Methodologies to determine the pu content of spent fuel assemblies for input nuclear material accountancy of pyroprocessing

Hee-Sung Shin; Young-Soo Kim; Ho-Dong Kim; Tae-Je Kwon; Tae-Hoon Lee

논문 상세보기

Methodologies to determine the pu content of spent fuel assemblies for input nuclear material accountancy of pyroprocessing

Tae-Hoon Lee, Tae-Je Kwon, Hee-Sung Shin, Young-Soo Kim, Ho-Dong Kim

언어ENG
URLhttps://db.koreascholar.com/Article/Detail/191697

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한국방사성폐기물학회 학술논문요약집 (Abstracts of Proceedings of the Korean Radioactive Wasts Society)

Vol.9 No.2 (2011.10)
pp.123-124

한국방사성폐기물학회 (Korean Radioactive Waste Society)

1. Introduction 2. Methods 2.1 True amounts of elements of a spent fuel assembly 2.2 Average bumup method 2.3 Neutron emission vs. PU method 3. Conclusions References

저자

Hee-Sung Shin(Korea Atomic Energy Research Institute)
Young-Soo Kim(Korea Atomic Energy Research Institute)
Ho-Dong Kim(Korea Atomic Energy Research Institute)
Tae-Je Kwon(KEPCO Nuclear Fuel)
Tae-Hoon Lee(Korea Atomic Energy Research Institute)

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