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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.”
Kresna Atkhen, Georges Berthoud
Nuclear Technology | Volume 142 | Number 3 | June 2003 | Pages 270-282
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT03-A3389
Articles are hosted by Taylor and Francis Online.
Within the framework of severe reactor accident studies, we present experimental and numerical parametric studies on debris bed coolability. Data are provided by the SILFIDE multidimensional experimental facility at Electricité de France. The bed is composed of inductively heated steel sphere beads (diameters ranging from 2 to 7.18 mm) contained in a 50- × 60- × 10-cm vessel. Numerical computations are obtained with MC3D REPO developed by Commissariat à l'Energie Atomique.Because of heterogeneous power distribution within the bed, two definitions (mean and local) for the critical heat flux (CHF) are proposed. Even in the first case, the CHF was higher than the Lipinsky one-dimensional flux. As the power is being increased, temperature plateaus above saturation temperature are observed. An analysis is proposed, based on possible different hydrodynamic flow configurations occurring in postdryout regimes. In some experiments, some spheres were superficially molten and stacked together, but globally, the bed was still coolable.The influence of operational parameters such as bottom coolant injection, height of the water, fluidization of upper particles, and subcooled liquid injection on dryout phenomena and CHF values are also described.The MC3D-REPO calculations assuming a thermal equilibrium between the three phases gives results in accordance with experimental data.