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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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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.”
M. Z. Hasan, T. Kunugi, M. Seki, M. Yokokawa, H. Ise, H. Kaburaki, The ARIES team
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 908-912
Advanced Reactor | doi.org/10.13182/FST91-A29460
Articles are hosted by Taylor and Francis Online.
The response of ARIES-I divertor plate to hard plasma disruptions has been analyzed numerically by a two-dimensional transient heat transfer code. For ARIES-I, the estimated thermal quench time is 0.3 msec and the average heat flux is 8.8×109 W/m2 with a peaking factor of 5. The divertor plate is made of 2.5 mm diameter SiC tubes with wall thickness of 0.5 mm and coated with a 2 mm layer of tungsten on the plasma facing side. The analysis predicts a total material erosion per disruption of about 111 µm without vapor shield and 48 µm with a simple vapor-shield model. The designated 1 mm of the tungsten coating for disruption is expected to last about 20 disruptions. A two-dimensional thermo-fluid dynamic analysis of the melt layer under the influence of buoyancy and surface tension forces has been performed. The results tend to imply that the melt layer is relatively unaffected during the disruption, especially for short thermal quench time.