INFRA performance evaluation for dry process fuel

It is necessary to develop a fuel performance code system to analyze the in-core behavior of the fuel which is fabricated from the spent Light Water Reactor (LWR) fuel through the remote dry process. The ultimate goal is to obtain dry-process fuel performance code systems for every target reactors, because dry-process fuel can be used for various nuclear systems. In order to evaluate the performance of dry-process fuel loaded into the Pressurized Water Reactor (PWR), we have modified INFRA, an high burnup fuel performance code system developed independently by Korea Atomic Energy Research Institute (KAERI), with thermal and mechanical performance models of dry-process fuel. Hence, the in-core behavior of dry-process fuel will be estimated in the PWR with this code system. This report deals with the comparative study of the thermal characteristics of UO2 fuel and dry-process fuel by the computational results obtained from the modified INFRA code with various thermal and mechanical models of the dry-process fuel. This report will be utilized to provide basic data for the dry-process fuel performance and to construct the dry-process fuel performance code system with new thermal and mechanical models of dry-process fuel for the future nuclear systems such as the generation IV reactor systems