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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Hsiang-Shou Cheng, David J. Diamond, Ming-Shih Lu
Nuclear Technology | Volume 37 | Number 3 | March 1978 | Pages 246-260
Technical paper | Reactor | doi.org/10.13182/NT78-A31993
Articles are hosted by Taylor and Francis Online.
An extensive study of boiling water reactor scram reactivity behavior is presented. It is based on a spacetime analysis using a two-dimensional (R,Z) dynamics code that includes a two-phase thermal-hydraulics model. Calculations were made of the sensitivity of scram to such physical quantities as initial control rod position and power distribution, scram speed, system pressure, and varying inlet flow rate and temperature. The end-of-cycle Haling operating condition with all rods initially withdrawn was found to give rise to the limiting scram reactivity function. Calculations were also made to find the effect on scram of commonly used modeling approximations. These included the effect of neglecting delayed neutrons (conservative), using a time invariant void distribution (nonconservative), and defining point kinetics parameters in terms of different weighting functions. The importance of defining these parameters consistent with their use in plant transient analyses was also demonstrated.