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.

The HTTR project as the world leader of HTGR research and development

Shiozawa, Shusaku; Komori, Yoshihiro; Ogawa, Masuro

Nihon Genshiryoku Gakkai-Shi, 47(5), p.342 - 349, 2005/05

http://ci.nii.ac.jp/naid/10014336574

For the purpose to extend high temperature nuclear heat application, JAERI constructed the HTTR, High Temperature Engineering Test Reactor, and has carried out research and development of high temperature gas cooled reactor system aiming at high efficiency power generation and hydrogen production. This paper explains the history, main results, present status of research and development of HTTR project, international cooperation of research and development of HTGR and future plan aiming at development of Japanese original future HTGR-Hydrogen production system. This paper includes results from the study, which is entrusted from Ministry of Education, Culture, Sports, Science and Technology of Japan.

Report on the Status and Future Upgrades of the Facilities and Instruments in the JRR-3

Subcommittee for Neutron Beam Utilization; Status and Future Upgrades of the Facilities and Instruments

JAERI-Review 2003-037, 88 Pages, 2004/02

JAERI-Review-2003-037.pdf:6.98MB

The refurbished JRR-3 reached critical in March 1990, and the facilities were opened to the general user program in June 1991. Since then the improved specification and the increase of the beam flux of JRR-3 made it recognized as one of the top four research reactors in the world. Despite the ten fruitful years of achievements in research activities performed at JRR-3, it is indispensable to continuously upgrade and improve research facilities in order to maintain our standard of excellence in the research activities. It is also important that the high intensity proton accelerator project (J-PARC project) is progressing in the same JAERI site. Under these circumstances surrounding the JRR-3 facility, a task force under the neutron beam utilization committee was formed in 2001 and assigned to recommend the necessary upgrade and improvements of reactor facilities as well as neutron scattering instruments in JRR-3. This report summarizes analysis and discussions carried out in the task force during these two years, and describes recommendations from the task force.

Thermal-hydraulic research on future reactor systems in the ROSA program at JAERI

Yonomoto, Taisuke; Otsu, Iwao; Svetlov, S.*

Proceedings of 3rd Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-3), p.521 - 528, 2002/00

A research project is being conducted at the Japan Atomic Energy Research Institute on thermal hydraulics for the future reactor systems. The present paper provides the belief description of the project, followed by two recent topics: the natural circulation in the PWR loop and the condensation heat transfer for a passive cooling system. For the first topic, we discuss the importance of the modeling of the nonuniform flow behavior among SG U-tubes for the assessment of the long-term decay heat removal systems relying on the SG secondary side cooling. Such a system is planned to be used in APWR+, a Japanese next-generation PWR. The condensation heat transfer was investigated using the data obtained at the SPOT test facility in Russia. The results have shown that the measured heat transfer rates on the inner surface of the tube consisting of several bends and short straight sections can be predicted using the existing correlations with the accuracy of several percentage, although the correlations are based typically on the data taken using relatively long straight tube.

Study on core physics characteristics of high burnup full MOX PWR core, 2

Kugo, Teruhiko; Okubo, Tsutomu; *

JAERI-Research 99-057, p.29 - 0, 1999/09

JAERI-Research-99-057.pdf:1.77MB

no abstracts in English

Study on nuclear physics of high burnup full MOX PWR core

Kugo, Teruhiko; Shimada, Shoichiro*; Okubo, Tsutomu; Ochiai, Masaaki

JAERI-Research 98-059, 40 Pages, 1998/10

JAERI-Research-98-059.pdf:1.73MB

no abstracts in English

Present status and activities of High energy nuclear data evaluation; For future radiation utilization facilities

Fukahori, Tokio; Mukaiyama, Takehiko; Oyama, Yukio; Chiba, Satoshi; Takada, Hiroshi; Maekawa, Hiroshi; Shibata, Tokushi*; Nakamura, Takashi*; *; *; et al.

Nihon Genshiryoku Gakkai-Shi, 40(1), p.3 - 28, 1998/00

https://doi.org/10.3327/jaesj.40.3

no abstracts in English

Proceedings of the Third Asian Symposium on Research Reactor; November 1114,1991,Sunpia Hitachi,Hitachi-shi,Ibaraki-ken,Japan

JAERI-M 92-028, 657 Pages, 1992/03

JAERI-M-92-028.pdf:23.0MB

no abstracts in English

Generation of radioactive wastes and management

Nakamura, Haruto

JAERI-M 89-057, 19 Pages, 1989/05

JAERI-M-89-057.pdf:0.92MB

no abstracts in English

Current trend and future prospect of nuclear instruments in industrial radioisotope applications

Radioisotopes, 33(2), p.100 - 108, 1984/00

https://doi.org/10.3769/radioisotopes.33.2_100

no abstracts in English

Perspectives of nuclear data activities from past to future

Okajima, Shigeaki

no journal, , 

For nuclear data activities, the presenter will look back on the basis of his career and will think about the importance in future activities.