2022 Post-LOCA ductility assessment of Zr-Nb Alloy from 1100°C to 1300°C to explore variable peak cladding temperature and equivalent cladding reacted safety criteria 본문 Author 이유호 Journal Journal of Nuclear Materials Vol./ Page Volume 567 Year 2022 DOI professor 수정 삭제 목록 이전글Estimation of rock joint diameter distribution using numerically generated joint center volume 24.07.11 다음글Study of high burnup effect on steam oxidation of Zircaloy and its regulatory implications via the developement of a pre-transient oxide model of TRANOX 24.07.11