MCNP程序用热中子散射数据制作和检验  

Generating and Validation of Thermal Neutron Scattering Library for MCNP

作　　者：陈朝斌[1] 陈义学[2] 胡泽华[1] 王佳[1] 吴军[2] 

机构地区：[1]北京应用物理与计算数学研究所,北京100088 [2]华北电力大学核科学与工程学院,北京102206

出　　处：《原子能科学技术》2010年第11期1335-1340,共6页Atomic Energy Science and Technology

基　　金：国家自然科学基金资助项目(10705011;10875042);北京市科技新星计划资助项目(2007B058);复杂系统可靠性参数灵敏度估计方法研究资助项目(70771014)

摘　　要：基于ENDF/B-Ⅶ.0评价库,以前已陆续研制了可供MCNP程序使用的连续截面库,以及多套多个温度、多组邦达连柯背景截面修正的多群参数库。本文采用NJOY程序以及ENDF/B-Ⅶ.0评价库热散射子库,完成了MCNP程序使用热中子散射数据库S(α,β)的制作和检验。比较了自制库与MCNP自带基于ENDF/B-Ⅵ版热散射数据库(sab2002),对改进较明显的重要介质"轻水中氢"和"重水中氘"给出了分析说明。通过48个基准装置keff计算结果可看出,MCNP程序自带热中子散射库sab2002与自制库thb70计算的keff整体上偏差不大,keff平均偏差约65pcm。A continuous neutron transport library for MCNP and several temperature-dependent multigroup cross section libraries with Bondarenko self-shielded factors based on ENDF/B-Ⅶ.0were generated in former work.In the work the thermal S（α,β） tables for MCNP code were converted from the thermal neutron scattering sublibrary of ENDF/B-Ⅶ.0using NJOY program.The available thermal S（α,β）library named sab2002（from ENDF/B-Ⅵ）released with MCNP were investigated and compared with the self-produced library thb70,and some significant improvements of important medias,such as H in H2O and D in D2O,were presented.Forty-eight critical bench-mark models were selected to calculate the keffusing sab2002and thb70,respectively. The results show that there is a not too much difference（65pcm averagely）between the two libraries.

关 键 词：ENDF/B-Ⅶ.0 热中子散射 MCNP 积分检验 

分 类 号：TL32[核科学技术—核技术及应用]