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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.
A. R. Larson, I. O. Bohachevsky
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 1245-1250
Blanket and First Wall Engineering | doi.org/10.13182/FST83-A23028
Articles are hosted by Taylor and Francis Online.
Discussed are the advantages of using fusion neutrons for breeding special nuclear materials and tritium. Monte Carlo calculations were used to identify both fissionable and nonfissionable materials that multiply neutrons and increase breeding ratios. Fissionable multipliers also greatly multiply the neutron energy. A generic blanket design that utilizes 238U as a neutron multiplier is decribed and compared to an ideal infinite-medium blanket. Time-dependent calculations show gradual improvement of performance during the lifetime of the blanket. The blanket analyzed here is compatible with a reaction chamber that uses high velocity lithium, held on the wall by centrifugal acceleration, to protect the wall from pellet explosions.