Utilization of VR-1 reactor for verification of the neutronic calculations

被引:0
|
作者
Rataj, Jan [1 ]
Huml, Ondrej [1 ]
机构
[1] Ceske Vysoke Uceni Tech Praze, Fak Jaderna & Fyzikalne Inzenyrska, Katedra Jadernych Reaktoru, Prague 18000 8, Czech Republic
关键词
Training Reactor VR-1; MCNP; Neutronic Calculation; Verification;
D O I
暂无
中图分类号
TE [石油、天然气工业]; TK [能源与动力工程];
学科分类号
0807 ; 0820 ;
摘要
The paper presents basic information about the verification process of MCNP code at VR-1 training reactor. Department of Nuclear Reactors, Czech Technical University in Prague, as the operator of VR-1 reactor, made detail MCNP model of this experimental facility. The model was refined during the verification process and it was also determined the precession in the case of VR-1 reactor critical state prediction by MCNP code. Based on the verification process, the MCNP code was authorized by State Office for Nuclear Safety for neutronic calculations of VR-1 reactor. The experience of the process will be used for the new neutronic calculations code development and its verification.
引用
收藏
页码:1225 / 1228
页数:4
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