Development, the Research Committee for Frontier Radiation Application

Kojima, Takuji

JAEA-Review 2006-019, 172 Pages, 2006/07

JAEA-Review-2006-019.pdf:18.82MB

The promotion of the collaboration among industries, government and universities on exchanges of information and technologies on the environmental conservation is strongly required for the acceleration of the R&D on environmental conservation technology and its transfer to society. The subcommittee on Material Development, the Research Committee for Frontier Radiation Application of Japan Atomic Energy Research Institute (Japan Atomic Energy Agency, from Oct.2005) organized subcommittee meetings six times in the four years from 2002. The discussion on the research plan of the environmental conservation processing using ionizing radiation and the information exchange of the present status on R&D on environmental conservation such as monitoring and purification treatment technologies for pollutants were performed in the subcommittee activities. The present report on such activities should contribute the acceleration of the R&D on environmental conservation technology and its transfer to society by the further collaboration among industries, government and universities.

JAEA Reports

Report on the 9th Workshop on the Innovative Water Reactor for Flexible Fuel Cycle; March 1, 2006, Koku-kaikan, Minato-ku, Tokyo

Ishikawa, Nobuyuki; Kobayashi, Noboru; Okubo, Tsutomu; Uchikawa, Sadao

JAEA-Review 2006-020, 102 Pages, 2006/07

JAEA-Review-2006-020.pdf:11.72MB

The research on Innovative Water Reactor for Flexible Fuel Cycle (FLWR) has been performed in JAEA for the development of future innovative reactor. The workshop on FLWRs has been held every year since 1998 aiming at information exchange with other organizations such as universities, laboratories, utilities and vendors. The 9th workshop was held on March 1, 2006 with 64 participants. The workshop began with presentation entitled "Activities on Nuclear Science and Engineering Research and Collaboration with Industry in JAEA", followed by presentations entitled "Progress of Research and Development on FLWR" and "On Final Report of Feasibility Study (phase 2) on Commercialized FBR Cycle Systems". Then two lectures followed: "Core and Fuel Design on Super Light Water Reactor" by Tokyo University and "Recent Trends on the Development of Next Generation Nuclear Reactor" by Institute of Applied Energy. This report summarizes the lectures of the workshop.

JAEA Reports

Review of research activities in the fusion neutronics source from April 1, 2004 to March 31, 2006

Fusion Neutronics Group

JAEA-Review 2006-021, 155 Pages, 2006/07

JAEA-Review-2006-021.pdf:12.4MB

no abstracts in English

JAEA Reports

The 2005 activities and the workshop of the human resources development project in FNCA (Contract research)

Otomo, Akitoshi

JAEA-Review 2006-022, 221 Pages, 2006/10

JAEA-Review-2006-022.pdf:104.5MB

In 1999, the Project for Human Resources Development (HRD Project) was initiated as defined in the framework of the Forum for Nuclear Cooperation in Asia (FNCA), organized by the Atomic Energy Commission of Japan. The objective of the HRD Project is to solidify the foundation of technologies for nuclear development and utilization in Asia by promoting human resources development in Asian countries. In the Project there are two kinds of activity; In-workshop activity and Outside-of-workshop activity. The FNCA 2005 Workshop on HRD Project was held on September 13-16, 2005, in Dalat, Viet Nam. The Workshop was sponsored by the Ministry of Science and Technology (MOST) of Viet Nam and the Ministry of Education, Culture, Sports, Science and Technology (MEXT) of Japan. The Vietnam Atomic Energy Commission (VAEC) and the Japan Atomic Energy Agency (JAEA) acted as the hosts. Participating countries were China, Indonesia, Republic of Korea, Japan, Malaysia, the Philippines, Thailand, and Vietnam. The activities of HRD Project was presented in the Seventh Coordinators Meeting of FNCA was held on March 30 - April 1, 2006, in Tokyo, Japan. This report consists of presentation papers and materials at the FNCA 2005 Workshop, a review document of HRD Project for the Coordinators Meeting of FNCA as Outside-Workshop Activity.

JAEA Reports

Annual report on major results and progress of Naka Fusion Research Establishment of JAERI from April 1 to September 30, 2005 and Fusion Research and Development Directorate of JAEA from October 1, 2005 to March 31, 2006

Fusion Research and Development Directorate

JAEA-Review 2006-023, 122 Pages, 2006/09

JAEA-Review-2006-023.pdf:26.73MB

This annual report provides an overview of major results and progress on research and development activities at Naka Fusion Research Establishment of Japan Atomic Energy Research Institute (JAERI) during the period from April 1 to September 30, 2005 and at Fusion Research and Development Directorate of Japan Atomic Energy Agency (JAEA) from October 1, 2005 to March 31, 2006, including those performed in collaboration with other research establishments of JAERI, research institutes, and universities.

