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Division Spotlight
Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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.”
Ki-Yong Choi, Seok Cho, Hyoung-Kyu Cho, Chul-Hwa Song
Nuclear Technology | Volume 170 | Number 1 | April 2010 | Pages 54-67
Technical Paper | Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Thermal Hydraulics | doi.org/10.13182/NT10-A9445
Articles are hosted by Taylor and Francis Online.
The 6 × 6 reflood test facility for Advanced Thermal Hydraulic Evaluation of Reflood phenomena (ATHER) has been operated by Korea Atomic Energy Research Institute to investigate the reflooding phenomena in a rod bundle. A series of bottom reflood tests was carried out by varying several parameters affecting the reflooding process such as the flooding velocity, inlet coolant subcooling, system pressure, initial maximum rod wall temperature, and rod power. Subsequently, counterpart reflood tests of rod bundle heat transfer data from The Pennsylvania State University were conducted for comparison, focusing especially on the effects of the heat flux on the peak cladding temperature (PCT) and the quenching behavior. The best-estimate thermal-hydraulic system analysis code MARS3.1 was assessed with the obtained data to investigate the parametric effects on its prediction accuracy. It was found that the prediction accuracy of the PCT is reasonable on the whole but that the MARS code predicts delayed quenching behavior compared with the data, especially for high heat flux conditions. In particular, the prediction becomes deteriorated downstream, far from the inlet of the test section.