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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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.
T. C. Hung, V. K. Dhir
Nuclear Technology | Volume 92 | Number 3 | December 1990 | Pages 396-410
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT90-A16241
Articles are hosted by Taylor and Francis Online.
Conjugate heat transfer associated with the flow of sodium in an annulus in the decay heat removal mode of advanced fast reactors is studied. The coupled governing equations of momentum and energy are solved numerically and analytically. The TEACH code with the SIMPLE algorithm has been used for the internal forced flow and wall regions. For turbulent flow, a k-ε model is employed. The integral method is used for natural convection, and one-dimensional analysis is performed for the stratified flow over and underneath the redan. Results are presented for the two-dimensional temperature field in the fluids and the solid for both laminar and turbulent flows. A substantial amount of energy exchange between the hot or cold pool and the sodium flowing in the annulus occurs via the liner. As a result, convective boundary layers form along the liner. The convective motion leads to a stratified flow along the redan. In the absence of a core barrel extending into the hot pool, the fluid stratified in the hot pool, for certain core power and flow conditions, can drain down the radial blanket or be entrained by the fluid exiting the core. In contrast to behavior with an insulated liner, the heat transfer across the liner reduces the average temperature drop of the sodium flowing in the annulus, which in turn leads to a reduction in the hydrostatic head available for driving the fluid through the core.