On the performance of ENDF/B-VII.0 data for fast neutron fluence calculations

被引：5
|
作者：
Vasiliev, Alexander [1 ]
Kolbe, Edwin [1 ]
Ferroukhi, Hakim [1 ]
Zimmermann, Martin A. [1 ]
Chawla, Rakesh [1 ,2 ]
机构：
[1] Paul Scherrer Inst, Lab Reactor Phys & Syst Behav, CH-5232 Villigen, Switzerland
[2] Ecole Polytech Fed Lausanne, CH-1015 Lausanne, Switzerland
来源：
ANNALS OF NUCLEAR ENERGY | 2008年 / 35卷 / 12期
关键词：
D O I：
10.1016/j.anucene.2008.07.009
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 newest release of the Evaluated Nuclear Data File, ENDF/B-VII.0, has recently become available, along with the announcement of its significant advances over previous versions. The older ENDF/B releases, however, have been assessed for numerous applications in the past and, as such, currently find wide application in the nuclear industry. An analysis of the influence of the recent upgrade in the data file is thus needed with respect to specific practical applications. The present technical note addresses the effects of modifications of the neutron cross-sections in the ENDF/B-VII.0 library, relative to the preceding ENDF/B-VI.8 release, on calculations of the fast neutron fluence accumulated in a PWR reactor pressure vessel. which is of direct relevance for the licensing and safe operation of nuclear power plants. (C) 2008 Elsevier Ltd. All rights reserved.
引用
收藏
页码：2432 / 2435
页数：4
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