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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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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
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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
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.
Vito Renda, Loris Papa
Fusion Science and Technology | Volume 20 | Number 1 | August 1991 | Pages 40-47
Technical Paper | Divertor System | doi.org/10.13182/FST91-A29641
Articles are hosted by Taylor and Francis Online.
The performance and limits of a divertor plate for the Next European Torus (NET) are assessed. The design is a plasma-facing component that integrates the divertor plates and the inboard first wall in a monoblock panel. It is made of stainless steel poloidal U-tubes embedded in a copper matrix and protected by a carbon-fiber composite graphite armor. The thermal and thermomechanical behavior are analyzed in the high thermal flux zone taking into account the actual surface heating, which ranges from 5 to 10 MW/m2. A simplified preliminary analysis assesses the water flow and the component geometry in accordance with the system and material data foreseen for NET. It is shown that if the surface temperature of the armor is limited to 1273 K, the graphite thickness must be limited to 7.5 mm. Detailed thermal and mechanical finite element analyses, performed by the CASTEM 2000 code, show that the cooling tubes remain just below the creep regime temperature. The allowable limits prescribed by international standards are met, and the component's lifetime is 3000 cycles.