Quenching of candidate materials for accident tolerant fuel-cladding in LWRs

Abstract

A quenching experiment with a vertical rod (diameter D = 10 mm and length L = 60 mm) was conducted under atmospheric pressure and saturation temperature of water to investigate the boiling parameters in the post-critical heat flux (CHF) regime for the candidate materials of accident tolerant fuel-cladding (ATF): FeCrAI(APMT) and SiC-CVD, compared to commercial cladding material Zircaloy-4(Zry-4) in light water reactors (LWRs). We prepared two test groups (plain surface PS and oxidized surface OS) and evaluated their surface parameters (roughness epsilon, contact angle theta(c), oxygen content of the surface, and oxide layer thickness delta(oxide)) and thermal properties (heat capacity rho C-p and thermal conductivity k) that influence the quenching performance. We analyzed the minimum film-boiling temperature T-MFB, minimum heat flux q"(min), and the heat transfer coefficient of film boiling h(film), under all test conditions. In particular, the surface damage of the SiC-CVD after quenching was analyzed by considering the post-CHF heat transfer condition, and its impact was evaluated at T-MFB during quenching. (C) 2017 Elsevier Ltd. All rights reserved.