Neutron transport-burnup code MCORGS and its application in...

Neutron transport-burnup code MCORGS and its application in fusion fission hybrid blanket conceptual research

Shi, Xue-Ming, Peng, Xian-Jue
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Volume:
44
Language:
english
Journal:
International Journal of Modern Physics: Conference Series
DOI:
10.1142/S2010194516602362
Date:
January, 2016
File:
PDF, 495 KB
english, 2016
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