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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.”
Masato Takahashi
Nuclear Technology | Volume 135 | Number 3 | September 2001 | Pages 230-240
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT01-A3218
Articles are hosted by Taylor and Francis Online.
A new method for off-gas source estimation in plants with nondefective fuel is proposed. This method based on the activity ratio between 138Xe and 88Kr is able to directly estimate the off-gas source using only measurement data. The 138Xe to 88Kr activity ratio is decided on the basis of the fissile irradiation with the different neutron spectrum in the core region and the fission fragment emission rate into coolant. This method was applied to actual plant data, and it was demonstrated that the dominant source of off-gas in a plant with nondefective fuel is Pu produced by the burnup of uranium impurities in the core structure. The concentration of uranium impurities in cladding estimated by this method is consistent with the result of neutron activation analysis.
