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
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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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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.
Arthur A. Bauer
Nuclear Technology | Volume 14 | Number 1 | April 1972 | Pages 65-70
Technical Paper | Session on Physics of Nuclear Materials Safeguards / Fuel | doi.org/10.13182/NT72-A31099
Articles are hosted by Taylor and Francis Online.
A fuel-specimen model is developed to describe the diametral swelling behavior of W-Re clad, oxide fuel specimens irradiated at a clad surface temperature in excess of 1200°C. The model is based on experimental observations at elevated fuel temperatures that fission-gas bubbles form to expand the fuel but that bubble and lenticular void movement, as a result of vaporphase transport, provide a mechanism for redensifying the fuel so that swelling is a continuous steady-state process. Good agreement with experimentally measured diametral changes is obtained by application of the model.
