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基于蒙特卡罗抽样的活化中子能谱测量不确定度分析
引用本文:李达,陈达,江新标,朱广宁,张文首,苏春磊,苗亮亮,余小任.基于蒙特卡罗抽样的活化中子能谱测量不确定度分析[J].原子能科学技术,2016,50(12):2249-2255.
作者姓名:李达  陈达  江新标  朱广宁  张文首  苏春磊  苗亮亮  余小任
作者单位:1.西北核技术研究所 强脉冲辐射环境模拟与效应国家重点实验室,陕西 西安710024;2.南京航空航天大学 核科学与工程系,江苏 南京210016
基金项目:国家自然科学基金青年科学基金资助项目(11305127);强脉冲辐射环境模拟与效应国家重点实验室基础研究基金资助项目(SKLIPR1216)
摘    要:不确定度分析是活化法测量中子能谱的关键环节。本文针对SAND-Ⅱ活化中子解谱过程,给出了一种基于先验谱、活化率和截面协方差的中子能谱测量不确定度蒙特卡罗分析方法。首先,建立了基于线性变换的截面协方差抽样方法;然后,利用MCNP计算了误差,使用迭代方法估计了先验谱不确定度;最后,结合活化率的测量不确定度,利用蒙特卡罗抽样算法计算了中子能谱的不确定度。利用锎源自发裂变谱对该方法进行了验证,与传统方法相比,不确定度分析结果更为准确。对西安脉冲堆某次中子能谱测量结果进行了测量不确定度分析,结果表明该方法更具保守性。

关 键 词:中子能谱    不确定度分析    1  MeV等效中子注量    西安脉冲堆

Uncertainty Analysis of Activation Neutron Spectrum Measurement Based on Monte-Carlo Sampling
LI Da,CHEN Da,JIANG Xin-biao,ZHU Guang-ning,ZHANG Wen-shou,SU Chun-lei,MIAO Liang-liang,YU Xiao-ren.Uncertainty Analysis of Activation Neutron Spectrum Measurement Based on Monte-Carlo Sampling[J].Atomic Energy Science and Technology,2016,50(12):2249-2255.
Authors:LI Da  [CHEN Da]  JIANG Xin-biao  ZHU Guang-ning  ZHANG Wen-shou  SU Chun-lei  MIAO Liang-liang  YU Xiao-ren
Affiliation:1.State Key Laboratory of Intense Pulsed Radiation Simulation and Effect, Northwest Institute of Nuclear Technology, Xi’an 710024, China; 2.Department of Nuclear Science and Engineering, Nanjing University of Aeronautics and Astronautics, Nanjing 210016, China
Abstract:The uncertainty analysis is a key link in activation neutron spectrum measure‐ment .According to SAND‐Ⅱ activation neutron spectrum unfolding process ,an uncer‐tainty analysis Monte‐Carlo method of neutron spectrum measurement based on cross‐section covariance ,activation rate and prior spectrum information was presented .First , the sampling method of cross‐section covariance based on linear transformation was built . Then , the error was computed with MCNP , and the uncertainty of prior spectrum was obtained using iteration method .Finally ,combining uncertainty of activa‐tion rate measurement ,the neutron spectrum uncertainty using Monte‐Carlo sampling algorithm was calculated . In the verification of this method with 252 Cf spontaneous fission spectrum ,its uncertainty analysis result was more comprehensive than that of traditional method .The uncertainty analysis of a neutron spectrum measurement for Xi’an Pulsed Reactor was analyzed .The analysis result shows that the method is more conservative .
Keywords:neutron spectrum  uncertainty analysis  1 MeV equivalent neutron fluence  Xi’an pulsed reactor
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