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Nishihara, Kenji
JAEA-Data/Code 2020-005, 48 Pages, 2020/07
JAEA-Data-Code-2020-005.pdf:2.95MB
JAEA-Data-Code-2020-005-appendix(CD-ROM).zip:3.62MB
In order to discuss the technological development and human resource development necessary for the future nuclear fuel cycle, various quantitative analyzes were conducted assuming a wide range of future nuclear power generation scenarios. In the evaluation of quantities, the future power generation of LWR and fast reactor, the amount of spent fuel reprocessing, etc. were assumed, and the amount of uranium demand, the accumulation of spent fuel, plutonium, vitrified waste etc. were estimated.
Nakajima, Hayato; Ikenoya, Kazuhiko*; Onuki, Kaoru; Shimizu, Saburo
Kagaku Kogaku Rombunshu, 24(2), p.352 - 355, 1998/00
Times Cited Count：49 Percentile：86.77(Engineering, Chemical)no abstracts in English
*
JAERI-M 8063, 60 Pages, 1979/01
no abstracts in English
Tateno, Haruka; Sato, Takumi; Tsubata, Yasuhiro; Hayashi, Hirokazu
no journal, ,
Japan Atomic Energy Agency has been pursuing research and development on partitioning and transmutation of minor actinides (MAs) by accelerator-driven system (ADS) using uranium-free nitride fuel. The target transmutation ratio of 99% MAs can be achieved if 99.9% of MAs in the spent fuel are recovered in reprocessing. From the point of view of neutronics design, the weight ratio of rare-earths against MAs in the refabricated fuel should be 5.0% or less. In this study, we calculated the material balance in the pyro-reprocessing of nitride fuel to evaluate the processing conditions to meet the above-mentioned requirements.
