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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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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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.”
Yoshiyuki Kataoka, Tadashi Fujii, Michio Murase
Nuclear Technology | Volume 116 | Number 1 | October 1996 | Pages 127-135
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT96-A35317
Articles are hosted by Taylor and Francis Online.
To evaluate the heat release characteristics of a primary containment vessel (PCV) external spray (one of the PCV cooling systems utilizing the steel PCV wall as the heat transfer medium), the thermal-hydraulic characteristics of the falling liquid film on the PCV surface have been investigated experimentally. Then, the performance of the PCV external spray cooling system was evaluated using the experimental findings. The following results were obtained: 1. Heat transfer coefficients of the falling liquid film under steady-state conditions were increased as the film flow rate per unit length of the liquid film width increased, and they agreed with Wilke’s correlation within about ±15%. 2. The PCV surface temperature, when preheated up to 150°C, which is the supposed PCV temperature under a severe accident, decreased below 100°C within a few seconds when the PCV external spray was initiated, and boiling on the PCV surface could not be maintained. 3. Heat transfer coefficients of the falling liquid film under transient conditions were higher initially due to the boiling effect; however, they decreased rapidly and approached those under steady-state conditions. 4. The PCV external spray for the conceptually designed PCV could suppress the PCV pressure below the design goal under a severe accident (failure of core cooling under low pressure). The maximum PCV pressure decreased as the spray flow rate increased and as the ratio of the PCV surface covered by the falling liquid film increased.