SNUEI

Thermal performance evaluation of dry storage cask using hybrid 3D and 2D models under normal and fire exposure conditions

2025 · Nuclear Engineering and Technology

저자

Sang-Jin Kim, Sangjin Kim, Samuel Park, Chongmyung Jin, Richard Ian Foster, Dong‐Jin Lee, Seunghyun Kim, Seunghyun Kim, 최성열 (Sungyeol Choi)

연구주제

Nuclear and radioactivity studies · Nuclear Engineering Thermal-Hydraulics · Nuclear reactor physics and engineering

NTIS 과학기술표준분류

에너지/자원만에너지·환경·원자력 확장

지원 과제·AI 키워드로 잡을 근거가 없어 분류하지 않았다.

AI 연구 키워드·방법

dry cask storage fire accident spent fuel storage

열수력 해석

키워드 (OpenAlex)

dry cask storage spent nuclear fuel fire exposure thermal performance beyond design basis accidents radiative transfer direct fire indirect fire

초록

Interim storage of Used Nuclear Fuel (UNF) is increasingly important due to saturated fuel pools at Nuclear Power Plants (NPPs). Safe UNF storage requires a detailed assessment of dry cask systems, focusing on thermal, mechanical, and corrosion aspects, which are yet to be fully studied for Korean systems. This study examines the thermal performance of Korean dry cask storage, called KORAD-21 under three cases: normal, direct fire, and indirect fire exposure. Additionally, it considers beyond-design-basis conditions and the impact of radiative heat transfer in the thermal model. The first case represents normal operation while the second and third cases involve fire exposure, modeled as direct and indirect fire. Direct fire involves contact with the cask surface, with 700 °C, 800 °C, 900 °C, and 1000 °C fire for 5–50 min. All cask components stayed below safety limits except at 1000 °C f…

이 논문을 지원한 국가R&D 과제 (NTIS 성과)

NTIS 성과DB(2020–24)에서 DOI 매칭 없음

인접 그래프

노드 hover = 이웃 강조 · 1회 클릭 = 고정 · 고정된 노드 다시 클릭 = 페이지 이동

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교수 1

최성열

연구주제 1

Nuclear and radioactivity studies

방법 1

열수력 해석