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Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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June 2025
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Latest News
BREAKING NEWS: Trump issues executive orders to overhaul nuclear industry
The Trump administration issued four executive orders today aimed at boosting domestic nuclear deployment ahead of significant growth in projected energy demand in the coming decades.
During a live signing in the Oval Office, President Donald Trump called nuclear “a hot industry,” adding, “It’s a brilliant industry. [But] you’ve got to do it right. It’s become very safe and environmental.”
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.