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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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 Science and Engineering
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Nuclear Technology
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.
H.M. Attaya, G.A. Emmert, J.F. Santarius, G.L. Kulcinski
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 367-372
Power Reactor and Next-Generation Studies | Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) | doi.org/10.13182/FST85-A40072
Articles are hosted by Taylor and Francis Online.
A summary of a recent design effort for a high wall loading, low power, compact tokamak reactor is presented. The design employs a bean-shaped plasma to reach the second stability regime, where high beta values are attainable. A point design was chosen based on a parameteric survey that was conducted using the Tokamak Systems Code (TSC). The most important parts of that survey are presented here. Investigation of different plasma confinement scaling laws shows that the chosen point design has a reasonable ignition margin.