Reducing enrichment of fuel for research reactors
Creators
- 1. Kyoto Univ., Kumatori, Osaka (Japan). Research Reactor Inst.
Description
In research reactors, highly enriched uranium (HEU) is used as fuel for their purposes of operation. However, the United States strongly required in 1977 that these HEU should be replaced by low enrichment uranium (LEU) of 20% or less, or even in unavoidable cases, it should be replaced by medium enrichment uranium (MEU). INFCE (International Nuclear Fuel Cycle Evaluation) which started its activity just at that time decided to discuss this problem in the research reactor group of No. 8 sectional committee. Japan has been able to forward the work, taking a leading part in the international opinion because she has taken the countermeasures quickly. INFCE investigated the problem along the lines of policy that the possibility of reducing the degree of enrichment should be limited to the degree in which the core structures and equipments of research reactors will be modified as little as possible, and the change of fuel element geometry will be done within the permissible thermohydrodynamic capacity, and concluded that it might be possible in near future to reduce the degree of enrichment to about 45% MEU, while the reduction to 20% LEU might require considerable research, development and verification. On the other hand, the joint researches by Kyoto University and ANL (Argonne National Laboratory) and by Japan Atomic Energy Research Institute and ANL are being continued. IAEA has edited the guidebook (IAEA-TECDOC-233) for reducing the degree of enrichment for developing countries. (Wakatsuki, Y.)
Availability note (English)
Available from DOI: https://doi.org/10.3327/jaesj.22.763Abstract (Japanese)
これまで研究炉燃料として、主に90-93%の高濃縮Uが使われていたが、核拡散抵抗力という考え方から、1977年米国政府は高濃縮Uの輸出を制限するという政策を打ち出してきた。わが国を含め、高濃縮Uを米国から輸入している多くの国々は、その対応策に追われた。しかし、INFCEやIAEAなどで討論を重ねるうちに、現在の研究炉は大幅に設計変更をすることなしに、ほぼこれまでの性能を保ちながら、U濃縮度を低減していく見通しがたってきた。本稿では、それらの国際的合意が得られるようになるなどの過程、およびわが国の関係者がそのなかで果してきた役割などを説明し、合わせて濃縮度を低減した場合の研究炉の性能について概説する。 (著者)Additional details
Additional titles
- Original title (Japanese)
- 研究炉用燃料の濃縮度低減化
Identifiers
- DOI
- 10.3327/jaesj.22.763;
Publishing Information
- Journal Title
- Nippon Genshiryoku Gakkai-Shi
- Journal Volume
- 22
- Journal Issue
- 11
- Journal Page Range
- p. 763-768
- ISSN
- 0004-7120
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 53113946
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ENRICHED URANIUM; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; HIGHLY ENRICHED URANIUM; ISOTOPE RATIO; MODERATELY ENRICHED URANIUM; NEUTRON FLUX; RESEARCH REACTORS; SPATIAL DISTRIBUTION
- Descriptors DEC
- ACTINIDES; DIMENSIONLESS NUMBERS; DISTRIBUTION; ELEMENTS; ENRICHED URANIUM; ISOTOPE ENRICHED MATERIALS; MATERIALS; METALS; RADIATION FLUX; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; URANIUM
Optional Information
- Notes
- 3655000; This record replaces 13669493