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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

Effects of $$alpha$$-radiation on a direct disposal system for spent nuclear fuel, 1 Review of research into the effects of $$alpha$$-radiation on the spent nuclear fuel, canisters and outside canisters

Kitamura, Akira; Takase, Hiroyasu*

Journal of Nuclear Science and Technology, 53(1), p.1 - 18, 2016/01

 Times Cited Count:1 Percentile:89.58(Nuclear Science & Technology)

Not only geological disposal of vitrified waste generated by spent fuel (SF) reprocessing, but also the possibility of disposing of SF itself in deep geological strata (hereinafter "direct disposal of SF") may be considered in the Japanese geological disposal program. In the case of direct disposal of SF, the radioactivity of the waste is higher and the potential effects of the radiation are greater. Specific examples of the possible effects of radiation include: increased amounts of canister corrosion; generation of oxidizing chemical species in conjunction with radiation degradation of groundwater and accompanying oxidation of reducing groundwater; and increase in the dissolution rate and the solubility of SF. Focusing especially on the effects of $$alpha$$-radiation in safety assessment, this study has reviewed research into the effects of $$alpha$$-radiation on the spent nuclear fuel, canisters and outside canisters.

Journal Articles

Effects of $$alpha$$-radiation on a direct disposal system for spent nuclear fuel, 2; Review of research into safety assessments of direct disposal of spent nuclear fuel in Europe and North America

Kitamura, Akira; Takase, Hiroyasu*; Metcalfe, R.*; Penfold, J.*

Journal of Nuclear Science and Technology, 53(1), p.19 - 33, 2016/01

 Times Cited Count:1 Percentile:89.58(Nuclear Science & Technology)

Not only geological disposal of vitrified waste generated by spent fuel (SF) reprocessing, but also the possibility of disposing of SF itself in deep geological strata (hereinafter "direct disposal of SF") may be considered in the Japanese geological disposal program. In the case of direct disposal of SF, the radioactivity of the waste is higher and the potential effects of the radiation are greater. Specific examples of the possible effects of radiation include: increased amounts of canister corrosion; generation of oxidizing chemical species in conjunction with radiation degradation of groundwater and accompanying oxidation of reducing groundwater; and increase in the dissolution rate and the solubility of SF. Therefore, the influences of radiation, which are not expected to be significant in the case of geological disposal of vitrified waste, must be considered in safety assessments for direct disposal of SF. Focusing especially on the effects of $$alpha$$-radiation in safety assessment, this study has reviewed safety assessments in countries other than Japan that are planning direct disposal of SF. The review has identified issues relevant to safety assessment for the direct disposal of SF in Japan.

JAEA Reports

Report of the summative evaluation by the Advisory Committee on Nuclear Safety Research

Research Evaluation Committee

JAERI-Review 2005-018, 45 Pages, 2005/03

JAERI-Review-2005-018.pdf:4.39MB

no abstracts in English

JAEA Reports

Proceedings of 2nd JAERI-JNC Joint Conference on Nuclear Safety Research; February 6, 2004, Tokyo

Secretariat of Second JAERI-JNC Joint Conference on Nuclear Safety Research

JAERI-Conf 2004-013, 97 Pages, 2004/08

JAERI-Conf-2004-013.pdf:18.89MB

no abstracts in English

JAEA Reports

Proceedings of JAERI-JNC Joint Conference on Nuclear Safety Research; March 7, 2003, Tokyo

Secretariat of JAERI-JNC Joint Conference on Nuclear Safety Research

JAERI-Conf 2003-013, 110 Pages, 2003/08

JAERI-Conf-2003-013.pdf:10.97MB

no abstracts in English

JAEA Reports

Proceedings of the International Symposium NUCEF 2001; Scientific Bases for Criticality Safety, Separation Process and Waste Disposal

NUCEF 2001 Symposium Working Group

JAERI-Conf 2002-004, 714 Pages, 2002/03

JAERI-Conf-2002-004.pdf:69.13MB

This volume contains 94 papers presented at the 3rd NUCEF International Symposium NUCEF 2001 held on October 31 - November 2, 2001, in Tokai, Japan, following the 1st symposium NUCEF'95 (Proceedings: JAERI-Conf 96-003) and the 2nd symposium NUCEF'98 (Proceedings: JAERI-Conf 99-004). The theme of this symposium was " Scientific Basis for Criticality Safety, Separation Process and Waste Disposal". The papers were presented in oral and poster sessions on following research fields: (1) Separation Process, (2) TRU Chemistry, (3) Radioactive Waste Disposal, (4) Criticality Safety.

Journal Articles

A Proposal to asian countries with operating research reactors for making nuclear criticality safety benchmark evaluations

Komuro, Yuichi

Journal of Nuclear Science and Technology, 37(6), p.548 - 554, 2000/06

no abstracts in English

Journal Articles

Major topics of LWR safety research in Japan

Ichikawa, Michio; Kosaka, Atsuo;

Proc. of the 9th Pacific Basin Nuclear Conf., Vol. 2, 0, p.583 - 588, 1994/00

no abstracts in English

JAEA Reports

Progress Report of Department ofF Chemistry

JAERI-M 85-213, 378 Pages, 1986/02

JAERI-M-85-213.pdf:9.65MB

no abstracts in English

Journal Articles

A Review of safety aspects of nuclear power plants in Japan

Ando, Yoshio*; *; ; ; ; *

Proc.Fourth Int.Conf.Peaceful Uses Atomic Energy, 3, 3, p.279 - 295, 1972/00

no abstracts in English

Oral presentation

Effects of $$alpha$$-radiation on a disposal of spent nuclear fuel

Kitamura, Akira

no journal, , 

The Japanese geological disposal program has started researching disposal of spent nuclear fuel (SF) in deep geological strata (hereafter "direct disposal of SF") as an alternative management option other reprocessing followed by vitrification and geological disposal of high-level radioactive waste. In the case of direct disposal of SF, specific examples of the possible effects of radiation include: generation of oxidizing chemical species in conjunction with decomposition of groundwater and accompanying oxidation of reducing groundwater; and increase in the dissolution rate of SF and the solubility of radionuclides. Focusing especially on the effects of $$alpha$$-radiation in safety assessment, this study has reviewed research into the effects of $$alpha$$-radiation on the spent nuclear fuel, canisters and environment outside the canisters, and safety assessments in countries other than Japan that are planning direct disposal of SF. It was found that the effects of $$alpha$$-radiation on SF disposal are not significant due to suppression of water radiolysis by hydrogen gas generated from canister corrosion according to the latest research.

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