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Journal Articles

Prospective features for integration of nuclear forensics capability in national framework

Tamai, Hiroshi; Okubo, Ayako; Kimura, Yoshiki; Shinohara, Nobuo; Tazaki, Makiko; Shimizu, Ryo; Suda, Kazunori; Tomikawa, Hirofumi

Proceedings of INMM 58th Annual Meeting (Internet), 6 Pages, 2017/07

Nuclear forensics is a technical measure to analyse and collate samples of illegally used nuclear materials, etc., to clarify their origins, routes, etc. and contribute to criminal identifications. Close collaboration with police and judicial organizations is essential. The national response framework is being built up with international cooperation. Discussions on promoting technical capability and regional cooperation are presented.

JAEA Reports

Japan Atomic Energy Research Institute (JAERI), Evaluation report of JAERI

The Institute Evaluation Committee

JAERI-Review 2004-028, 102 Pages, 2004/12

JAERI-Review-2004-028.pdf:30.81MB

At Japan Atomic Energy Research Institute, the evaluation on general organizational management and overall research and development activities for five year term beginning with FY1999 was conducted in accordance with "The Broad Guidelines for Implementation of Evaluation of All National Research and Development Projects (determined by the Prime Minister on August 7, 1997)" and "The Broad Guidelines for Evaluation of All National Research and Development Projects (determined by the Prime Minister on November 28, 2001)". The evaluation was implemented by "Japan Atomic Energy Research Institute, Institute Evaluation Committee" consisted of third-party evaluators, and the evaluation results were summarized as "Evaluation Report of JAERI".

Journal Articles

History and understanding of the double contingency principle

Komuro, Yuichi

Nihon Genshiryoku Gakkai-Shi, 45(4), p.265 - 269, 2003/04

no abstracts in English

JAEA Reports

Development of statistical analysis code for meteorological data, W-View

Tachibana, Haruo; Sekita, Tsutomu; Yamaguchi, Takenori

JAERI-Data/Code 2003-002, 46 Pages, 2003/03

JAERI-Data-Code-2003-002.pdf:4.49MB

A computer code (W-View) was developed to analyze the meteorological data statistically based on “the guideline of meteorological statistics for the safety analysis of nuclear power reactor"(Nuclear Safety Commission on January 28,1982; revised on March 29,2001), which code is used for statistical analysis of meteorological data to assess the public dose in case of normal operation and severe accident to get the license of nuclear reactor operation. This code was revised from large office computer code and developed for personal computer user to analyze the meteorological data simply and conveniently and to make the statistical data tables and figures of meteorology.

Journal Articles

The Harmonic current control for DTQ power supplies to high intensity proton Linac

Hori, Toshihiko*; Ito, Takashi; Chishiro, Etsuji; Izumi, Keisuke*; Yamazaki, Masayoshi*; Watanabe, Kazuhiko*; Takasaki, Eiichi*; Hasegawa, Kazuo; Yoshikawa, Hiroshi

Proceedings of 27th Linear Accelerator Meeting in Japan, p.255 - 257, 2002/08

no abstracts in English

JAEA Reports

The Arrangement of the seismic design method of the underground facility

Tanai, Kenji; Horita, M.*; Dewa, Katsuyuki*; Goke, Mitsuo*

JNC TN8410 2001-026, 116 Pages, 2002/03

JNC-TN8410-2001-026.pdf:9.19MB

Earthquake resistance for the underground structure is higher than the ground structure. Therefore, the case of examining the earthquake resistance of underground structure was little. However, it carries out the research on the aseismic designing method of underground structure, since the tunnel was struck by Hyogo-ken Nanbu Earthquake, and it has obtained a much knowledge. However, an object of the most study was behavior at earthquake of the comparatively shallow underground structure in the alluvial plain board, and it not carry out the examination on behavior at earthquake of underground structure in the deep rock mass. In the meantime, underground disposal facility of the high level radioactive waste constructs in the deep underground, and it carries out the operation in these tunnels. In addition, it has made almost the general process of including from the construction start to the backfilling to be about 60 years (Japan Nuclear Fuel Cycle Development Institute, 1999). During these periods, it is necessary to also consider the earthquake resistance as underground structure from the viewpoint of the safety of facilities. Then, it extracted future problem as one of the improvement of the basis information for the decision of the safety standard and guideline of the country on earthquake-resistant design of the underground disposal facility, while it carried out investigation and arrangement of earthquake-resistant design cases, guidelines and analysis method on existing underground structure, etc.. And, the research item for the earthquake resistance assessment of underground structure as case study of the underground research laboratory.

