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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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 Science and Engineering
August 2024
Nuclear Technology
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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 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. 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.”
C. M. Sommer, W. M. Stacey, B. Petrovic, C. L. Stewart
Nuclear Technology | Volume 182 | Number 3 | June 2013 | Pages 274-285
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-A16979
Articles are hosted by Taylor and Francis Online.
Fuel cycle analyses of the transmutation of (a) all of the transuranics (TRUs) in light water reactor (LWR) spent nuclear fuel (SNF) and of (b) the minor actinides (MAs) remaining in SNF (after separation of much of the plutonium for starting up fast reactors) have been performed for the conceptual subcritical advanced burner reactor (SABR) fission-fusion hybrid sodium-cooled fast burner reactor. Both metallic and oxide burner reactor fuels were considered, and the effect of clad radiation damage limit on fuel residence time was investigated. For a radiation damage limit of 200 displacements per atom, the support ratio (LWR power/SABR power) for transmuting all of the TRUs produced by LWRs is 3/1, and for transmuting just the MAs produced by LWRs the support ratio is 25/1. The reduction in high-level waste repository capacity required due to this transmutation is a factor of 10, based on a decay heat at a 100 000-yr limit on capacity.