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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 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.”
L. G. Miller, J. M. Beeston, P. Y. Hsu, B. L. Harris
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 427-432
Materials Engineering | doi.org/10.13182/FST83-A22901
Articles are hosted by Taylor and Francis Online.
The lifetime of hollow beryllium pebbles in a hybrid fusion blanket was estimated using the existing radiation damage data base. The ductility of the irradiated beryllium at 400 to 500°C was estimated as ∼3%, and the loading stresses produced a strain of <0.3%. The failure analysis was based on the maximum stress theory. The principal stresses calculated were thermal and swelling. The estimated lifetimes for beryllium pebbles were <2 yr for those near the first wall of the blanket, >2 yr for those near the center, and >9 yr for those near the back wall. An overall average lifetime of 2.6 yr was calculated for the hollow beryllium pebbles. The snap-ring fuel form, not considered in this analysis, is expected to give longer beryllium lifetimes, provided stress concentration effects are not present.