The Safety Evaluations of Age-Related-Degradation of BWR-4 Vessel Internals in Taiwan Nuclear Power Plant

摘要

Taiwan BWR-4 Nuclear Power Plant Units 1 and 2 implemented IVVI for the reactor internals during each scheduled outage requested by ROCAEC to prevent the fracture problems due to aging. The purpose of this paper is to present the failure information survey results. The inspection results and the safety evaluation for the circumferential crack problems of the horizontal weld in core shroud are also discussed here.