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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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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.”
Bernd Grambow, Andreas Loida, Emmanuel Smailos
Nuclear Technology | Volume 121 | Number 2 | February 1998 | Pages 174-188
Technical Paper | German Direct Disposal Project | doi.org/10.13182/NT98-A2830
Articles are hosted by Taylor and Francis Online.
The results are summarized of 15 yr of German research on spent fuel with respect to its suitability as a waste form disposed of in a repository located in the Gorleben salt dome. Within the multibarrier system for long-term isolation of high-level waste (HLW), the innermost engineered barrier "canistered spent fuel" contributes essentially to isolating radionuclides from the biosphere if a salt brine were to come into contact with the waste form. A large fraction of the radionuclide contents of the reacted fuel mass would become reimmobilized within secondary alteration products and on container corrosion products, but inevitably a certain nuclide-specific fraction would be released into the aqueous geochemical environment. The corrosion resistance of the fuel and the radionuclide mobility are not inherent materials properties but also depend on geological disposal conditions, packing concepts, and radioactive decay. In particular, the availability of oxidants is critical, controlling spent-fuel alteration rates and alteration products as well as radionuclide solubilities. Spent fuel is at least as suitable for final disposal as is HLW glass.