CENDL-3.1临界基准装置的积分检验

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Benchmark CENDL-3.1 with International Handbook of Evaluated Criticality Safety Benchmark Experiments

China Nuclear Data Center, China Institute of Atomic Energy, Beijing, 102413, China

摘要: 从国际核临界安全手册(ICSBEP)中选取1000余个基准实验方案,装置能谱覆盖快、中、热能区,用于系统化地检验最新版中国评价中子核反应全套数据库CENDL-3.1。采用MCNP4C程序对这些基准实验进行临界模拟计算,MCNP4C接口ACE格式的群常数库采用NJOY99制作而成。将基于CENDL-3.1计算得到的k_eff与基准实验值进行了比对,并且与CENDL-2.1进行了比较。结果表明,在检验的能区内,CENDL-3.1的检验结果整体优于CENDL-2.1。
- CENDL-3.1 /
- 基准检验 /
- 国际核临界安全手册ICSBEP /
- MCNP
Abstract: Nearly one thousand assemblies were selected from the International Criticality Safety Benchmark Evaluation Project（ICSBEP） in the International Handbook of Evaluated Criticality Safety Benchmark Experiments.These cases cover the fast,inter-and thermal spectrum.Criticality calculations were done by using Monte Carlo code MCNP4C.The ACE files were produced with nuclear data processing code NJOY99.259.The calculated results of effective multiplication factor k_eff with CENDL-2.1 and CENDL-3.1 libraries were compared with the experimental results.The systematic validation shows that the data from CENDL-3.1 give better results of k_eff values than those from CENDL-2.1.
- CENDL-3.1 /
- Benchmark /
- International Handbook of Evaluated Criticality Safety Benchmark Experiments（ICSBEP） /
- MCNP