2023 Eutectic reaction and oxidation behavior of Cr-coated Zircaloy-4 accident-tolerant fuel cladding under various heating rates 본문 Author 이유호 Journal Journal of Nuclear Materials Vol./ Page Volume 583 Year 2023 DOI professor 수정 삭제 검색 목록 이전글Recrystallization and grain growth of Zr-Nb-Sn alloy in 400-500 degrees C and effect on hydride embrittlement 24.07.11 다음글Effect evaluation on performance issues of passive safety system- Part II. Passive emergency core cooling system 24.07.11