COMPUTATIONAL BENCHMARK FOR FUEL ASSEMBLY OF VVER-1000 USING THE MONTE CARLO SERPENT CODE

被引：2
|
作者：
Galchenko, Vitaliy V. [1 ]
Shlapak, Ihor [1 ]
Gulik, Volodymyr [1 ,2 ]
机构：
[1] RPA Impulse, Kiev, Ukraine
[2] Inst Safety Problems Nucl Power Plants, Kiev, Ukraine
来源：
NUCLEAR TECHNOLOGY & RADIATION PROTECTION | 2018年 / 33卷 / 01期
关键词：
VVER-1000; Monte Carlo method; reactor calculation; Serpent code; REACTOR; CORE;
D O I：
10.2298/NTRP1801024G
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
The use of a new Monte Carlo Serpent code for the calculation of water-cooled reactors is presented and a calculation scheme of the fuel assembly for VVER-1000 reactors developed. The calculation of neutron-physical characteristics for the fuel assembly of VVER-1000 is carried out for different states and the results obtained by the Serpent model compared with the results of other reactor codes. The analyses of these results are presented in the paper submitted here. Based on this article, the Monte Carlo Serpent code could be used for neutron-physical calculations of VVER-1000 reactors.
引用
收藏
页码：24 / 30
页数：7
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