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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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
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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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.
G. L. Kulcinski, R. R. Peterson, G. A. Moses, D. Bruggink, P. Cousseau, R. L. Engelstad, Y.-M. Lee, H. Y. Khater, E. G. Lovell, J. J. MacFarlane, E. A. Mogahed, S. Rutledge, M. E. Sawan, I. N. Sviatoslavsky, P. Wang, L. J. Wittenberg
Fusion Science and Technology | Volume 26 | Number 3 | November 1994 | Pages 849-856
Inertial Confinement Fusion Reactor, Reactor Target, and Driver | Proceedings of the Eleventh Topical Meeting on the Technology of Fusion Energy New Orleans, Louisiana June 19-23, 1994 | doi.org/10.13182/FST94-A40261
Articles are hosted by Taylor and Francis Online.
The use of light ion or electron beams to compress matter to the densities required for fusion has been proposed for more than 20 years. In the past ten years, a series of light ion beam power plant conceptual designs have been published under the generic name LIBRA. Considerable advances in both physics and technology have allowed major improvements from the design performance of the earliest LIBRA 330 MWe power plant to the more recent 979 MWe LIBRA-LiTE, and the 1000 MWe LIBRA-SP reactors. The recent declassification of target designs allows more realistic target spectra, gains, and injection parameters to be analyzed. The pulsed power driver technology has matured to the point that Helia induction technology can be tested in the laboratory under single pulse conditions and confidently extrapolated to LIBRA repetition rates. New concepts for protecting the first structural wall of the reactor have been developed; the use of flexible INPORT (INhibited Flow in PORous Tube) and rigid PERIT (PErforated RIgid Tube) units allow the reflector and first wall to last the lifetime of the power plant. The use of PbLi eutectic alloy has greatly improved the safety features of these reactors and the economics of all three compare very favorably to the tokamak, laser, and heavy ion beam reactors.
