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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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.”
M. R. Fox, A. B. Hull, T. F. Kassner
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1619-1628
Material and Tritium | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29573
Articles are hosted by Taylor and Francis Online.
Susceptibility of Types 316NG, 316, and 304 stainless steels (SS) to stress corrosion cracking was investigated in slow-strain-rate tests (SSRTs) in oxygenated water that simulates important parameters anticipated in first-wall/blanket systems. The water chemistry was based on a computer code that yielded the nominal concentrations of radiolytic species produced in an aqueous environment under conditions expected in the International Thermonuclear Experimental Reactor (ITER). Actual SSRTs were performed in a less benign, more oxidizing reference environment at temperatures of 52 to 150°C. Predominantly ductile fracture was observed in Type 316NG and nonsensitized Types 316 and 304 SS SSRT specimens that were strained to failure in a reference ITER water chemistry. The failure behavior of Type 304 SS specimens, heat-treated to yield sensitization values of 2, 3, and 20 Coulomb (C)/cm2 by the electrochemical potentiokinetic reactivation technique, demonstrated that the degree of sensitization dramatically affected susceptibility to intergranular stress corrosion cracking. Ranking for resistance to stress corrosion cracking in simulated ITER water by electron microscopy and SSRT parameters, i.e., failure time, ultimate strength, total elongation, and stress ratio, is 304 SS (EPR = 20<2 C/cm2)<316NG SS.