JAEA Reports

Annual report on the effluent control of low level liquid waste in Nuclear Fuel Cycle Engineering Laboratories FY2005

Takeishi, Minoru; Miyagawa, Naoto; Uezu, Yasuhiro; Nakano, Masanao; Koarashi, Jun; Mizutani, Tomoko; Kono, Takahiko; Hiyama, Yoshinori*; Fujii, Yoshiyuki*; Kikuchi, Masaaki*; et al.

JAEA-Review 2006-024, 133 Pages, 2006/09

JAEA-Review-2006-024.pdf:6.69MB

Based on the regulations (the safety regulation of Tokai reprocessing plant, the safety regulation of nuclear fuel usage facilities, radiation safety rule, the regulation about prevention from radiation hazards due to radioisotopes, which are related with the nuclear reguratory acts, and the local agreement concerning with security and environment conservation around nuclear facilities, the water pollution control law, and byelaw of Ibaraki prefecture), this report describes the effluent control results of low level liquid waste discharged from the JAEA's Nuclear Fuel Cycle Engineering Laboratories in the fiscal year 2005, from 1st April 2005 to 31th March 2006. In this period, the concentrations and the quantities of the discharged radioactive materials 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

Summaries of research and development activities by using JAEA computer system in FY2005 (April 1, 2005 - March 31, 2006)

Information Technology Systems' Management and Operating Office

JAEA-Review 2006-025, 190 Pages, 2006/10

JAEA-Review-2006-025.pdf:43.74MB

Center for Promotion of Computational Science and Engineering(CCSE) of Japan Atomic Energy Agency (JAEA) installed large computer systems including super-computers in order to support research and development activities in JAEA. CCSE operates and manages the computer system and network system. This report presents usage records of the JAERI computer system and the big users' research and development activities by using the computer system in FY2005 (April 1, 2005 - March 31, 2006)

JAEA Reports

A Semi annual report on the activities in Safety Administration Department; Report of the second half of 2005

Yamamoto, Junta

JAEA-Review 2006-026, 164 Pages, 2006/09

JAEA-Review-2006-026.pdf:15.26MB

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 Octorber, 2005 until March, 2006.

JAEA Reports

Review of recent events involving degradation of reactor coolant system pressure boundary due to primary water stress corrosion cracking at U. S. PWRs

Watanabe, Norio; Takahara, Shogo

JAEA-Review 2006-027, 141 Pages, 2006/09

JAEA-Review-2006-027.pdf:24.85MB

Primary Water Stress Corrosion Cracking (PWSCC), which occurs on nickel-based alloy (Alloy 600) reactor coolant pressure boundary components, has been a safety concern at pressurized water reactors (PWRs). During the years from 2000 to 2002, in particular, circumferential cracks on reactor pressure vessel head penetrations and significant degradation of vessel head have been observed at U. S. PWR plants and thus, awareness of the safety significance of PWSCC was raised because circumferential cracking and leakage of RPV head nozzles and corrosion of the RPV head resulting from PWSCC may lead to pressure boundary failure if the conditions are not detected and repaired. In response to the recent experience, the Nuclear Regulatory Commission (NRC) issued the inspection Order EA-03-009 for PWR licensees to prepare and implement more effective inspections of the reactor vessel heads and associated penetration nozzles. This report provides the description on the historical NRC's responses to PWSCC issues and the review of the forty-five events, reported as licensee event reports, involving PWSCC on reactor coolant pressure boundary components at U. S. PWRs during the years from 1999 to 2005.

JAEA Reports

Proceedings of the Workshop on Multiple Prompt Gamma-ray Analysis; Tokai, March 8, 2006

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

JAEA-Review 2006-028, 97 Pages, 2006/10

JAEA-Review-2006-028.pdf:29.98MB

The workshop on "Multiple Prompt Gamma-ray Analysis" was held on March 8, 2006 at Tokai. It is based on a project, "Developments 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. In this workshop, the latest results of the Multiple Prompt Gamma ray Analysis (MPGA) study were presented, together with those of Neutron Activation Analysis with Multiple Gamma-ray Detection (NAAMG). This report records the papers and the materials of 9 presentations in the workshop.