JAEA Reports

None

JNC TN1400 2001-015, 509 Pages, 2001/10

JNC-TN1400-2001-015.pdf:25.67MB

no abstracts in English

JAEA Reports

None

JNC TN1400 2001-014, 437 Pages, 2001/10

JNC-TN1400-2001-014.pdf:23.1MB

no abstracts in English

Journal Articles

What is Japanese for English "double contingency principle"?

Komuro, Yuichi

Nihon Genshiryoku Gakkai-Shi, 43(6), p.580 - 581, 2001/06

no abstracts in English

Journal Articles

Status of Japanese response to the JCO accident

Nozawa, Masao*; Watanabe, Norio

Proceedings of US-Japan Workshop on the Role of Nuclear Energy in a New Environment of Deregulation and Climate Change, 14 Pages, 2000/10

no abstracts in English

JAEA Reports

None

JNC TN4420 2000-009, 11 Pages, 2000/06

JNC-TN4420-2000-009.pdf:0.84MB

None

JAEA Reports

Study of safety aspects for pyrochemical reprocessing systems

Kakehi, Isao; Nakabayashi, Hiroki

JNC TN9400 2000-051, 237 Pages, 2000/04

JNC-TN9400-2000-051.pdf:8.14MB

In this study, we have proposed the concept of safety systems (solutions of safety problems) in pyrochemical reprocessing systems (lt consists of pyrochemical reprocessing methods and the injection casting process for the metal fuel fabrication, or vibro-packing process for the oxide fuel fabrication.) which has different concept from the existing PUREX reprocessing method and pellet fuel fabrication process. And we performed its safety evaluations. FoIlowing the present Japanese safety regulations for reprocessing facilities, we pointed out functions, design requirements and equipments relating to its safety systems and picked up subjects. For the survey of safety evaluations, we first selected anticipated events and accident events, and second by evaluated 6the correspondence of the limitation of the public exposure to the accidents above, by using two parameters, the safety design parameter (the filter performance to confine radioactive matelials) and the leak inventory of radioactivities, and last by picked up its problems. ln addition to the above evaluations we performed basic criticality analyses for its systems to utilize these results for the design and evaluation of the criticality safety management system. Thus this study specified the concept of safety systems for pyrochemical reprocessing processes and then issues in order to establish safety design policies (matters which must consider for the safety design) and guides and to advance more definite safety design.

JAEA Reports

Criticality safety evaluation in Tokai reprocessing plant

Shirai, Nobutoshi; ; ; Shirozu, Hidetomo; Sudo, Toshiyuki; Hayashi, Shinichiro;

JNC TN8410 2000-006, 116 Pages, 2000/04

JNC-TN8410-2000-006.pdf:2.77MB

Criticality limits for equipments in Tokai Reprocessing Plant which handle fissile material solution and are under shape and dimension control were reevaluated based on the guideline No.10 "Criticality safety of single unit" in the regulatory guide for reprocessing plant safety. This report presents criticality safety evaluation of each equipment as single unit. Criticality safety of multiple units in a cell or a room was also evaluated. The evaluated equipments were ones in dissolution, separation, purification, denitration, Pu product storage, and Pu conversion processes. As a result, it was reconfirmed that the equipments were safe enough from a view point of criticality safety of single unit and multiple units.

JAEA Reports

None

*

JNC TN1440 2000-001, 47 Pages, 2000/01

JNC-TN1440-2000-001.pdf:2.57MB

no abstracts in English

JAEA Reports

Report of the JAERI's institution evaluation committee on general organizational managements

Institute Evaluation Committee

JAERI-Review 99-030, p.25 - 0, 1999/11

JAERI-Review-99-030.pdf:1.58MB

no abstracts in English

JAEA Reports

None

JNC TN1440 2000-003, 88 Pages, 1999/08

JNC-TN1440-2000-003.pdf:5.11MB

no abstracts in English

JAEA Reports

None

JNC TN1440 2000-002, 148 Pages, 1999/08

JNC-TN1440-2000-002.pdf:8.54MB

no abstracts in English

JAEA Reports

Assessment report on the research and development themes of Japan Atomic Energy Research Institute

Research Evaluation Committee

JAERI-Review 98-025, 64 Pages, 1998/11

JAERI-Review-98-025.pdf:5.11MB

no abstracts in English

Journal Articles

Overview and present status of the IAEA/RADWASS programme

Abe, Masayoshi

Dekomisshoningu Giho, (18), p.2 - 16, 1998/08

no abstracts in English

Journal Articles

Reduced cost option for ITER

Kikuchi, Mitsuru

Kagaku Gijutsu Janaru, 7(8), p.47 - 48, 1998/08

no abstracts in English

33 (Records 1-20 displayed on this page)