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keff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。
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 keff 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 keff values than those from CENDL-2.1.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2010年第S2期145-149,共5页
Nuclear Power Engineering
