铅基快堆RBEC-M燃耗库制作方法研究及验证

      提出了一套新的方法流程，用来处理和生成燃耗计算所需的数据。利用核数据处理程序NJOY处理评价数据库ENDF-B-Ⅶ.1生成33群的MATXS格式库，再根据具体问题中的材料信息，经截面处理程序MGGC处理得到相关核素的微观、宏观截面，经自编写的处理模块Triso对其进行格式转化、合并，最终得到提供给燃耗计算程序使用的ISOTXS库文件，其中一般核素以微观截面的形式表示，裂变产物以类似宏观截面的伪裂变产物形式表示。对铅冷快堆基准题900 MW RBEC-M进行了计算，采用REBUS-3进行燃耗计算，对比了结果中的有效增殖系数k_eff随燃耗的变化趋势、功率分布以及中子能谱，最终结果与参考报告较为符合，初步验证了这一系列燃耗库制作流程的可行性。 

Research and Validation of Burnup Library Processing for Lead Based Fast Reactor RBEC-M

A new method to process the data for burnup calculation is proposed. Using NJOY is used to process ENDF-B-VII.1, and 33-group MATXS format library is generated. The multigroup cross section generating code (MGGC) can get the micro and macro cross section with composition information, using a new added module Triso to merge and output the data, and finally the ISOTXS format library for burnup calculation can be obtained. The fission product is expressed with the macroscopic cross section of lumped fission product, and others are in the form of microscopic cross section. The lead cooled fast reactor benchmark 900 MW RBEC-M was calculated using REBUS-3 burnup calculation module, and the results of effective neutron multiplication factor, power distribution and neutron spectrum were compared. The final results are consistent with the reference in the report, and the feasibility of this burnup library processing method is validated preliminarily.