摘要
为检验和改进233 U核反应全套中子评价数据的质量,从国际核临界安全手册ICSBEP中选取快谱、超热谱和热谱临界基准实验装置,对中国评价核数据库CENDL-3.1、美国评价核数据库ENDF/B-Ⅶ.0、日本评价核数据JENDL-3.3和JENDL-4.0中的233 U评价数据进行了基准检验。采用蒙特卡罗程序MCNP5计算了所选基准装置的有效增殖因数keff,并与基准值进行比较。运用基于能谱指标的趋势分析、灵敏度分析等方法进行了分析。在基准检验中,现有的233 U评价数据的主要问题是从热临界基准中能谱较硬的装置到超热谱基准装置再到部分快谱临界基准装置,较为普遍地存在keff的严重低估。从热堆设计角度考虑,ENDF/B-Ⅶ.0库233 U评价数据表现较好,但仍高估了共振俘获的贡献。
To validate and improve the quality of the complete set of evaluated nuclear reaction data for^ 233U,criticality benchmarks with fast,epithermal and thermal spectra from ICSBEP handbook were selected to test ^233U evaluations from CENDL-3.1,ENDF/B-Ⅶ.0,JENDL-3.3 and JENDL-4.0.The effective multiplication factors keff of selected benchmarks were calculated with the Monte Carlo code MCNP5 and compared with the benchmark values.The results were analyzed with trend against energy spectrum index and sensitivity analysis.In present validation,the underestimation of keff for benchmarks with thermal,epithermal or some of fast spectra is the main problem existed in the tested evaluations.From the view of thermal reactors design,the 233U evaluation from ENDF/B-Ⅶ.0 shows better performance than other file tested,but still overestimates the contribution of capture reaction in resonance region.
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2012年第10期1158-1164,共7页
Atomic Energy Science and Technology
