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논문 상세

Thermal-hydraulic and load following performance analysis of a heat pipe cooled reactor

출판일
20240525
ISSN
(P)1738-5733 / (E)2234-358X
수록정보
권 5호 1698 ~ 1711쪽
식별자 정보
DOI10.1016/j.net.2023.12.024
KCIART003076006
이전

논문 저자

No 이름 이메일 기관
1 Guanghui Jiao - Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University
2 Genglei Xia - Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University
3 Jianjun Wang - Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University
4 Minjun Peng - Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University