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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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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.
John Galambos, Y.-K. M. Peng, John Haines
Fusion Science and Technology | Volume 26 | Number 3 | November 1994 | Pages 1196-1202
Fusion Power Reactor, Economic, and Alternate Concept | Proceedings of the Eleventh Topical Meeting on the Technology of Fusion Energy New Orleans, Louisiana June 19-23, 1994 | doi.org/10.13182/FST94-A40314
Articles are hosted by Taylor and Francis Online.
We find minimum sized Spherical Tokamak (ST) configurations capable of Q∼1 (scientific break-even) and ignition. For Q∼1 cases, we normalize our models to the JET device. We find comparable plasma power balance performance in an ST configuration of major radius ∼ 0.7 m, using both global and 3/2 D plasma transport modeling. For ignited plasma, we first normalize the plasma modeling to the ITER device. We find similar ignited plasma performance capabilities in an ST configuration of major radius 1.2 m. These are much smaller size plasmas than the standard tokamak counterparts, indicating a potentially easier path towards commercial applications. Also, we find that the quantity IA is not a good figure-of-merit for comparing performance of widely different tokamak configurations.