https://doi.org/10.1051/epjconf/202023919005
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: 18200228211@163.com
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
This is an Open Access article distributed under the terms of the Creative Commons Attribution License 4.0, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
