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DTRA’s advancements in nuclear and radiological detection
A new, more complex nuclear age has begun. Echoing the tensions of the Cold War amid rapidly evolving nuclear and radiological threats, preparedness in the modern age is a contest of scientific innovation. The Research and Development Directorate (RD) at the Defense Threat Reduction Agency (DTRA) is charged with winning this contest.
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.