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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.
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.”
Kevin W. Brinckman, Mark A. Chaiko
Nuclear Technology | Volume 133 | Number 1 | January 2001 | Pages 133-139
Technical Note | Thermal Hydraulics | doi.org/10.13182/NT01-A3164
Articles are hosted by Taylor and Francis Online.
The TRAC-BF1 computer code is used to analyze the fluid pressure response for a waterhammer event in a water-filled pipe with entrapped air. TRAC's capabilities are assessed by comparison against a method-of-characteristics (MOC) solution of pressure-wave propagation in a gas/liquid interface system. A vertically oriented pipe with air initially occupying up to 10% of the pipe volume is considered. A step increase in pressure is imposed at the inlet, and the fluid pressure response in the pipe is calculated. TRAC correctly predicts that the peak pressure with entrapped air is substantially higher than it would be in a purely liquid system. For an initial air volume equal to 10% of the pipe volume, the peak pressure calculated by TRAC compares within 1% of the MOC result. For smaller initial air volumes, TRAC underpredicts the peak pressure disturbance by up to 14% compared to the MOC. The TRAC solution exhibits a degree of long-term artificial damping, but in all cases it captures the basic features of the pressure response for a waterhammer event in a system with entrapped air.