Prospects of using different clad materials in a material test research reactor - Part 1-The kinetic parameters

被引:4
|
作者
Muhammad, Farhan [1 ]
Majid, Asad [1 ]
机构
[1] Pakistan Inst Engn & Appl Sci, Dept Nucl Engn, Islamabad 45650, Pakistan
关键词
MTR; Excess reactivity; Neutron flux; Prompt neutron generation time; Effective delayed-neutron fraction;
D O I
10.1016/j.pnucene.2008.10.009
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 kinetic parameters of a material test research reactor using stainless steel-316 and zircaloy-4 as clad were calculated. For this purpose, the aluminum clad of an MTR was replaced separately with stainless steel-316 and zircaloy-4. Calculations were carried out to find the core excess reactivity, neutron flux spectrum, prompt neutron generation time and effective delayed-neutron fraction. Nuclear reactor analysis codes including WIMS-D4 and CITATION were employed to carry out these calculations. It was observed that at the beginning of life, the excess reactivity was maximum at 0.054110 Delta k/k when zircaloy-4 was used as clad while it was minimum at -0.365650 Delta k/k when stainless steel-316 was the clad as compared to 0.017945 Delta k/k for aluminum. The thermal neutron flux at the mid of the central flux trap increased by 59.9% and 12.5% for stainless steel and zircaloy-4 clads, respectively, from the flux of the original aluminum clad. The prompt neutron generation time was maximum at 45.36 mu s when stainless steel-316 was the clad while it was minimum at 44.03 mu s for the original aluminum clad. The effective delayed-neutron fraction was maximum at 0.007185 for the original aluminum clad while it was minimum at 0.007078 for stainless steel clad. (C) 2008 Elsevier Ltd. All rights reserved.
引用
收藏
页码:496 / 499
页数:4
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