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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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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.”
Masabumi Nishikawa
Fusion Science and Technology | Volume 59 | Number 2 | February 2011 | Pages 350-362
Technical Paper | doi.org/10.13182/FST11-A11651
Articles are hosted by Taylor and Francis Online.
The tritium balance in a D-T fusion power reactor to assure a self-sustainable tritium system is discussed in this paper, comparing the amount of tritium consumed in the fueling cycle including the plasma vessel with the amount of tritium generated in the blanket system. It is determined that recovering tritium from the redeposition layer is highly effective in achieving tritium balance. It is also known from this discussion that having a burning plasma with an overall burning efficiency >0.5% is needed to maintain tritium balance. A burning efficiency >3 to 4% is even better because the tritium balance increases. It is also known that a first-wall material having an overall trapping factor >0.005 or that having an overall permeation loss ratio >0.0001 is not desirable because the tritium loss at the plasma vessel becomes too large to maintain the tritium balance. This discussion also finds that a blanket system with an overall breeding ratio of [approximately]1.1 is desirable early in fusion development to maintain a short tritium doubling time.