Research activities on nuclear reactor physics and thermal-hydraulics in Japan after Fukushima-Daiichi accident
- 1. Hokkaido University, Graduate School of Engineering, Sapporo, Hokkaido (Japan)
Description
Research and development in nuclear reactor physics and thermal-hydraulics continue to be vital parts of nuclear science and technology in Japan. The Fukushima accident not only brought tremendous change in public attitudes towards nuclear engineering and technology, but also had huge influence towards the research and development culture of scientific communities in Japan. After the Fukushima accident, thorough accident reviews were completed by independent committees, namely, Tokyo Electric Power Company (TEPCO), the Japanese government, the Diet of Japan, the Rebuild Japan Initiative Foundation, and the Nuclear and Industrial Safety Agency. Reactor physics and thermal-hydraulics divisions of Atomic Energy Society of Japan (AESJ) also issued the roadmaps after the accident. As a result, lessons learned from the accident were made clear, and a number of new research activities were initiated. The present paper reviews ongoing nuclear engineering research activities in Japanese institutes, universities, and corporations, focusing on the areas in reactor physics and thermal-hydraulics since the Fukushima accident to the present date. (author)
Availability note (English)
Available from http://dx.doi.org/10.1080/00223131.2017.1417177Additional details
Identifiers
Publishing Information
- Journal Title
- Journal of Nuclear Science and Technology (Tokyo) (Online)
- Journal Volume
- 55
- Journal Issue
- 6
- Journal Page Range
- p. 575-598
- ISSN
- 1881-1248
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 49088015
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Descriptors DEI
- COMPUTER CODES; CRITICALITY; FISSION PRODUCT RELEASE; FISSION PRODUCTS; FUEL STORAGE POOLS; FUKUSHIMA DAIICHI NUCLEAR POWER STATION; GAMMA SPECTROSCOPY; MELTDOWN; MONTE CARLO METHOD; NEUTRAL-PARTICLE TRANSPORT; NUCLEAR ENGINEERING; NUCLEAR POWER PLANTS; REACTOR CORES; REVIEWS; THERMAL HYDRAULICS
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; CALCULATION METHODS; DOCUMENT TYPES; ENGINEERING; FLUID MECHANICS; HYDRAULICS; ISOTOPES; MATERIALS; MECHANICS; NUCLEAR FACILITIES; POWER PLANTS; RADIATION TRANSPORT; RADIOACTIVE MATERIALS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR SITES; SEVERE ACCIDENTS; SPECTROSCOPY; THERMAL POWER PLANTS
Optional Information
- Notes
- 234 refs., 6 figs.