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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Nuclear Science and Engineering
February 2025
Nuclear Technology
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Latest News
State lawmakers across the country push for more nuclear
From lifting moratoriums to launching studies to labeling it as clean, state lawmakers are exploring ways to give nuclear energy a boost in 2025. Here’s a look at some of the pronuclear legislation under review.
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.