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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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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Nuclear Technology
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May 2025
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Industry Update—May 2025
Here is a recap of industry happenings from the recent past:
TerraPower’s Natrium reactor advances on several fronts
TerraPower has continued making aggressive progress in several areas for its under-construction Natrium Reactor Demonstration Project since the beginning of the year. Natrium is an advanced 345-MWe reactor that has liquid sodium as a coolant, improved fuel utilization, enhanced safety features, and an integrated energy storage system, allowing for a brief power output boost to 500-MWe if needed for grid resiliency. The company broke ground for its first Natrium plant in 2024 near a retiring coal plant in Kemmerer, Wyo.
Nicholas T. Saltos, Tunc Aldemir, Richard N. Christensen
Nuclear Technology | Volume 82 | Number 2 | August 1988 | Pages 187-210
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT88-A34107
Articles are hosted by Taylor and Francis Online.
An efficient variational method was developed to solve the transient radial-azimuthal heat conduction problem in nuclear fuel rods under loss-of-coolant-accident (LOCA) conditions. The method is efficient in that it is fast, accurate, and compatible with the modular accident analysis codes already in use in the nuclear industry. The methodology uses the Lebon-Labermont restricted variational principle, with parabolic trial functions in the radial direction and circular trial functions in the azimuthal direction, to reduce the transient heat conduction problem in the rod to a set of first-order ordinary differential equations in time. These equations are then solved by an explicit technique. The solution is in a readily usable form (i.e., averages and gradients can be determined without interpolation) and the same algorithm is used for both one- and two-dimensional problems. The solution technique allows changing the trial functions at every time step to obtain an accurate solution with minimum computing time. The methodology is implemented for a single rod under hypothetical LOCA conditions in order to (a) investigate the sensitivity of the predicted radial-azimuthal temperature distributions to the choice of the trial functions, (b) investigate the importance of nonlinearity effects (i.e., temperature dependence of thermal properties) on rod response, and (c) compare the variational and finite difference techniques with respect to computation time and accuracy of the results. It is shown that the variational technique leads to substantial reduction in computing time (more than a factor of 3) for comparable accuracy.