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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.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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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.
Yoshiyuki Kataoka, Tadashi Fujii, Michio Murase
Nuclear Technology | Volume 116 | Number 1 | October 1996 | Pages 127-135
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT96-A35317
Articles are hosted by Taylor and Francis Online.
To evaluate the heat release characteristics of a primary containment vessel (PCV) external spray (one of the PCV cooling systems utilizing the steel PCV wall as the heat transfer medium), the thermal-hydraulic characteristics of the falling liquid film on the PCV surface have been investigated experimentally. Then, the performance of the PCV external spray cooling system was evaluated using the experimental findings. The following results were obtained: 1. Heat transfer coefficients of the falling liquid film under steady-state conditions were increased as the film flow rate per unit length of the liquid film width increased, and they agreed with Wilke’s correlation within about ±15%. 2. The PCV surface temperature, when preheated up to 150°C, which is the supposed PCV temperature under a severe accident, decreased below 100°C within a few seconds when the PCV external spray was initiated, and boiling on the PCV surface could not be maintained. 3. Heat transfer coefficients of the falling liquid film under transient conditions were higher initially due to the boiling effect; however, they decreased rapidly and approached those under steady-state conditions. 4. The PCV external spray for the conceptually designed PCV could suppress the PCV pressure below the design goal under a severe accident (failure of core cooling under low pressure). The maximum PCV pressure decreased as the spray flow rate increased and as the ratio of the PCV surface covered by the falling liquid film increased.