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.