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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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Fusion Science and Technology
Latest News
Webinar: MC&A and safety in advanced reactors in focus
Towell
Russell
Prasad
The American Nuclear Society’s Nuclear Nonproliferation Policy Division recently hosted a webinar on updating material control and accounting (MC&A) and security regulations for the evolving field of advanced reactors.
Moderator Shikha Prasad (CEO, Srijan LLC) was joined by two presenters, John Russell and Lester Towell, who looked at how regulations that were historically developed for traditional light water reactors will apply to the next generation of nuclear technology and what changes need to be made.
S. I. Abdel-Khalik, L. Crosatti, D. L. Sadowski, S. Shin, J. B. Weathers, M. Yoda, ARIES Team
Fusion Science and Technology | Volume 54 | Number 3 | October 2008 | Pages 864-877
Technical Paper | Aries-Cs Special Issue | doi.org/10.13182/FST08-A1907
Articles are hosted by Taylor and Francis Online.
This paper describes a numerical and experimental investigation in support of the ARIES-CS divertor design, which selected a modular, helium-cooled, T-tube design that can accommodate a peak heat load of 10 MW/m2. Numerical analyses were carried out using the FLUENT computational fluid dynamics software package to evaluate the thermal performance of the divertor at the nominal design and operating conditions. Sensitivity studies were also performed to determine the effect of variations in geometry and operating conditions resulting from manufacturing tolerances and/or flow maldistribution between modules. The results indicate that the selected design is "robust" with respect to such anticipated variations in design and operational parameters and that a peak heat flux of 10 MW/m2 can be accommodated within the constraints dictated by material properties. Extremely high heat transfer coefficients [>40 kW/(m2K)] were predicted by the numerical model; these values were judged to be "outside the experience base" for gas-cooled engineering systems. Hence, an experimental investigation was undertaken to verify the results of the numerical model. Variations of the local heat transfer coefficient within an air-cooled, geometrically similar test module were measured at the same Reynolds number as the actual helium-cooled divertor. Close agreement between the model predictions and experimental data was obtained. The results of this investigation provide added confidence in the results of the numerical model used to design the ARIES-CS divertor and its applicability to other gas-cooled high-heat flux components.