基于全蒙特卡罗和基准的LFR安全参数核数据不确定性传播
Combining Total Monte Carlo and Benchmarks for nuclear data uncertainty propagation on an LFRs safety parameters
摘要：
分析进行评估的影响，核数据的不确定性对欧洲铅冷训练堆（ELECTRA）使用总蒙特卡罗方法的keff。利用TADSS系统生成的大量Pu-239随机ENDF格式库，用NJOY99.336程序处理成ACE格式，并作为Serpent Monte Carlo中子输运程序的输入，得到Keff分布。得到的keff分布与最新的主要核数据库JEFF-3.1.2，ENDF/B-VII.1和JENDL-4.0进行了比较。提出了一种使用总蒙特卡罗方法为特定应用程序选择基准的方法。最后，接受/拒绝标准进行了研究的基础上卡方值使用钚-239 Jezebel临界基准。据观察，核数据的不确定性keff大大减少，从748至443 pcm的应用更严格的验收标准接受随机文件。
英文摘要：
Analyses are carried out to assess the impact of nuclear data uncertainties on keff for the European Lead Cooled Training Reactor (ELECTRA) using the Total Monte Carlo method. A large number of Pu-239 random ENDF-formated libraries generated using the TALYS based system were processed into ACE format with NJOY99.336 code and used as input into the Serpent Monte Carlo neutron transport code to obtain distribution in keff. The keff distribution obtained was compared with the latest major nuclear data libraries - JEFF-3.1.2, ENDF/B-VII.1 and JENDL-4.0. A method is proposed for the selection of benchmarks for specific applications using the Total Monte Carlo approach. Finally, an accept/reject criterion was investigated based on chi square values obtained using the Pu-239 Jezebel criticality benchmark. It was observed that nuclear data uncertainties in keff were reduced considerably from 748 to 443 pcm by applying a more rigid acceptance criteria for accepting random files.
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