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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. Iseli
Fusion Science and Technology | Volume 48 | Number 1 | July-August 2005 | Pages 629-633
Technical Paper | Tritium Science and Technology - Materials Interaction and Permeation | doi.org/10.13182/FST05-A1004
Articles are hosted by Taylor and Francis Online.
Knowledge of the levels of tritium in the First Wall (FW) coolant and components of ITER is important for public and operator safety and waste management. To overcome the large uncertainty of plasma wall interaction and physical properties, a basic set of properties is theoretically calculated for the dissolved tritium atoms in a perfect Beryllium (Be) lattice. These properties are combined with models for tritium trapping by lattice imperfections including the equilibrium conditions between gaseous, dissolved and trapped hydrogen isotopes. The 3 models for trapping by impurities, radiation damage and surface defects are adjusted to experimental solubilities, to tritium release experiments from irradiated samples and to outgassing of hydrogen isotopes from the JET FW. An elastic lattice model evaluates the activation energy of diffusion. For the calculations, the code DIET (Diffusion, Implantation and Equilibrium Trapping) was developed, which includes tritium trapping with time-dependent trap concentrations of multiple trap sites. The sensitivity analysis, with the expected deviations from the basic properties provides confidence that tritium permeation is below one gram in ITER for a neutron load of 0.3 MWa/m2 within 10 years.