JAEA Reports

JAEA-Tokai tandem annual report 2005; April 1, 2005 - March 31, 2006

Department of Research Reactor and Tandem Accelerator

JAEA-Review 2006-029, 151 Pages, 2006/09

JAEA-Review-2006-029.pdf:23.69MB

This annual report describes research activities, which have been performed using the JAEA-Tokai tandem accelerator with the energy booster from April 1, 2005 to March 31, 2006. Summary reports of 51 papers are categorized into seven research/development fields, i.e., (1) accelerator operation and development, (2) nuclear structure, (3) nuclear reaction, (4) nuclear chemistry, (5) nuclear theory, (6) atomic physics and solid state physics, and (7) radiation effects in materials, and lists of publications, meetings, personnel and cooperative researches with universities are contained.

JAEA Reports

A Review of key issues for regulations on geological disposal; Focusing on principle, standard and compliance

Miyahara, Kaname; Kato, Tomoko

JAEA-Review 2006-030, 26 Pages, 2006/10

JAEA-Review-2006-030.pdf:2.48MB

Japan Atomic Energy Agency (JAEA) rigorously continues to conduct research and development for establishing scientific and technical basis as an advanced knowledge base for implementation and safety regulations of HLW geological disposal. The current main goal of the regulator is to establish the required structure of safety goals and guidelines. In this respect, knowledge is required to provide a guidance to support definition of regulatory guidelines and guidance on demonstration of compliance. These may involve international review of regulations in particular with regard to areas where there is a lack of consensus (e.g. cut-off times, performance measures in the distant future). This report is to provide an example of an international review of key issues for regulations on geological disposal.

JAEA Reports

Annual report on the environmental radiation monitoring around Tokai Reprocessing Plant FY2005

Takeishi, Minoru; Miyagawa, Naoto; Nakano, Masanao; Takeyasu, Masanori; Isozaki, Hisaaki; Isozaki, Tokuju; Morisawa, Masato; Fujita, Hiroki; Kokubun, Yuji; Kato, Chiaki; et al.

JAEA-Review 2006-031, 155 Pages, 2006/10

JAEA-Review-2006-031.pdf:7.76MB
JAEA-Review-2006-031(errata).pdf:0.13MB

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 2005 to March 2006. 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 for FY2005 on the activities of Department of Radiation Protection; April 1, 2005 - March 31, 2006

Murakami, Hiroyuki; Mizushita, Seiichi; Yoshizawa, Michio; Yamamoto, Hideaki; Yamaguchi, Takenori; Yamaguchi, Yasuhiro

JAEA-Review 2006-032, 181 Pages, 2006/11

JAEA-Review-2006-032.pdf:45.0MB

This annual report describes the activities of Department of Radiation Protection in Nuclear Science Research Institute in the fiscal year 2005. The report covers environmental monitoring around the facilities, radiation protection of workplace and workers, individual monitoring, maintenance of monitoring instruments, and research and development of radiation protection technologies, which were performed at Nuclear Science Research Institute, Tokai Research and Development Center, Japan Atomic Energy Agency. There were no occupational or public exposures exceeding the prescribed dose limits. No effluent releases were recorded exceeding the prescribed limits on the amount and concentration of radioactivity for gaseous release and liquid waste. As for the research and development activities, studies were conducted focusing mainly on the following themes: technological developments on operational radiation protection and establishment of calibration fields for various types of neutrons.

JAEA Reports

2005 Annual report of MEXT specially promoted research, "Development of the 4D space access neutron spectrometer (4SEASONS) and elucidation of the mechanism of oxide high-$$T_c$$ superconductivity"

Arai, Masatoshi; Yokoo, Tetsuya*; Kajimoto, Ryoichi; Nakajima, Kenji; Shamoto, Shinichi; Yamada, Kazuyoshi*; Fujita, Masaki*; Ino, Takashi*; Soyama, Kazuhiko; Nakamura, Mitsutaka; et al.

JAEA-Review 2006-033, 58 Pages, 2006/11

JAEA-Review-2006-033.pdf:17.22MB

A research project entitled "Development of the 4D Space Access Neutron Spectrometer (4SEASONS) and Elucidation of the Mechanism of Oxide High-$$T_c$$ Superconductivity" has started in 2005 (repr. by M. Arai). It is supported by MEXT, Grant-in-Aid for Specially Promoted Research and is going to last until fiscal 2009. The goal of the project is to elucidate the mechanism of oxide high-$$T_c$$ superconductivity by neutron scattering technique. For this purpose, we will develop an inelastic neutron scattering instrument 4SEASONS (4d SpacE AccesS neutrON Spectrometer) for the spallation neutron source in Japan Proton Accelerator Research Complex (J-PARC). The instrument will have 100 times higher performance than existing world-class instruments, and will enable detailed observation of anomalous magnetic excitations and phonons in a four-dimensional momentum-energy space. This report summarizes the progress in the research project in fiscal 2007.

