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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.
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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.”
L. Bromberg, D.R. Cohn, E. Bobrov, N. Diatchenko, R.J. LeClaire, J.E. Meyer, J.E.C. Williams
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 264-269
Alternate Fuels | doi.org/10.13182/FST83-A22879
Articles are hosted by Taylor and Francis Online.
DD-DT operation could provide a significant reduction in tritium breeding requirements in high field tokamak reactors without requiring very large increases in reactor size or plasma beta. Operation with the tritium breeding requirement is of particular interest. The reduced tritium breeding requirement makes possible the use of blanket designs which might be difficult to implement in a DT reactor (for example, LiAl2O3 blankets). The reduced blanket requirement could also be used for excess tritium production. Tradeoffs between tritium breeding and plasma performance requirements are investigated. Illustrative design features are developed for devices using both resistive magnets and superconducting magnets. Parameters for the device with superconducting magnets are BT = 7 T, β = 0.063, R = 9.6 m, a = 2.4 m, γ = 0.8, and Pwall = 2.2 MW/m2.