Development and testing of the code for automatic generating of multi-temperature continuous-energy neutron cross section libraries  

作　　者：陈冲 邹俊 郑剑 孙梦萍 陈红丽 

机构地区：[1]School of Nuclear Science and Technology, University of Science and Technology of China [2]Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences

出　　处：《Nuclear Science and Techniques》2014年第5期86-89,共4页核技术（英文）

基　　金：Supported by the National Natural Science Foundation of China(No.91326101)

摘　　要：In the nuclear reactor design, a code for automatically generated multi-temperature continuous-energy neutron cross section data library, which is called AMTND for short, was designed and developed to meet the need of the reactor core design coupled with thermal-hydraulic design. The code can provide a point-wise crosssection at any temperature for a Monte Carlo neutron transport program, such as MCNP. In ensuring that the nuclear data produced by AMTND meets the testing of critical benchmark experiments, the time-consumed by the nuclear data generating of AMTND compared with NJOY's was carried out and the result shows the code's excellence. In order to test the accuracy of the code, the Doppler coefficient test benchmark was also carried out and the results verified the code preliminarily.In the nuclear reactor design, a code for automatically generated multi-temperature continuous-energy neu- tron cross section data library, which is called AMTND for short, was designed and developed to meet the need of the reactor core design coupled with thermal-hydraulic design. The code can provide a point-wise cross- section at any temperature for a Monte Carlo neutron transport program, such as MCNE In ensuring that the nuclear data produced by AMTND meets the testing of critical benchmark experiments, the time-consumed by the nuclear data generating of AMTND compared with NJOY＇s was carried out and the result shows the code＇s excellence. In order to test the accuracy of the code, out and the results verified the code preliminarily. the Doppler coefficient test benchmark was also carried

关 键 词：测试代码 自动生成 中子截面 连续能量 多点温度 开发 反应堆设计 基准测试 

分 类 号：TL33[核科学技术—核技术及应用]