과제정보
이 논문은 2024년도 원자력안전위원회의 재원으로 사용후핵연료관리핵심기술개발사업단 및 한국원자력안전재단의 지원(RS-2021-KN066110)과 과학기술정보통신부의 재원으로 한국연구재단의 지원(No. 2022R1A2C1009524)을 받아 수행되었습니다.
참고문헌
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