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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
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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
出处 《Nuclear Science and Techniques》 SCIE CAS CSCD 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)
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 Reactor design, Temperature doppler coefficient, Critical benchmark experiments
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参考文献11

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