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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.
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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 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. 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.”
T. A. Heltemes, G. A. Moses
Fusion Science and Technology | Volume 52 | Number 4 | November 2007 | Pages 927-931
Technical Paper | Inertial Fusion Technology: Drivers and Advanced Designs | doi.org/10.13182/FST07-A1612
Articles are hosted by Taylor and Francis Online.
The introduction of magnetic cusp fields into the High Average Power Laser (HAPL) reactor design is to prevent target ions from interacting with the armor layer. Diverting the ions and preventing their impact on the chamber armor eases thermal design constraints considerably. The BUCKY code was used to simulate thermal loads for the candidate armor materials tungsten and silicon carbide.Parametric analysis was done to ascertain the peak temperature rise in the armor due to X-rays from the HAPL target thermonuclear ignition. Temperature values as a function of chamber armor radius were obtained using initial conditions of T0 = 600 °C and xenon buffer gas pressures of 66.7, 666.7 and 6666.1 mPa (0.5, 5 and 50 mTorr). The armor radius was decreased until thermal thresholds were met (2400 °C and 1000 °C for tungsten and silicon carbide, respectively) to determine the minimum allowable radius of the HAPL chamber.A second set of parametric simulations were performed at xenon gas initial pressures of 666.7 and 6666.1 mPa (5 and 50 mTorr) and temperature of 600°C to a time of 5 ms to observe the effect of re-radiation from the buffer gas on the surface temperature of tungsten and silicon carbide.