2025 Exploring the Peak Cladding Temperature Limit of Cr-coated ATF Cladding by Assessing the Impact of the Zr-Cr Eutectic on the Structural Integrity of Cladding 본문 Author 이유호 Journal Journal of Nuclear Materials Vol./ Page 605/155577 Year 2025 All Authors Joung, S.[Joung, SungHoon]; Yook, H.[Yook, Hyunwoo]; Kim, D.[Kim, Dongju]; Lee, Y.[Lee, Youho] P-ISSN 0022-3115 DOI 10.1016/j.jnucmat.2024.155577 목록 이전글Evaluation of tritium production capability of the 5 MWe gas-cooled graphite-moderated reactor at Yongbyon using tritium-producing burnable absorber rods 25.12.10 다음글Laser cutting study of zirconium alloys for nuclear decommissioning 25.12.10