PRELIMINARY ANALYSIS ON IN-REACTOR PERFORMANCE OF THE BLANKET ROD FOR HYPER

摘要

TRU-Zr alloy is used as the blanket fuel of the HYPER system. The in-reactor performance analysis in fuel design is essential to assure adequate fuel performance and integrity under irradiation conditions. In this paper, modeling efforts of the material properties and a fuel temperature prediction scheme for TRU-Zr fuel rods have been made to formulate an estimated temperature profile of the blanket pin, and the properties and the fuel temperature prediction scheme are incorporated into the MACSIS-H code. The in-reactor performance characteristics for TRU-Zr fuel rod have also been analyzed by the MACSIS-H.