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JAEA Reports

Fuel debris criticality analysis technology using non-contact measurement method (Contract research); FY2021 Nuclear Energy Science & Technology and Human Resource Development Project

Collaborative Laboratories for Advanced Decommissioning Science; Tokyo Institute of Technology*

JAEA-Review 2022-043, 52 Pages, 2023/01

JAEA-Review-2022-043.pdf:3.48MB

The Collaborative Laboratories for Advanced Decommissioning Science (CLADS), Japan Atomic Energy Agency (JAEA), had been conducting the Nuclear Energy Science & Technology and Human Resource Development Project (hereafter referred to "the Project") in FY2021. The Project aims to contribute to solving problems in the nuclear energy field represented by the decommissioning of the Fukushima Daiichi Nuclear Power Station, Tokyo Electric Power Company Holdings, Inc. (TEPCO). For this purpose, intelligence was collected from all over the world, and basic research and human resource development were promoted by closely integrating/collaborating knowledge and experiences in various fields beyond the barrier of conventional organizations and research fields. The sponsor of the Project was moved from the Ministry of Education, Culture, Sports, Science and Technology to JAEA since the newly adopted proposals in FY2018. On this occasion, JAEA constructed a new research system where JAEA-academia collaboration is reinforced and medium-to-long term research/development and human resource development contributing to the decommissioning are stably and consecutively implemented. Among the adopted proposals in FY2021, this report summarizes the research results of the "Fuel debris criticality analysis technology using non-contact measurement method" conducted in FY2021. The purpose of research was to improve the fuel debris criticality analysis technology using non-contact measurement method by the development of the fuel debris criticality characteristics measurement system and the multi-region integral kinetic analysis code. It was performed by Tokyo Institute of Technology (Tokyo Tech), National Institute of Advanced Industrial Science and Technology (AIST), and National Research Nuclear University (MEPhI) as the first year of four years research project. For the criticality characteristic measurement systems to be developed by the Japanese and Russian sides, …

JAEA Reports

Progress report on Nuclear Safety Research Center (JFY 2015 - 2017)

Nuclear Safety Research Center, Sector of Nuclear Safety Research and Emergency Preparedness

JAEA-Review 2018-022, 201 Pages, 2019/01

JAEA-Review-2018-022.pdf:20.61MB

Nuclear Safety Research Center (NSRC), Sector of Nuclear Safety Research and Emergency Preparedness, Japan Atomic Energy Agency (JAEA) is conducting technical support to nuclear safety regulation and safety research based on the Mid-Long Term Target determined by Japanese government. This report summarizes the research structure of NSRC and the cooperative research activities with domestic and international organizations as well as the nuclear safety research activities and results in the period from JFY 2015 to 2017 on the nine research fields in NSRC; (1) severe accident analysis, (2) radiation risk analysis, (3) safety of nuclear fuels in light water reactors (LWRs), (4) thermohydraulic behavior under severe accident in LWRs, (5) materials degradation and structural integrity, (6) safety of nuclear fuel cycle facilities, (7) safety management on criticality, (8) safety of radioactive waste management, and (9) nuclear safeguards.

Journal Articles

Scaling issues for the experimental characterization of reactor coolant system in integral test facilities and role of system code as extrapolation tool

Mascari, F.*; Nakamura, Hideo; Umminger, K.*; De Rosa, F.*; D'Auria, F.*

Proceedings of 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16) (USB Flash Drive), p.4921 - 4934, 2015/08

JAEA Reports

Progress of nuclear safety research, 2004

Editorial Committee on Nuclear Safety Research Results

JAERI-Review 2005-009, 151 Pages, 2005/03

JAERI-Review-2005-009.pdf:31.04MB

no abstracts in English

JAEA Reports

Progress of nuclear safety research, 2003

Editorial Committee on Nuclear Safety Research Results

JAERI-Review 2004-010, 155 Pages, 2004/03

JAERI-Review-2004-010.pdf:16.43MB

JAERl is conducting 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 Annual Plan for Safety Research issued by the Japanese government. The fields of conducting safety research at JAERl are 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 has conducted international collaboration to share the information on common global issues of nuclear safety and to supplement own research. This report summarizes the nuclear safety research activities of JAERI from April 2001 through March 2003 and utilized facilities.

JAEA Reports

Progress of nuclear safety research; 2002

Editorial Committee on Nuclear Safety Research Results

JAERI-Review 2002-030, 143 Pages, 2002/11

JAERI-Review-2002-030.pdf:16.51MB

JAERl is conducting 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 or the Safety Research Annual Plan issued by the Japanese government. The safety research at JAERl concerns 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 has conducted international collaboration to share the information on common global issues of nuclear safety. This report summarizes the nuclear safety research activities of JAERI from April 2000 through April 2002.

JAEA Reports

Progress of nuclear safety resarch; 2001

Editorial Committee on Nuclear Safety Research Results

JAERI-Review 2001-032, 126 Pages, 2001/10

JAERI-Review-2001-032.pdf:10.42MB

no abstracts in English

JAEA Reports

Status of nuclear safety research, 2000

Editorial Committee on Nuclear Safety Research Results

JAERI-Review 2000-028, 106 Pages, 2000/11

JAERI-Review-2000-028.pdf:14.37MB

no abstracts in English

JAEA Reports

Radiation shielding safety guidebook; Elementary volume

JAERI-Tech 94-036, 226 Pages, 1994/12

JAERI-Tech-94-036.pdf:6.38MB

no abstracts in English

Journal Articles

LISA Package user guide, Part 2: LISA(Long Term Isolation Safety Assessment) program description and user guide

P.Prado*; A.Saltelli*; Homma, Toshimitsu

EUR-13923, 47 Pages, 1992/00

no abstracts in English

Journal Articles

Post-dryout heat transfer of high-pressure steam-water two-phase flow in single rod channel and multi rod bundle

Koizumi, Yasuo; ; ; Tasaka, Kanji

Nucl.Eng.Des., 99, p.157 - 165, 1987/00

 Times Cited Count:10 Percentile:70.03(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Reactor Physics Characteristics of the NSRR(Nuclear Safety Research Reactor)

; Inabe, Teruo;

Nihon Genshiryoku Gakkai-Shi, 17(6), p.314 - 321, 1975/06

no abstracts in English

Journal Articles

RELAP-2 code analysis on loss-of-coolant accidents in BWR simulator pressure vessel-ROSA

Nihon Genshiryoku Gakkai-Shi, 15(8), p.562 - 568, 1973/08

no abstracts in English

14 (Records 1-14 displayed on this page)
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