Using Spatial Flux Calculations to Improve the Fluence-Based Neutron Balance Approach

摘要

Nuclear fuel cycle (NFC) simulators are used for the evaluation and comparison of new fuel cycle technologies. In order to carry out this comparison, it is necessary to determine with sufficient accuracy the various isotopic compositions of materials passing through the fuel cycle facilities. In some cases, it is very useful to determine the isotopic compositions of materials passing through the fuel cycle based on certain parameters such as reactor burnups or reactor conversion ratios.