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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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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.”
J.M. Perlado, J. Sanz,a D. Guerra, A.S. Perez
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 709-715
Inertial Fusion | doi.org/10.13182/FST91-A29428
Articles are hosted by Taylor and Francis Online.
The feasibility of the ferritic alloy HT-9 as the main component of the first structural wall (FSW) of inertial confinement fusion (ICF) reactors, such as HIBALL-II or LIBRA, which use thin film liquid protection through porous tubes (INPORT) has been studied in terms of radiation damage and activation. Swelling and shift in the ductile brittle transition temperature (DBTT) have been analyzed in the light of the results of experimental fast breeder reactors, which are demonstrated to be good experimental tools in our ICF range. The good performance of HT-9 is remarkable. An analysis of the generation of new solid transmutants and the depletion of initial constituents is given. Activation has been studied using recycling and shallow land burial (SLB) criteria. The interest has been focussed in a reduced activation HT-9 (Niobium-free). Recycling using HT-9 is shown to be not feasible. SLB waste disposal is also not feasible. The critical role of some short lived isotopes as Pt193, Nb93m, Re186 is analyzed, together with that of the more conventional Re186m, Nb94, Bi210m.