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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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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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. Zimmermann, M.S. Kazimi, N.O. Siu, R.J. Thome
Fusion Science and Technology | Volume 15 | Number 2 | March 1989 | Pages 951-956
Magnet Engineering, Design and Experiments — I | doi.org/10.13182/FST89-A39816
Articles are hosted by Taylor and Francis Online.
Several fault scenarios for electrical failures in the Poloidal Field (PF) magnet system are investigated involving shorts and faults with constant applied voltage at the coil terminals. A simplified model of the Compact Ignition Tokamak (CIT) is used to examine the load conditions for the PF and the Toroidal Field (TF) coils resulting from these fault scenarios. It is concluded that shorts do not pose large risks for the PF coils. Also, the type of plasma disruption has little impact on the net forces on the PF and the TF coils. However, the out-of-plane loads at the inner corner of the TF coils can increase substantially for a wide range of scenarios, and this effect can even be stronger depending on the terminal constraints on the internal PF coils.