Comparative validation of Monte Carlo codes for the conversion of a research reactor

被引：12
|
作者：
Alferov, V. P. [1 ]
Radaev, A. I. [1 ]
Shchurovskaya, M. V. [1 ]
Tikhomirov, G. V. [1 ]
Hanan, N. A. [2 ]
van Heerden, F. A. [3 ]
机构：
[1] Natl Res Nucl Univ MEPhI, Moscow Engn Phys Inst, Moscow 115409, Russia
[2] Argonne Natl Lab, Nucl Engn Div, GTRI Program, Argonne, IL 60439 USA
[3] South African Nucl Energy Corp Necsa, Res & Dev, ZA-0001 Pretoria, South Africa
来源：
ANNALS OF NUCLEAR ENERGY | 2015年 / 77卷
关键词：
Research reactor; LEU fuel; Monte Carlo codes; Validation of neutronics codes;
D O I：
10.1016/j.anucene.2014.11.032
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 paper presents the calculation results of the set of test problems for a research reactor with a tube-type low enriched uranium (LEU, 19.7 w/o, U-9%Mo) fuel and oxide high enriched uranium (HEU, 90 w/o) fuel, a light water moderator, and a beryllium reflector. The static cases and the depletion problem were examined. Calculations were performed using continuous energy Monte Carlo codes: MCNP (+MCREB for burnup calculation), MCU-PTR, and SERPENT 2. The impact of the cross-section libraries used for a particular problem on the calculated results was investigated. (C) 2014 Elsevier Ltd. All rights reserved.
引用
收藏
页码：273 / 280
页数：8
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