Carbide Fuel
作者： A.K. Sengupta , R. Agarwal , H.S. Kamath
DOI: 10.1016/B978-0-08-056033-5.00051-3
关键词:
摘要: Uranium–plutonium-mixed carbide fuel is considered an advanced for liquid-metal-cooled fast breeder reactor or gas-cooled reactor. The development of was initiated all over the world as early in 1960s. However, to date, use has been limited capsule test pin irradiation except a small reactor: India which operation with plutonium-rich (Pu 30%) uranium–plutonium-mixed driver fuel. present review summarizes different aspects cycle, includes both front end and back end. Effort made include most recent literature information that will be helpful understanding cycle. chapter broadly classified into sections, namely thermophysical thermochemical properties, fabrication procedure, in-pile performance, reprocessing, waste management. effects plutonium content on fabrication, management have also discussed.
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