A comparative neutronic study of the standard HEU core and various potential LEU alternatives for a typical MNSR system

被引：11

作者：

Waqar, Sadaf ^{[1
]}

Mirza, Sikander M. ^{[1
]}

Mirza, Nasir M. ^{[1
]}

Asad, Tariq ^{[1
]}

机构：

[1] Pakistan Inst Nucl Sci & Technol, Dept Appl Math & Phys, Islamabad 45650, Pakistan

来源：

NUCLEAR ENGINEERING AND DESIGN | 2008年 / 238卷 / 09期

关键词：

D O I：

10.1016/j.nucengdes.2008.03.016

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：

A comparative study has been performed for neutronic analysis of highly enriched in uranium (HEU) and potential low enriched in uranium (LEU) cores for the Pakistan Research Reactor-2 (PARR-2) taken as a typical miniature neutron source reactor (MNSR) system. The group constant generation has been carried out using transport theory code WIMS-D4 and a detailed five-group RZ-model has been used in the CITATION code for multigroup diffusion theory analysis. The neutronic analysis of the 90% HEU reference and potential LEU alternative: UO2, U3Si2 and U9Mo, cores has been carried out yielding 11%, 20.7% and 14.25% enrichments with corresponding values of excess reactivity: 4.33, 4.30 and 4.07 mk. These results have been found in good agreement with recently reported Monte Carlo-based transport theory calculations. The diffusion theory-based calculated values of thermal flux profiles for axial as well as for radial directions have been found to agree well with the corresponding experimental measurements. The UO2-based LEU core has been found having flux spectrum closest to the reference core while U9Mo core has significantly harder flux spectrum at irradiation site. (C) 2008 Elsevier B.V. All rights reserved.

引用

页码：2302 / 2307

页数：6

共 11 条

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