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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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
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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.”
K. A. Werley, C. G. Bathke, R. A. Krakowski, R. L. Miller, J. N. DiMarco
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1266-1271
Result of Large Experiment and Plasma Engineering | doi.org/10.13182/FST91-A29515
Articles are hosted by Taylor and Francis Online.
Essential to the achievement of economically compact fusion power cores is the radiation of a large fraction of the plasma heating power uniformly to the first wall, thereby assuring adequate longevity of the divertor impurity control system. The radiation of significant fractions of the heating power from the beta-limited core-plasma region in an RFP, however, requires a corresponding increase in the quality of (non-radiative) confinement. It is shown that radiating ≳ 70% of the total heating power from the core plasma of the TITAN compact reversed-field-pinch (RFP) reactor is possible with non-radiative confinement times that are a large factor (> 15) below classical confinement predictions and are within the present scaling relation based upon extrapolations of the existing RFP transport database. By comparison, the confinement in the ARIES-I tokamak reactor is within a factor of 2 of neo-classical predictions.