摘要
通过一系列基于实验的基准题对DRAGON3.05B程序挂载WIMS-D核数据库的计算结果进行验证,综合检验了其对不同燃料、不同元件结构的临界计算以及燃耗中的核密度和k∞的计算正确性。并通过DRAGON3.05B与WIMSD-5B分别挂载WIMS-D和ENDF/B-VI.8核数据库的计算结果进行比较。结果表明:DRAGON3.05B挂载WIMS-D库的计算结果是可靠的,其正确性可以满足对钍基先进CANDU堆的设计要求。
Through a series of benchmarks based on experiments, this paper validates the calculations of DRAGON3.05B with WIMS-D nuclear data library, and testes the correctness of its criticality and its isotope prediction and k∝ in burnup calculation of various fuel materials and different lattices. By the comparison of the results of WIMSD-5B using WIMS-D and ENDF/B-VI.8, respectively, the result indicates that the calculation of DRAGON3.05B using WIMS-D is reliable and can satisfy the requirement of TACR design.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2007年第6期20-24,共5页
Nuclear Power Engineering