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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.”
K.H. Schrader, A. Perujo
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1416-1419
Tritium Storage, Distribution, and Transportation | Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30610
Articles are hosted by Taylor and Francis Online.
This paper presents the design and first tests of a portable uranium getter bed where the drawbacks of the standard available transport getters have been either mitigated or eliminated. The heating of the bed is made internally, ie, heating the uranium by a close contact of the heater element with the material, therefore reducing the temperature of the wall that is shielded from the heat source. Keeping the wall relatively cold reduces the tritium losses by permeation and the heat load to the glovebox. With this design the maximum operating temperature of the external wall is ≈ 373 K, this corresponds to a nominal reduction in permeation of four orders of magnitude.