Processing Methods for Temperature-Dependent MCNP Libaries
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摘要: 在截面库研制过程中,着重考虑了在反应堆设计与运行温度范围的温度点;使用NJOY软件将ENDF格式的中子截面文件处理为ACE (A Compact ENDF)格式的点截面文件,供MCNP程序使用。验证过程应用了3种不同类型的临界基准题:简单的球形几何基准题、板式燃料元件实验装置和带有可燃毒物的堆芯。结果表明,3种临界基准题所得到的验证结果均较为理想,在精确度方面也达到了要求。证明了使用NJOY制作截面库方法的正确性。Abstract: In this paper,the processing method of NJOY which transfers ENDF files to ACE(A Com-pact ENDF) files(point-wise cross-Section file used for MCNP program) is discussed.Temperatures that cover the range for reactor design and operation are considered.Three benchmarks are used for testing the method: Jezebel Benchmark,28cm-thick Slab Core Benchmark and LWR Benchmark with Burnable Absorbers.The calculation results showed the precision of the neutron cross-section library and verified the correct processing methods in usage of NJOY.
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Key words:
- NJOY /
- MCNP /
- Temperature-dependent Cross-section Library /
- Benchmark.
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