Effects of different nuclear evaluation data on the RMC keff calculation
1 Nuclear Power Institute of China, Cheng Du, China
2 Science Technology on Reactor System Design Technology Laboratory, Cheng Du, China
* Corresponding author: firstname.lastname@example.org
Published online: 30 September 2020
Neutron cross section data is the basis of nuclear reactor physical calculation and has a decisive influence on the accuracy of calculation results. AFA3Gassemble is widely used in nuclear power plants. CENACE is an ACE format multiple-temperature continuous energy cross section library that developed by China Nuclear Data Centre. In this paper, we calculated the AFA3G assemble by RMC.We respectively used ENDF6.8/, ENDF/7 and CENACE data for calculation. The impact of nuclear data on RMC calculation is studied by comparing the results of different nuclear data.
© The Authors, published by EDP Sciences, 2020
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