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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.
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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.”
S. K. Combs, L. R. Baylor, C. R. Foust, M. J. Gouge, T. C. Jernigan, S. L. Milora, J-F Artaud, A. Géraud
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 419-424
Plasma Fueling, Heating, and Current Drive | doi.org/10.13182/FST98-A11963649
Articles are hosted by Taylor and Francis Online.
High-speed injection of pellets, composed of frozen hydrogen isotopes and multimillimeter in size, is commonly used for core fueling of magnetically confined plasmas for controlled thermonuclear fusion research. Straight guide tubes have typically been used to transport/deliver pellets from the acceleration device to the outside, or magnetic low-field side, of the torus/plasma (distance of −5 to 10 m for most installations). Recently, alternative pellet injection schemes have been used in plasma fueling experiments, including inside launch from the magnetic high-field side on ASDEX-U and top launch (vertically downward) on Tore Supra and DIII-D. These schemes require the use of curved guide tubes in which the pellets are subjected to stresses from centrifugal and impact forces. Thus, with curved guide tubes the speed at which intact pellets can be delivered reliably to the plasma is limited. In impact experiments on flat plates, it was found that deuterium (D2) pellets can survive single collisions at normal velocities in the range 20 to 35 m/s. Several series of tests with various curved guide tube configurations have been carried out, showing that intact pellets can be reliably delivered at speeds of several hundreds of meters per second. The experimental data are summarized and discussed. Also, a model is under development at Tore Supra for predicting these phenomena, and preliminary comparisons with the data are discussed.