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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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Jul 2024
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Nuclear Science and Engineering
August 2024
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.”
Erich Wieland, Benjamin Z. Cvetkovi?, Dominik Kunz (Scherrer Inst), Gary Salazar, Söenke Szidat (Univ of Bern)
Proceedings | 16th International High-Level Radioactive Waste Management Conference (IHLRWM 2017) | Charlotte, NC, April 9-13, 2017 | Pages 506-511
Carbon-14 is an important radionuclide in the inventory of radioactive waste. In Switzerland, the 14C inventory in a cement-based repository for low- and intermediate-level radioactive waste (L/ILW) is mainly associated with activated steel (?85 %). In light water reactors (LWR) 14C is the product of 14N activation in steel parts exposed to thermal neutron flux. 14C has been identified a key radionuclide in safety assessments. Release of 14C occurs due to slow corrosion of activated steel in the near field of a deep geological repository. While the 14C inventory is well known, the speciation of 14C upon release from activated steel is only poorly understood. The present study is aimed at investigating the formation of carbon species during the anoxic corrosion of iron and steel and determining the 14C species formed in a corrosion experiment with activated steel. The experiments were carried out in conditions similar to those anticipated in the near field of a cement-based repository.