Recent research trends of thorium fuel cycle. Fuel cycle with effective non-proliferative properties and other attractive characteristics. Part 2
- 1. Tokyo Univ., Tokyo (Japan)
- 2. Kyoto Univ., Kyoto, Kyoto (Japan)
- 3. Tokyo Inst. of Technology, Tokyo (Japan)
Description
Following a previously published report on thorium fuel cycle from the Atomic Energy Society of Japan in 1980, progress made since then is reviewed focusing of studies in chemical, thermodynamic and mechanical properties of thorium oxides including their behavior under irradiation. Variation of melting point of mixed oxides (Th, Pu)O2 with the thorium oxide/plutonium oxide ratio and thermal conductivity change with temperature (1000 - 1900 K), and some diffusion properties of composing atoms are also described. Fabrication methods of mixed oxide fuel, pellet and particle, are reported. Characteristics of molten salt of thorium fluorides are reported. Possible technologies for reprocessing processes for thorium fuels, as dissolution of thorium oxide by nitric acid solutions, followed by solvent extraction using TBP (THOREX process), including protactinium problem and pyrochemical process, are also reported. Present status for economic assessment for thorium cycle is briefly discussed. (S. Ohno)
Availability note (English)
Available from DOI: https://doi.org/10.3327/jaesj.48.20Abstract (Japanese)
1980年に日本原子力学会から発表されたトリウム燃料サイクルに関する報告書に続き、トリウム混合酸化物燃料の化学的、熱力学的及び機械的特性(照射下挙動)の研究を中心に、それ以降の進展をレビューする。また、混合酸化物(Th、Pu)O2の融点の酸化トリウム/酸化プルトニウム比による変化、熱伝導率の温度による変化(1000-1900K)、及び構成原子の拡散特性についても紹介する。混合酸化物燃料の製造方法として、ペレット及び粒子の製造方法を報告する。トリウムフッ化物溶融塩の特性について報告する。トリウム燃料の再処理技術として、トリウム酸化物を硝酸溶液で溶解し、TBPで溶媒抽出する方法(THOREXプロセス)、プロトアクチニウム問題、乾式再処理プロセスについて報告した。また、トリウムサイクルの経済性評価の現状について簡単に述べる。(日本)Additional details
Additional titles
- Original title (Japanese)
- トリウム燃料サイクルの研究開発と動向 高い核拡散抵抗性と優れた特性を有するトリウム燃料サイクル (第2部)
Identifiers
- DOI
- 10.3327/jaesj.48.20;
Publishing Information
- Journal Title
- Nippon Genshiryoku Gakkai-Shi
- Journal Volume
- 48
- Journal Issue
- 1
- Journal Page Range
- p. 20-34
- ISSN
- 0004-7120
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 54068904
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Descriptors DEI
- COST ESTIMATION; MELTING POINTS; MIXED OXIDE FUELS; MOLTEN SALT FUELS; PHASE DIAGRAMS; PROLIFERATION; PROTACTINIUM; PYROCHEMICAL REPROCESSING; THERMAL CONDUCTIVITY; THOREX PROCESS; THORIUM CYCLE; THORIUM OXIDES; VISION
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDES; CHALCOGENIDES; DIAGRAMS; ELEMENTS; ENERGY SOURCES; FUEL CYCLE; FUELS; INFORMATION; LIQUID FUELS; MATERIALS; METALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; REACTOR MATERIALS; REPROCESSING; SEPARATION PROCESSES; SOLID FUELS; THERMODYNAMIC PROPERTIES; THORIUM COMPOUNDS; TRANSITION TEMPERATURE
Optional Information
- Notes
- 57 refs., 13 figs., 6 tabs.; This record replaces 37048939