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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.
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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.”
David R. Mikkelsen, Clifford E. Singer, Robert J. Goldston
Fusion Science and Technology | Volume 7 | Number 3 | May 1985 | Pages 361-373
Technical Paper | Plasma Engineering | doi.org/10.13182/FST85-A24556
Articles are hosted by Taylor and Francis Online.
The efficiency of plasma heating and current drive expected in the Tokamak Fusion Test Reactor has been computed for various orientations of neutral injection beamlines. Computer codes that model plasma transport and particle orbits have been used to compute power losses caused by “shinethrough,” charge-exchange, intersection of particle orbits with the limiter or wall, and toroidal field ripple, and to compute the effect of finite size particle orbits on penetration of injected beam particles. Less readily quantifiable considerations such as impurity contamination and toroidal plasma rotation are discussed briefly.