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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.”
Yasunori Bessho, Takashi Nakayama, Michiro Yokomi, Katsuma Nakayama, Hiroki Sano, Nobuhiro Kanazawa
Nuclear Technology | Volume 123 | Number 1 | July 1998 | Pages 30-43
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT98-A2877
Articles are hosted by Taylor and Francis Online.
The steam-water power reactor core concept, originally proposed by several Russian engineers, is expected to improve natural uranium utilization through self-sustaining plutonium by using tight-lattice plutonium fuels and large void fraction two-phase flow, and to realize inherent safety characteristics through large neutron leakage from the core by a flat core configuration.Results are described for the core conceptual design for specifications meeting a 500-MW(electric) electricity supply for 13 months of continuous operation and 92 GWd/tonne fuel average discharge exposure. The design has core nuclear thermal-hydraulic characteristics that satisfy the specifications and limitations usually applied to boiling water reactors (BWRs), based on analyses by the three-dimensional multineutron-energy group diffusion analysis program CITATION. Further, its safety characteristics satisfy limitations, usually applied to BWRs, by the steam cooling emergency core cooling system and the reflood system, based on analyses of a loss-of-coolant accident, which is thought to be most critical for a core with a small water inventory, by the general transient analysis program TRAC.