SN方法粒子输运计算程序自动建模关键技术问题研究

在充分调研和分析SN方法粒子输运计算程序自动建模方法的基础上，对建模过程中的模型文件格式识别、属性编辑、空腔处理及自动划分离散网格等关键技术问题进行了研究，并提出了合理可行的解决方法。通过对SNAM程序建模部分功能测试，验证了这些方法的正确性和有效性。This paper presents two approaches to enhance the geometry modeling ability of SN particle transport simulation codes and focus on the key issues that lie in the processing from CAD model to SN code geometry model, e.g. CAD file format support, void modeling, mesh generation and model-editing. SNAM （SN Automatic Modeling system） has been developed as an interface code between commercial CAD software and SN particle transport simmulation codes. The testing results have shown that the algorithm and implementation used in SNAM are efficient and capable of all the necessary processing from CAD model to SN geometry model.     

HENDL1.1/MG数据库和VisualBUS1．0程序的临界基准计算与分析

使用自主开发的一维输运／燃耗／可视化计算程序系统VisualBUS1．0和HENDL1．1／MG数据库,对^233U,^235U和^239Pu的热溶液临界球基准实验和^237Np,^241Am和^244Cm的金属快裂变临界球问题进行校核。和国际上广泛使用的各种程序和数据库的模拟计算结果以及相关实验结果进行综合对比和分析,初步验证了HENDL1．1／MG中裂变核素核数据的可靠性和应用性,同时也进一步证明了VisualBUS1.0程序的正确性。The evaluated critical safety benchmark experiments including some major elements of fission materials, such as ^233U, ^235U, ^239pu and ^237Np, ^241Am, ^244Cm, were simulated using the home-developed one-dimensionaltrasportation/burnup/optimization code system VisualBUS1.0 and HENDL1.1/MG, a multi-group working library of fusion-fission Hybrid Evaluated Nuclear Data Library, by FDS team. By the comparison with the measured resuits and the calculated values given in the International Handbook of Evaluated Criticality Safety Benchmark Experiments, HENDL1.1/MG data library and VisualBUS1.0 code are validated and qualified to be reliable.     

混合评价核数据库HENDL1.0/MG/MC研制

根据世界几个主要核评价数据库,如ENDF/B 6(美国)、JEF 2.2(欧盟)、JENDL 3.2(日本)、BROND 2.2(俄罗斯)、CENDL 2.1(中国)和FENDL 2(IAEA/NDS),兼顾聚变、裂变以及聚变 裂变次临界混合堆设计研究的多种需要,经过甄别、筛选,最后集成为包含213个核素的基本评价文件,名为HENDL1.0/E的核评价数据库.在此基础上,利用目前流行的群常数加工程序系统NJOY和输运截面制备程序TRANSX制作两套用于中子或/和光子输运计算的输运截面工作库:①参考Vitamin J能群结构制作了175群中子和42群光子、中子 光子耦合多群工作数据库HENDL1.0/MG,可用于离散纵标Sn法程序计算;②连续能群结构、紧凑ENDF(ACE)格式中子截面库HENDL1.0/MC,可用于蒙特卡罗方法输运计算,如MCNP.另外还制作了可用于燃耗(嬗变)计算的燃耗库BURNUP.LIB和响应函数库RESPONSE.LIB两个专用数据库.同时,也对HENDL1.0综合评价核数据库的有效性进行了抽样测试、基准检验和初步确认. A Hybrid Evaluated Nuclear Data Library(HENDL) named as HENDL1.0 has been developed by Fusion Design Study (FDS) team of Institute of Plasma Physics, Academia Sinica (ASIPP) to take into account the requirements in design and research relevant to fusion, fission and fusion-fission sub-critical hybrid reactor. HENDL1.0 contains one basic evaluated sub-library naming HENDL1.0/E and two processed working sub-libraries naming HENDL1.0/MG and HENDL1.0/MC, respectively. Through carefully comparing...