Moderator temperature effects on reactivity of HEU core of MNSR

被引:5
作者
Ahmad, Siraj-ul-Islam [1 ]
Sahibzada, Tasveer Muhammad [1 ]
机构
[1] Pakistan Inst Engn & Appl Sci, Islamabad 45650, Pakistan
关键词
MNSR; Moderator temperature coefficient; WIMS-D; PRIDE; Cross section libraries; TEST RESEARCH REACTOR; NEUTRON ENERGY-SPECTRUM; CRITICALITY; ACTINIDE;
D O I
10.1016/j.anucene.2012.07.004
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
In this article we report on analyses that were performed to investigate the influence of cross section differences among libraries released by various centers on reactivity of Miniature Neutron Source Reactors. The 3D model of the core was developed with WIMS-D and PRIDE codes and six cross section libraries were used including JENDL-3.2, JEF-2.2, JEFF-3.3, ENDF/B-VI and ENDF/B-VII, and IAEA library. It was observed that all the libraries predict the reactivity within 10%, with IAEA library giving minimum reactivity worth, and JEF-2.2 data library resulted in highest worth. (C) 2012 Elsevier Ltd. All rights reserved.
引用
收藏
页码:207 / 211
页数:5
相关论文
共 21 条
[1]   Influence of evaluated data of fission product poisons on criticality [J].
Ahmad, Ammar ;
Ahmad, Siraj-ul-Islam ;
Ahmad, Nasir ;
Chaudri, Khurrum Saleem ;
Sahibzada, Tasveer Muhammad ;
Ahmad, Masroor .
PROGRESS IN NUCLEAR ENERGY, 2009, 51 (02) :334-338
[2]  
Ahmad S.I., 2009, PRIDE USER MANUAL
[3]   Plutonium build-up credits for a material test research reactor and influence of cross-section differences on actinide production [J].
Ahmad, Siraj Islam ;
Ahmad, Nasir .
NUCLEAR ENGINEERING AND DESIGN, 2006, 236 (24) :2537-2546
[4]   Burnup-dependent core neutronics analysis and calculation of actinide and fission product inventories in discharged fuel of a material test research reactor [J].
Ahmad, Siraj-ul-Islam ;
Ahmad, Nasir .
PROGRESS IN NUCLEAR ENERGY, 2006, 48 (06) :599-616
[5]   Effect of updated WIMSD libraries on neutron energy spectrum at irradiation site of Pakistan Research Reactor-1 using 3D modeling [J].
Ahmad, SUI ;
Ahmad, N .
ANNALS OF NUCLEAR ENERGY, 2005, 32 (05) :521-548
[6]   Effect of new cross-section evaluations on criticality and neutron energy spectrum of a typical material test research reactor [J].
Ahmad, SUI ;
Ahmad, N ;
Aslam, N .
ANNALS OF NUCLEAR ENERGY, 2004, 31 (16) :1867-1881
[7]   Effect of different cross-section data sets on reflectors of a typical material test research reactor [J].
Ahmad, SUL ;
Ahmad, N .
PROGRESS IN NUCLEAR ENERGY, 2006, 48 (02) :155-164
[8]  
Halsall M.J., 1980, SUMMARY WIMS D4 INPU
[9]   APPLICATION OF A DUAL VARIATIONAL FORMULATION TO FINITE-ELEMENT REACTOR CALCULATIONS [J].
HEBERT, A .
ANNALS OF NUCLEAR ENERGY, 1993, 20 (12) :823-845
[10]  
INDC, 1991, COMM NUCL DAT PROGR