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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.”
R.D. Pillsbury, Jr., R.J. Thome, B.A. Smith
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1065-1069
Ignition Device | doi.org/10.13182/FST91-A29484
Articles are hosted by Taylor and Francis Online.
The poloidal field (PF) coil system in a tokamak must provide the flux swing and the equilibrium and shaping field distributions required to create, maintain, and control the plasma during the discharge. The present design for CIT calls for an 11.8 MA plasma in a double null configuration with a major radius of 2.59 m, a minor radius of 0.795 m, and an elongation (at the 95% flux surface) of 2.0. The toroidal field at the major radius is 9 T. The central solenoid is self-supporting and the TF coils wedge under the Lorentz load. The previous design point called for the TF and PF to buck against each other in order to lower the stresses in both. That design called for an 11 MA, 10 T plasma with a major radius of 2.14 m and a minor radius of 0.66 m. The impact on the PF system of this change in the design point is assessed.