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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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.”
Tay-Jian Liu, Yea-Kuang Chan, Yuh-Ming Ferng, Chien-Yeh Chang
Nuclear Technology | Volume 129 | Number 2 | February 2000 | Pages 187-200
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3056
Articles are hosted by Taylor and Francis Online.
The thermal-hydraulic phenomena of inadequate core cooling caused by a cold-leg small-break loss-of-coolant accident (SBLOCA) were investigated experimentally at the Institute of Nuclear Energy Research Integral System Test facility. The experiments were performed under the conditions of different break sizes (0.5 and 2%) in the cold leg followed by failure of the high-pressure injection system. The primary system cooldown is implemented by the secondary-side depressurization. The effectiveness of early initiation of the recovery action on reactor safety and related thermal-hydraulic phenomena are examined. The initiation criterion for recovery action considered here is determined by core water levels instead of core exit temperature based on the current emergency operating procedures. The impact of emergency core-cooling flow bypass phenomenon may significantly deteriorate the effectiveness of the recovery operation for a cold-leg SBLOCA. The results showed that the early initiation of secondary-side depressurization can effectively minimize the risk of core damage by preventing fuel rods from heating up throughout the transient. In addition, the core suffers a rather moderate thermal stress during the cooldown process.