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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.”
M. Tetenbaum, A. K. Fischer, C. E. Johnson
Fusion Science and Technology | Volume 7 | Number 1 | January 1985 | Pages 53-56
Technical Paper | Blanket Engineering | doi.org/10.13182/FST85-A24517
Articles are hosted by Taylor and Francis Online.
The solubility of LiOH in Li2O was measured as a function of temperature and partial pressure of H2O. For these measurements, solid Li2O at temperatures of 973 to 1273 K was equilibrated with moisture in a helium carrier gas stream; monitoring the moisture content in the helium carrier gas allowed determination of LiOH solubility. The slope of the curve for the partial pressure of H2O(g) versus LiOH solubility was observed to be 0.6 and is interpreted as an indication of nonideality in the system. For a given partial pressure of H2O, the solubility of LiOH increased with increasing temperature. As a consequence of these measurements, the solubility of tritium (as LiOT) in a breeding blanket of solid Li2O is expected to be low under anticipated fusion reactor environments [e.g., 0.56 wppm tritium at 1000K for 1 Pa (10−5 atm) T2O].
