Advances in nuclear fuel technology. 3. Development of advanced nuclear fuel recycle systems
Creators
- 1. Toshiba Corp., Kawasaki, Kanagawa (Japan)
- 2. Japan Nuclear Cycle Development Inst., Tokai, Ibaraki (Japan)
- 3. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Description
Fast breeder reactor (FBR) cycle technology has a technical characteristics flexibly easy to apply to diverse fuel compositions such as plutonium, minor actinides, and so on and fuel configurations. By using this characteristics, various feasibilities on effective application of uranium resources based on breeding of uranium of plutonium for original mission of FBR, contribution to radioactive wastes problems based on amounts reduction of transuranium elements (TRU) in high level radioactive wastes, upgrading of nuclear diffusion resistance, extremely upgrading of economical efficiency, and so on. In this paper, were introduced from these viewpoints, on practice strategy survey study on FBR cycle performed by cooperation of the Japan Nuclear Cycle Development Institute (JNC) with electric business companies and so on, and on technical development on advanced nuclear fuel recycle systems carried out at the Central Research Institute of Electric Power Industry, Japan Atomic Energy Research Institute, and so on. Here were explained under a vision on new type of fuels such as nitride fuels, metal fuels, and so on as well as oxide fuels, a new recycle system making possible to use actinides except uranium and plutonium, an 'advanced nuclear fuel cycle technology', containing improvement of conventional wet Purex method reprocessing technology, fuel manufacturing technology, and so on. (G.K.)
Availability note (English)
Available from DOI: https://doi.org/10.3327/jaesj.44.593Abstract (Japanese)
原子力の開発利用に当たっては、安全性、経済性等の一層の向上のみならず、環境への負荷の低減、核不拡散への配慮など、将来の社会の多様なニーズに対応できる技術の可能性を追求し、技術の選択の幅を広げていくことが重要である。このため、酸化物燃料だけでなく、窒化物燃料、金属燃料等の新型燃料も視野に入れ、ウランやプルトニウム以外のアクチニドも利用することを可能にする新たなリサイクルシステム、「先進的核燃料リサイクル技術」について、従来の湿式ピューレックス法再処理技術の改良、燃料製造技術等について解説する。(日本)Additional details
Additional titles
- Original title (Japanese)
- 「核燃料技術高度化の現状と展望」シリーズ3 先進的核燃料リサイクル技術開発
Identifiers
- DOI
- 10.3327/jaesj.44.593;
Publishing Information
- Journal Title
- Nippon Genshiryoku Gakkai-Shi
- Journal Volume
- 44
- Journal Issue
- 8
- Journal Page Range
- p. 593-599
- ISSN
- 0004-7120
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 54066200
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Descriptors DEI
- COST; FUEL CYCLE; FUEL MANAGEMENT; FUEL PELLETS; NUCLEAR FUELS; PROCESS CONTROL; PRODUCTION; PUREX PROCESS; RESEARCH PROGRAMS; SAFETY; URANIUM DIOXIDE; URANIUM NITRIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; CONTROL; ENERGY SOURCES; FUELS; MANAGEMENT; MATERIALS; NITRIDES; NITROGEN COMPOUNDS; NUCLEAR MATERIALS MANAGEMENT; OXIDES; OXYGEN COMPOUNDS; PELLETS; PNICTIDES; REACTOR MATERIALS; REPROCESSING; SEPARATION PROCESSES; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Notes
- This record replaces 33062439