Parameter making and preliminary test of ACE format libraries based on different ENDF/B
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摘要: 评价核数据库是反应堆物理分析的基础。本研究调研了各个时期重要版本的评价核数据库ENDF/B-Ⅳ,Ⅴ.2,Ⅵ.8,Ⅶ.0,Ⅶ.1,用国际著名的核数据处理程序NJOY进行加工得到五组连续能量点截面库,对部分核素的微观截面进行比较,利用堆用蒙卡程序RMC进行临界基准检验。结果表明：基于ENDF/B-Ⅶ.1制作的连续能量中子截面库具有更高的精确度和良好的可靠性。Abstract: Evaluated nuclear data libraries are the basis of reactor physics analysis. This study investigates major versions of evaluated nuclear data libraries in various stages, namely ENDF/B-Ⅳ, Ⅴ.2, Ⅵ.8, Ⅶ.0 and Ⅶ.1, which are then processed by the internationally renowned nuclear data processing code NJOY to obtain five groups of continuous energy point cross section libraries. Micro cross sections of certain nuclides are compared and Reactor Monte Carlo Code (RMC) is used for verification of criticality benchmark. The result shows that continuous energy neutron cross section libraries, based on ENDF/B-Ⅶ.1, has higher accuracy and reliability.
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Key words:
- ENDF/B /
- NJOY /
- Reactor Monte Carlo Code(RMC) /
- ACE format library /
- criticality benchmark
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