Feedback on Neutron Capture Cross Sections of 238pu and 241am from Analyses of Measured Isotopic Compositions of Irradiated LWR Fuels and MOX Core Physics Experiments
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY（2016）
关键词
MOX fuel,LWR,Pu-238,Am-241,neutron capture cross section,JEFF-3.2,JENDL-4.0,irradiated fuel isotopic composition,neutron multiplication factor,MOX core physics experiment
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