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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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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 Technology
Fusion Science and Technology
Latest News
Vogtle-3 shuts down for valve issue
One of the new Vogtle units in Georgia was shut down unexpectedly on Monday last week for a valve issue that has since been investigated and repaired. According to multiple local news outlets, Georgia Power reported on July 17 that Unit 3 was back in service.
Southern Company spokesperson Jacob Hawkins confirmed that Vogtle-3 went off line at 9:25 p.m. local time on July 8 “due to lowering water levels in the steam generators caused by a valve issue on one of the three main feedwater pumps.”
William P. Duggan, Don Stelner , Mark J. Embrechts
Fusion Science and Technology | Volume 10 | Number 3 | November 1986 | Pages 890-895
Innovative Concepts for Power Conversion | Proceedings of the Seveth Topical Meeting on the Technology of Fusion Energy (Reno, Nevada, June 15–19, 1986) | doi.org/10.13182/FST86-A24849
Articles are hosted by Taylor and Francis Online.
A design of a compact fusion reactor is proposed based on the reversed field pinch and utilizing the "Integrated-Blanket-CoiI" (IBC) concept. The IBC is applied to the toroidal field and divertor systems, with liquid metal used for cooling both the first wall and blanket. This simplifies the overall design by requiring only a single coolant cycle. In addition, safety is increased by eliminating any possible lithium-water interaction in the fusion power core. Finally, replacing conventional copper divertor coils with IBC components enhances tritium breeding and energy recovery. A generic problem with liquid metal coolants is their reduced heat transfer capabilities in magnetic fields. In this context, the use of liquid metal coolants may limit the allowable neutron wall loading to a value of 10 MW/m2. Above this value it may be necessary to use water cooling for the first wall and divertor surfaces.