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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.”
Kyle E. Brumback, Seth R. Cadell, Brian G. Woods (Oregon State Univ)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 701-713
An investigation into the onset of natural circulation during a depressurized conduction cooldown was conducted at the High Temperature Test Facility at Oregon State University. In this set of four tests, the primary loop of the facility was filled with helium and then heated until a temperature difference across the core was: 125°C, 250°C, 375°C, and 500°C. The Reactor Cavity Simulation Tank (RCST) was filled with nitrogen gas. During the heating phase of the test the primary loop and RCST were held at pressures greater than 130 kPa. Once the desired temperature was achieved the primary loop and RCST pressures were reduced to 112 and 110 kPa, respectively. The cold leg break valve was opened and then the hot leg break valve was opened. The hot helium in the primary loop began to flow into the RCST displacing the cold nitrogen, in a lock exchange flow. Once the density differences equalized in the two tanks, a natural circulation will develop as the gas is heated in the core, flows from into the RCST through the upper plenum, upcomer, and cold leg. Once cooled in the RCST the gas then flows through the hot leg and returns into the core. This paper discusses the findings for each of the four tests and compares the time required for the natural circulation to establish as a function of temperature across the core.