The interface design of storage and examination system for BWR spent nuclear fuel dry storage demonstration project in Taiwan

Abstract Due to the lack of Boiling Water Reactor (BWR) fuel examination data after dry storage, Taiwan Power Company and Institute Nuclear Energy Research jointly launched “Taiwan Fuel Storage Demonstration Project” collect characteristics under simulated storage. To meet project requirements, BWR rods in different designs will be selected then store storage containers environments for 10 years. The interface considerations design results auxiliary equipment spent nuclear transfer, non-destructive testing simulation stage were summarized. In addition, possibility operating at high heating power avoiding deformation components due thermal extension was included consideration. A simplification concept introduced, with frequent NDT (Non-destructive Testing) inspections that performed through transfer process. test showed can requirements long-term experiment, maintenance radiation protection is ready further demonstration.