JAEA Reports

Annual report on the present state and activities of the radiation protection department, Nuclear Fuel Cycle Engineering Laboratories in fiscal 2005

Radiation Protection Department

JAEA-Review 2006-034, 145 Pages, 2006/12

JAEA-Review-2006-034.pdf:10.99MB

This annual report summarizes the activities on radiation control in the Nuclear Fuel Cycle Facilities, personnel monitoring, monitoring of gas and liquid waste effluents, environmental monitoring, maintenance of radiation instruments, safety research, and technical support were, undertaken by the Radiation Protection Department at Nuclear Fuel Cycle Engineering Laboratories in fiscal 2005.

JAEA Reports

Annual report of JMTR, No.20, FY2005; April 1, 2005 - March 31, 2006

Department of JMTR

JAEA-Review 2006-035, 60 Pages, 2006/12

JAEA-Review-2006-035.pdf:5.82MB

During the FY2005 (from April 2005 to March 2006), the Japan Materials Testing Reactor (JMTR) was operated in five operation cycles in order to carry out various irradiation tests and post-irradiation examinations (PIEs) for studies on Irradiation Assisted Stress Corrosion Cracking (IASCC) of internal structures of light water reactor, development of the fusion blanket, basic materials researches, radioisotope production, and so on. Operating days of FY2005 was shorter than scheduled because of the commercial power failure in the 160th operation cycle and extension of the annual inspection term caused by incompleteness of inspecting condition.

JAEA Reports

Annual report of Department of Research Reactors and Tandem Accelerator, JFY2005; Operation, utilization and technical development of JRR-3, JRR-4, NSRR and Tandem Accelerator

Department of Research Reactor and Tandem Accelerator

JAEA-Review 2006-036, 219 Pages, 2006/12

JAEA-Review-2006-036.pdf:11.96MB

The Department of Research Reactors and Tandem Accelerator is responsible for the operation, utilization and technical development of JRR-3(Japan Research Reactor-3), JRR-4(Japan research Reactor-4) and NSRR(Nuclear Safety Research Reactor) as well as Tandem Accelerator. The following services and technical developments were achieved in Japanese Fiscal Year (JFY) 2006: JRR-3 was operated for 156 days in 7 cycles and JRR-4 for 145 days in 37 cycles. They provided neutrons for research and development of internal and external users. (1) JRR-3 and JRR-4 were utilized through deliberate coordination as follows, (a) Neutron irradiations of 633 such as neutron transmutation doping of silicon, (b) Capsule irradiations of 2922 such as neutron activation analyses, (c) Neutron beam experiments of 5511 (cases*workdays). (2) According for the plan increasing cold neutron beam strength 10 times, Integrity of moderator vessel at liquid-hydrogen-evaporation events was confirmed by the stress analyses. Also, it was confirmed by optical tests that glass type carbon plates promising as radiation-resistant neutron guides possesses the same performance of glass plates, and irradiation tests of glass type carbon plates was prepared. (3) In Born Neutron Capture Therapy using JRR-4, an extended collimator that enable clinical trials for head-and-neck cancer were put into practical use. (4) In NSRR, pulse operations of 4 were carried out as planed, to experiment the high burn-up fuel of LWR. The capsule loading facility Type B was completed for to high- plutonium-content and high-burn-up MOX fuel. (5) Tandem accelerator was operated for 182 days to carry out all the scheduled experiments with heavy ions for internal and external users. The multi-charge ion injector in the high voltage terminal was moved to the other side in the terminal so that the beam stability was improved.

JAEA Reports

Annual report of Nuclear Technology and Education Center (April 1, 2005 - March 31, 2006)

Nuclear Technology and Education Center

JAEA-Review 2006-037, 112 Pages, 2006/12

JAEA-Review-2006-037.pdf:9.38MB

This report summarizes the activities of the Nuclear Technology and Education Center (NuTEC) of the Japan Atomic Energy Agency (JAEA) in the fiscal year 2005. On unification of JAERI and JNC on October, 2005, the former NuTEC of JAERI and the Human Resources Development Section of JNC were reorganized as the new NuTEC. Concomitantly, the training courses on nuclear emergency preparedness, held at the former NuTEC, was transferred to NEAT, JAEA, and the management related to university cooperation was assigned as one of the tasks of the new NuTEC. In total, the number of trainees for the general domestic training courses was 652, while that for the staff technical training courses was 616. The international training courses have also been carried out as planned. In addition, supportive activities for the Nuclear Professional School of Tokyo University, commenced in April, 2006, have been made mainly concerning the experimental exercises for the students.

