Calculation and measurement of neutron flux in the VVER-1000 mock-up on the LR-0 research reactor

被引：16
|
作者：
Kost'al, M. [1 ]
Cvachovec, F. [2 ]
Rypar, V. [1 ]
Juricek, V. [1 ]
机构：
[1] Res Ctr Rez Ltd, Husinec Rez 25068, Czech Republic
[2] Univ Def, Brno 66210, Czech Republic
来源：
ANNALS OF NUCLEAR ENERGY | 2012年 / 40卷 / 01期
关键词：
VVER-1000; LR-0; Neutron flux; MCNPX; Nuclear data library; IRON;
D O I：
10.1016/j.anucene.2011.10.003
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 neutron fluence load on a reactor pressure vessel is an important physical quantity affecting material degradation and consequently reliable assessment of pressure vessel integrity and lifetime prolongation beyond designed conditions. This degradation is influenced by mixed neutron-photon source from the core periphery as well as by material parameters of the reactor pressure vessel. Computational procedures and experimental determination of neutron fluxes in the VVER-1000 mock-up internal structures as well as the results achieved are described in this paper. The calculation were performed with the MCNPX code with different nuclear data libraries. Nuclear data were processed using NJOY code. The neutron spectra measurements were performed with a two-parameter stilbene spectrometer. (C) 2011 Elsevier Ltd. All rights reserved.
引用
收藏
页码：25 / 34
页数：10
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