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

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

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 prov...

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Veröffentlicht in:核技术（英文版） 2014-10, Vol.25 (5), p.86-89
1. Verfasser: 陈冲 邹俊 郑剑 孙梦萍 陈红丽
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Sprache:eng
Schlagworte:
中子截面
反应堆设计
基准测试
多点温度
开发
测试代码
自动生成
连续能量
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container_issue 5
container_start_page 86
container_title 核技术（英文版）
container_volume 25
creator 陈冲 邹俊 郑剑 孙梦萍 陈红丽
description 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
doi_str_mv 10.13538/j.1001-8042/nst.25.050602
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subjects 中子截面
反应堆设计
基准测试
多点温度
开发
测试代码
自动生成
连续能量
title Development and testing of the code for automatic generating of multi-temperature continuous-energy neutron cross section libraries
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