| Issue |
EPJ Web Conf.
Volume 239, 2020
ND 2019: International Conference on Nuclear Data for Science and Technology
|
|
|---|---|---|
| Article Number | 19005 | |
| Number of page(s) | 3 | |
| Section | Validation of Evaluated Data | |
| DOI | https://doi.org/10.1051/epjconf/202023919005 | |
| Published online | 30 September 2020 | |
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.
Current usage metrics show cumulative count of Article Views (full-text article views including HTML views, PDF and ePub downloads, according to the available data) and Abstracts Views on Vision4Press platform.
Data correspond to usage on the plateform after 2015. The current usage metrics is available 48-96 hours after online publication and is updated daily on week days.
Initial download of the metrics may take a while.