钍铀循环核数据库

为满足钍基熔盐实验堆物理设计对钍铀燃料循环核数据的需求，中国科学院上海应用物理研究所与中国核数据中心联合研制了钍铀燃料循环专用评价数据库CENDL-TMSR-V1。根据钍基熔盐实验堆的实际需求，开发了一系列宏观群常数库，建立了钍铀燃料循环专用核数据库。对于中子评价数据，结合宏观检验及微观评价对比分析，从国际主流评价数据库中筛选出科学可靠的通用核素核数据。重点改进TMSR关键核素7,6Li、231,232Th、233Pa和232,233U核数据；新增了熔盐堆独需的FLiBe热中子散射率数据；最终形成了TMSR物理设计所需的轻核、结构材料、裂变产物和裂变核等共405种核素的专用中子评价数据库。基于国际核临界安全手册，建立了包含300多个基准实验装置的宏观检验系统，对实验堆用数据库进行了适用性分析。检验结果显示，CENDL-TMSR-V1的计算值与实验值的差异大部分都控制在0.5%之内，其计算结果与ENDF/B-VII.0库的计算结果基本一致，部分装置要优于ENDF/B-VII.0。结果表明CENDL-TMSR-V1数据库是可靠的，其整体临界计算性能已达到或略优于ENDF/B-Ⅶ.0数据库，可用于钍基熔盐实验堆的物理设计。

To meet the demand for thorium-uranium fuel cycle nuclear data in the physical design of the thorium-based molten salt experimental reactor, the Shanghai Institute of Applied Physics of the Chinese Academy of Sciences and the China Nuclear Data Center jointly developed the specialized evaluated nuclear data library CENDL-TMSR-V1 for the thorium-uranium fuel cycle. Based on the actual requirements of the thorium-based molten salt experimental reactor, a series of macroscopic group constant libraries were developed, and a dedicated nuclear database for the thorium-uranium fuel cycle was established. For neutron evaluated data, scientifically reliable general-purpose nuclide nuclear data were screened from international mainstream evaluated databases via macroscopic validation and comparative analysis of microscopic evaluations. Prioritized improvements were made to the nuclear data of key TMSR nuclides: ⁶Li, ⁷Li, ²³¹Th, ²³²Th, ²³³Pa, ²³²U and ²³³U. Thermal neutron scattering cross-section data of FLiBe, which is uniquely required for molten salt reactors, were also added. Finally, a dedicated neutron evaluated database covering a total of 405 nuclides including light nuclei, structural materials, fission products and fission nuclei required for TMSR physical design was developed. Based on the International Handbook of Nuclear Criticality Safety, a macroscopic validation system containing over 300 benchmark experimental setups was established to conduct applicability analysis of the library for the experimental reactor. The validation results show that the discrepancies between the calculated values from CENDL-TMSR-V1 and the experimental values are mostly within 0.5%. The calculation results are basically consistent with those from the ENDF/B-VII.0 library, and perform better for some facilities. The results demonstrate that the CENDL-TMSR-V1 library is reliable, with its overall criticality calculation performance reaching or slightly exceeding that of the ENDF/B-VII.0 library, and it can be used for the physical design of thorium-based molten salt experimental reactors.

搜集汇总

背景与挑战

背景概述

该数据集是为钍基熔盐实验堆物理设计而开发的钍铀燃料循环专用核数据库，包含405种核素的中子评价数据。经过宏观检验，其计算性能可靠，整体临界计算达到或略优于国际主流数据库ENDF/B-Ⅶ.0水平。