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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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Nuclear Dirigo
On April 22, 1959, Rear Admiral George J. King, superintendent of the Maine Maritime Academy, announced that following the completion of the 1960 training cruise, cadets would begin the study of nuclear engineering. Courses at that time included radiation physics, reactor control and instrumentation, reactor theory and engineering, thermodynamics, shielding, core design, reactor maintenance, and nuclear aspects.
Xueyou Ding, Qinglong Wen (Chongping Univ), Cheng Cheng (Southeast Univ), Hongyang Wang, Shenhui Ruan, Zhiqiang Chen (Chongqing Univ)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 277-290
Helical-Coiled-Type once through steam generator (HOTSG) is considered as the first choice for its advantages in compactness and increased heat transfer in Small Modular Reactor (SMR). In this study, mathematical models of void fraction, pressure drop, and heat transfer for different boiling flow conditions in helical coil tube were presented and a computer code (OTSG-TH) for thermal-hydraulic analysis of the HOTSG was developed. Firstly, calculations were carefully validated and verified with steady-state results of ONCESG (Once Through Steam Generator) code and MRX (Marine Reactor X) experiment. Then, postulated scenarios, such as flow rate step changed in secondary side, were also calculated in this study. The results show that helical coiled tubes have higher heat transfer coefficient and fast temperature responds. Furthermore, the investigations on steady and transient states of thermal hydra-ulic analysis lay a foundation for the further study on HOTSG.