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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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
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.”
Michael G. Izenson, Javier A. Valenzuela
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 1828-1834
Plasma-Facing Component | doi.org/10.13182/FST92-A29984
Articles are hosted by Taylor and Francis Online.
Helium cooling offers safety advantages for fusion reactors because helium is single-phase and chemically inert. The Normal Flow Heat Exchanger (NFHX) enables highly efficient heat transfer to helium with low pressure drops at high heat fluxes. Thus, the NFHX enables helium cooling of divertor panels in Tokamak reactors and potentially enhances the safety of fusion power production. This paper explains the NFHX concept, presents the current status of the technology, and shows how the NFHX can be used to cool divertor panels in Tokamak reactors.