CANFLEX-NU Fuel Licensing Status and Issues in Korea

Abstract

The CANFLEX-NU Fuel Design Report (FDR) for Wolsung 1,2,3,4 was submitted for licensing review in July 1996. The FDR contains sections of fuel rod design, fuel bundle design, nuclear design and thermal-hydraulic design. Each section describes the design bases, design methodology and design evaluation results showing that the design bases are met. The CANFLEX-NU fuel design is not finalized yet in Korean licensing point of view. For example, among others, new Xc-BL correlation is needed to be developed, fuel rod gap reduction effect is to be considered in the Critical Heat Flux, more information for power ramp defect of fuel rod especially in the end-cap weld regon is needed in the he1 rod design, and enough data are not available in irradiated conditions in the fuel rod and bundle designs. The specific detailed technical licensing issues and their backgrounds are explained for the CANFLEX-NU FDR in Korea. The Korean nuclear regulation environment is changing due to the Korean government policy of overall regulation reduction. The contents and timetables of Korean nuclear regulation changes are also explained for new fuel licensing.