ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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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Apr 2025
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Nuclear Science and Engineering
May 2025
Nuclear Technology
Fusion Science and Technology
Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
G. A. Deis, P. Y. Hsu, K. D. Watts, E. C. Welch
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 791-796
Blanket and First Wall Engineering | doi.org/10.13182/FST83-A22957
Articles are hosted by Taylor and Francis Online.
The PE-II Solid Breeder Concept Integral Simulation Test is designed to simulate (by way of nonnuclear heating) the thermal-hydraulic/thermomechanical operating characteristics of a water-cooled, Li2O fusion reactor blanket. The test piece consists of a central coolant tube surrounded by a cylinder of solid breeder material. This test piece, which simulates a unit cell of a blanket, is then subjected to an external heat flux and a purge flow of helium at carefully controlled conditions. Instrumentation provides information on temperature profiles, moisture levels, and purge flow conditions. Pretest thermal/stress analysis of this experiment indicates that it can provide an accurate simulation of actual conditions in a prototypical fusion reactor blanket.