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JAEA Reports

Direction of future safety research to be conducted by Sector of Nuclear Safety Research and Emergency Preparedness (FY 2021 Edition)

Planning and Co-ordination Office, Sector of Nuclear Safety Research and Emergency Preparedness

JAEA-Review 2021-019, 58 Pages, 2021/11

JAEA-Review-2021-019.pdf:2.26MB

In response to the directives of the 4th medium-to-long-term objectives, Japan Atomic Energy Agency will formulate the 4th medium-to-long-term plan and run its operation according to the plan from the fiscal year 2022. Consequently, the Sector of Nuclear Safety Research and Emergency Preparedness has reviewed the strategies of the safety research for contributing to the demand, "the continuous improvement of nuclear safety and the effectiveness of nuclear disaster prevention". It was also discussed how to proceed the safety research over the medium-to-long-term plan period based on the proposed new strategies. From the viewpoint of developing human resources and maintaining research capabilities in the sector, discussion was made on measures to pass on the knowledge and skills of senior and mid-career researchers to young researchers. The main elements of the proposed strategies are: (1) to efficiently and effectively develop both problem-solving research and advanced or leading research, considering the importance and needs on the nuclear safety and corresponding to regulatory trends and introduction of new technologies, (2) to produce research results of high quality for social implementation, including proactive proposal of measures for enhancing rationality of nuclear safety and regulation by utilizing risk information, and (3) to promote development of human resources and maintenance of technological base through challenging new research subjects. This report summarizes results of the discussion on the medium-to-long-term safety research strategies and the research plans based on the proposed strategies.

JAEA Reports

Effective dose coefficients for internal exposure dose assessment in accordance with ICRP 2007 recommendations (Contract research)

Takahashi, Fumiaki; Manabe, Kentaro; Sato, Kaoru

JAEA-Review 2020-068, 114 Pages, 2021/03

JAEA-Review-2020-068.pdf:2.61MB

Radiation safety regulations have been currently established based on the 1990Recommendation by the International Commission on Radiological Protection (ICRP) in Japan. Meanwhile, ICRP released the 2007 Recommendation that replaces the 1990 Recommendation. Thus, the Radiation Council, which is established under the Nuclear Regulation Authority (NRA), has made discussions to incorporate the purpose of the 2007 Recommendation into Japanese regulations for radiation safety. As ICRP also has published effective dose coefficients for internal exposure assessment in accordance with the 2007recommendation, the technical standards are to be revised for the internal exposure assessment method in Japan. Currently, not all of the effective doses have been published to revise concentration limits for internal exposure protections of workers and public. The published effective dose coefficients are applied to radionuclides which are important in radiation protection for internal exposure of a worker. Thus, we review new effective dose coefficients as well as basic dosimetry models and data based upon Occupational Intakes of Radionuclides (OIR) parts 2, 3 and 4 that have been published from 2016 to 2019 by ICRP. In addition, issues are sorted out to provide information for revision of the technical standards for internal exposure assessment based on the 2007 Recommendations in future.

JAEA Reports

Introduction of a new framework of safety, maintenance and quality management activities in Japan Atomic Energy Agency under the new nuclear regulatory inspection system since FY 2020

Sono, Hiroki; Sukegawa, Kazuhiro; Nomura, Norio; Okuda, Eiichi; Study Team on Safety and Maintenance; Study Team on Quality Management; Task Force on New Nuclear Regulatory Inspection Systems

JAEA-Technology 2020-013, 460 Pages, 2020/11

JAEA-Technology-2020-013.pdf:13.46MB

Japan Atomic Energy Agency (JAEA) has completed the introduction of a new frame work of safety, maintenance and quality management activities under the new acts on the Regulation of nuclear source material, nuclear fuel material and reactors since April 2020, in consideration of variety, specialty and similarity of nuclear facilities of JAEA (Power reactor in the research and development stage, Reprocessing facility, Fabrication facility, Waste treatment facility, Waste burial facility, Research reactor and Nuclear fuel material usage facility). The JAEA task forces on new nuclear regulatory inspection systems prepared new guidelines on (1) Safety and maintenance, (2) Independent inspection, (3) Welding inspection, (4) Free-access response, (5) Performance indicators and (6) Corrective action program for the JAEA's nuclear facilities. New Quality management systems and new Safety regulations were also prepared as a typical pattern of these facilities. JAEA will steadily improve these guidelines, quality management systems and safety regulations, reviewing the official activities under the new regulatory inspection system together with the Nuclear Regulation Authority and other nuclear operators.

