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Division Spotlight
Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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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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.
R.D. Pillsbury, Jr., J.H. Schultz, R.J. Thome
Fusion Science and Technology | Volume 10 | Number 3 | November 1986 | Pages 504-507
The Compact Ignition Tokamak Program | Proceedings of the Seveth Topical Meeting on the Technology of Fusion Energy (Reno, Nevada, June 15–19, 1986) | doi.org/10.13182/FST86-A24796
Articles are hosted by Taylor and Francis Online.
Preliminary designs for the poloidal field coil system for several alternative concepts for the Ignition Studies Project have been analyzed. Options include both a limiter and divertor configuration with PF coils located internal to the TF coil, external to the TF coil, and a mixture of internal and external (hybrid) coils. The effect on the system parameters of ampere-meters, stored and dissipated energy, and peak requirements are reported. The all internal coil configuration for the diverted plasma has significantly lower amperemeters, energy, and power requirements. However, internal coils are disadvantageous from the remote maintenance standpoint.
