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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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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, Tohru Fukui, Shigeo Hatamiya, Toshitsugu Nakao, Masanori Naitoh, Isao Sumida
Nuclear Technology | Volume 99 | Number 3 | September 1992 | Pages 386-396
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34722
Articles are hosted by Taylor and Francis Online.
To evaluate the heat removal capability of an external water wall-type containment vessel, which is a passive system for containment cooling, thermal-hydraulic behavior in the suppression and outer pools has been examined experimentally. The following results are obtained: 1. A thermal stratification boundary, which separates the pools into an upper high-temperature region and a lower low-temperature region, is observed just below the vent outlet. 2. The natural-convection heat transfer coefficients (HTCs) for the downward and upward flows that appear inside and outside the primary containment vessel wall are measured. These values can be expressed by Nu = 0.13Ra1/3. 3. The condensation HTCs in the presence of non-condensable gas, which affect heat transfer between the wet well and the outer pool, are measured along the long wall. The vertical variations of the condensation HTCs are within 10% of the averaged coefficients, and the averaged coefficients can be expressed by hm = 0.43(ma/ms)-0.8, where hm (kW/m2·K is the condensation HTC and (ma/ms) is the mass ratio of noncon-densable gas and steam. 4. The capability for decay heat removal in the external water wall-type containment vessel for a 600-MW(electric) plant is evaluated based on these results and is found to be large enough.