Development and application of a safety analysis code for...

Annals of Nuclear Energy 2015 / 07 Vol. 81

Development and application of a safety analysis code for small Lead cooled Fast Reactor SVBR 75/100

Guo, Chao, Lu, Daogang, Zhang, Xun, Sui, Danting
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Volume:
81
Language:
english
Journal:
Annals of Nuclear Energy
DOI:
10.1016/j.anucene.2015.03.021
Date:
July, 2015
File:
PDF, 2.74 MB
english, 2015
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