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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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.
M. Z. Hasan, T. Kunugi, M. Seki, M. Yokokawa, H. Ise, H. Kaburaki, The ARIES team
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 908-912
Advanced Reactor | doi.org/10.13182/FST91-A29460
Articles are hosted by Taylor and Francis Online.
The response of ARIES-I divertor plate to hard plasma disruptions has been analyzed numerically by a two-dimensional transient heat transfer code. For ARIES-I, the estimated thermal quench time is 0.3 msec and the average heat flux is 8.8×109 W/m2 with a peaking factor of 5. The divertor plate is made of 2.5 mm diameter SiC tubes with wall thickness of 0.5 mm and coated with a 2 mm layer of tungsten on the plasma facing side. The analysis predicts a total material erosion per disruption of about 111 µm without vapor shield and 48 µm with a simple vapor-shield model. The designated 1 mm of the tungsten coating for disruption is expected to last about 20 disruptions. A two-dimensional thermo-fluid dynamic analysis of the melt layer under the influence of buoyancy and surface tension forces has been performed. The results tend to imply that the melt layer is relatively unaffected during the disruption, especially for short thermal quench time.