Journal Articles

Study on criticality control of fuel debris by Japan Atomic Energy Agency to support Nuclear Regulation Authority of Japan

Tonoike, Kotaro; Yamane, Yuichi; Umeda, Miki; Izawa, Kazuhiko; Sono, Hiroki

Proceedings of International Conference on Nuclear Criticality Safety (ICNC 2015) (DVD-ROM), p.20 - 27, 2015/09

From the viewpoint of safety regulation, criticality control of the fuel debris in the Fukushima Daiichi Nuclear Power Station would be a risk-informed control to mitigate consequences of criticality events, instead of a deterministic control to prevent such events. The Nuclear Regulation Authority of Japan has set up a research and development program to tackle this challenge. The Nuclear Safety Research Center of Japan Atomic Energy Agency, commissioned by the authority, has launched activities such as computations of criticality characteristics of the fuel debris, development of criticality risk assessment method, and preparation of criticality experiments to support them.

Journal Articles

Structure reform and special economic zone in large helium liquifier complex for the 4th generation ERL light source

Minehara, Eisuke

Proceedings of 2nd Annual Meeting of Particle Accelerator Society of Japan and 30th Linear Accelerator Meeting in Japan, p.200 - 201, 2005/07

As the fourth generation energy recovering super-conducting linac (ERL) driven light source is planned to develop and to build as the most advanced national light source facility in Japan, this is a conceptual design work and key components developmental programs including a 200MeV prototype construction. Our existing 4K zero-boil off refrigerator cryogenic and a huge 2K liquefier facility will be combined to make a new hybrid one. Because all cryogenic devices in Japan have been seriously and unnecessarily controlled and affected their safety, maintenance, operation and construction over these several tens years, we will therefore have to cut back excess safety regulation in Japanese domestic high pressure vessel code using a structure reform and special economic zone policy.

Journal Articles

Deuterium effect on the subcritical limit for fissile-to-hydrogen ratio

Okuno, Hiroshi; Akiyama, Hideo*; Mochizuki, Hiroki*

Journal of Nuclear Science and Technology, 40(1), p.57 - 60, 2003/01

 Times Cited Count:1 Percentile:11.39(Nuclear Science & Technology)

Low-level waste (LLW) drums are required to transport as fissile material if the current IAEA's Regulations for the Safe Transport of Radioactive Material are rigorously applied. This problem is a consequence that water contents of concrete in LLW drums contained deuterium (D) in quantities more than 0.1% of fissile material mass, therefore they are not excepted from packages containing fissile material. Consideration of differences in the absorption cross sections of light hydrogen and D shows that the relative increase in the neutron multiplication factor by a presence of D in natural water for hydrogen (H)-moderated systems is not larger than 0.015%. A numerical calculation confirms that the infinite multiplication factor of a mixture of $$^{235}$$U-metal and water in a $$^{235}$$U/H mass ratio of 5% increases proportionally to the D/H atomic ratio, and that its relative increase is less than 0.03% for the D/H atomic ratio of 0.015%. The limiting fissile-to-H mass ratio of 5% in the exception rule is concluded to be applicable to H-moderated systems including D in natural water.

Journal Articles

Criticality safety studies related to advisory material for the IAEA regulations

; *

Proc. of PATRAM'98, 1, p.217 - 223, 1998/00

no abstracts in English

Journal Articles

Near surface disposal of very low level waste generated from reactor decommissioning and related safety requirements

Okoshi, Minoru; Yoshimori, Michiro; Abe, Masayoshi

Planning and Operation of Low Level Waste Disposal Facilities IAEA-SM-341/70, 0(0), p.416 - 425, 1997/00

no abstracts in English

Journal Articles

Int.Conf.on Probabilistic Safety Methodology and Applications

*; Sobajima, Makoto

Nihon Genshiryoku Gakkai-Shi, 38(5), p.369 - 370, 1996/00

no abstracts in English

Journal Articles

Near surface disposal of VLLW from reactor decommissioning and safety requirements

Okoshi, Minoru; Yoshimori, Michiro

Proc. of 3rd Japan-Russia Joint Symp. on Radiation Safety, 0, p.75 - 85, 1995/00

no abstracts in English

Oral presentation

Graded approach for safety of research reactors

Yonomoto, Taisuke; Nakatsuka, Toru; Hirane, Nobuhiko; Tsumura, Takashi

no journal, , 

no abstracts in English

Oral presentation

Initiatives of developing engineering methods for application of graded approach to ensuring safety of research reactors

Nakatsuka, Toru; Tsumura, Takashi; Motome, Yuiko; Amaya, Masaki; Yonomoto, Taisuke

no journal, , 

no abstracts in English

13 (Records 1-13 displayed on this page)
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