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.
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页码:496 / 499
页数:4
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