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Division Spotlight
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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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.”
C. A. Ordonez, R. Carrera, W. D. Booth, M. E. Oakes
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1740-1744
Impurity Control and Plasma-Facing Component | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29593
Articles are hosted by Taylor and Francis Online.
Tritium retention at the wall is an important consideration for the operation of a fusion ignition experiment. In this paper, the fusion ignition experiment IGNITEX is considered and tritium implantation, retention, and removal from the first wall are investigated. For the analysis, a new implantation model is used. The implantation model incorporates analytical fits to detailed Monte Carlo calculations of the implantation profile. The Monte Carlo calculations include the effect of the surface floating potential on the ion distribution function at the plasma-surface interface. Tritium retention at the first wall is shown to increase with incident fluence until saturation occurs. The isotope-exchange process for use in tritium removal at the wall is studied.