Study the neutronic analysis and burnup for BWR fueled with hydride fuel using MCNPX code

被引：6
|
作者：
Galahom, A. Abdelghafar [1 ]
Bashter, I. I. [2 ]
Aziz, Moustafa [3 ]
机构：
[1] Higher Technol Inst, Cairo, Egypt
[2] Zagazig Univ, Fac Sci, Dept Phys, Zagazig, Egypt
[3] Nucl Regulatory Commiss & Radiol Regulatory, Nasr City, Egypt
来源：
PROGRESS IN NUCLEAR ENERGY | 2014年 / 77卷
关键词：
BWR; MCNPX; Hydride fuel; Neutronic analysis; UZrH1.6; UThH2;
D O I：
10.1016/j.pnucene.2014.06.008
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：
This work presents the neutronic characteristics of advanced boiling water reactor (BWR) which fueled with hydride fuel. MCNPX Computer code based on Mont Carlo Method, is used to design a three dimensional model for BWR fuel assembly in a typical operating temperature and pressure conditions. A test case was compared with a benchmark problem and good agreement was found. This model is used to determine attainable discharge burnup, pin-by-pin power distribution, axial power distribution and reactivity effect of voiding. It is found that hydride fuel bundle design can be simplified by reducing the volume of water in-between the fuel bundles. The increase in the number of fuel rods per given core volume enables an increase in the BWR power density relative to oxide fueled core design. (C) 2014 Elsevier Ltd. All rights reserved.
引用
收藏
页码：65 / 71
页数：7
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