期刊名称:Bulletin of the Institute of Heat Engineering
印刷版ISSN:2083-4187
出版年度:2015
卷号:94
期号:5
页码:69-76
语种:English
出版社:Warsaw University of Technology
摘要:The aim of this study was to analyze the accuracy of neutron-physical calculations made using the so far used and alternative computational model of basic cell component of MARIA reactor core. For this purpose, an analysis of the accuracy of the calculation of the neutron flux and the effective multiplication factor by an alternative and existing computational model was done. The results were compared with the exact model of the core primary cell prepared using the MCNP computational code.
关键词:nuclear reactor;beryllium blocks;MARIA reactor;computational model of reactor