JAEA Reports

Research on improvement of nuclear characteristic evaluation method for High Temperature Engineering Test Reactor (HTTR) (thesis)

Fujimoto, Nozomu

JAEA-Review 2006-038, 160 Pages, 2007/01

JAEA-Review-2006-038.pdf:9.75MB

A nuclear characteristic evaluation method for the HTTR has been developed with data obtained by criticality tests. The developed calculation model shows good agreement to the measured results within an error of 1%$$Delta$$k/k. The calculation model is expanded for power operation calculation. In the expansion, effects of fuel enrichment, effects of temperature on BP burnup characteristics are evaluated. The expanded calculation model shows about the same results with experimental results. In the comparison with Monte Carlo code, power distribution in the core shows good agreement with each other. In the comparison with $$gamma$$ ray measurements from fuel block, expanded model shows good agreements with measured results. It is also become clear that the improvement of calculation model is effective in improvement of power distribution calculation with comparison to a calculation model for HTTR design.

JAEA Reports

Study plan for performance assessment of potential effect of natural phenomena on a HLW disposal system, 5-year plan

Kawamura, Makoto; Oi, Takao; Makino, Hitoshi; Umeda, Koji; Niizato, Tadafumi; Yasue, Kenichi; Kawachi, Susumu; Ishimaru, Tsuneari; Seo, Toshihiro; Ebina, Takanori*; et al.

JAEA-Review 2006-039, 60 Pages, 2007/01

JAEA-Review-2006-039.pdf:7.39MB

This report is to outline a 5-year plan of research and development (R&D) for performance assessment of potential effect of natural phenomena on a geological disposal of high-level radioactive waste in JAEA. In each research plan, objectives based on the necessity and the significance of the research plan are clarified in the section of "Objectives and the past progresses", with summarizing the progresses of H12: Project to establish the scientific and technical basis for HLW disposal in Japan (Second Progress Report), and H17: Development and management of the technical knowledge base for the geological disposal of HLW (H17 report). In addition, next five year plan is described in the section.

JAEA Reports

Analysis of nuclear and radiological events; Textbook for lecture in graduate school of engineering in the University of Tokyo

Watanabe, Norio

JAEA-Review 2006-040, 60 Pages, 2007/02

JAEA-Review-2006-040.pdf:5.41MB

The Japan Atomic Energy Agency is carrying out the cooperative activity by providing specialized educational and training staff and making our facilities available for the graduate school of engineering in The University of Tokyo as part of developing human resources in nuclear technology. This report is prepared as a textbook for the lecture in the graduate school of engineering in The University of Tokyo and provides the outlines of activities on the analysis of nuclear and radiological events and analysis methods as well as the summaries of major incidents and accidents that occurred.

JAEA Reports

Probabilistic safety assessment for nuclear power plants: Level 1 PSA for internal events; Textbook for lecture in graduate school of engineering in the University of Tokyo

Watanabe, Norio

JAEA-Review 2006-041, 43 Pages, 2007/02

JAEA-Review-2006-041.pdf:3.08MB

The Japan Atomic Energy Agency is carrying out the cooperative activity by providing specialized educational and training staff and making our facilities available for the graduate school of engineering in The University of Tokyo as part of developing human resources in nuclear technology. This report is prepared as a textbook for the lecture in the graduate school of engineering in The University of Tokyo and provides the outlines of procedures and analysis approach to the probabilistic safety assessment (PSA) for nuclear power plants, in particular, the level 1 PSA (evaluation of core damage frequency) with examples shown.

JAEA Reports

JAEA Takasaki annual report 2005

Ohara, Yoshihiro

JAEA-Review 2006-042, 240 Pages, 2007/02

JAEA-Review-2006-042.pdf:31.02MB

JAEA Takasaki annual report 2005 describes research and development activities performed from April 1, 2005 to March 31, 2006 with Takasaki Ion Accelerators for Advanced Radiation Application (TIARA, four ion accelerators), and those in a recent few years with 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) nuclear and energy engineering, (2) environmental conservation and resource security, (3) biotechnology and medical application, (4) advanced materials, analysis and novel technology. This annual report contains 182 reports consisting of 174 research papers and 8 status reports on operation/maintenance of above irradiation facilities, and a list of publications, related press-releases, TV programs, patents, and the type of research collaborations as Appendices.

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