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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.”
Eric Pinton, Bernard Duret, Georges Berthoud
Nuclear Technology | Volume 127 | Number 3 | September 1999 | Pages 332-351
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT99-A3005
Articles are hosted by Taylor and Francis Online.
To improve the knowledge of the behavior of a UF6 container during a fire, an experimental project called Tenerife was conducted by the Commissariat à l'Energie Atomique. Three tests with UF6 with different kinds of heating and temperature furnaces were carried out. The main information obtained from monitoring temperature and pressure during the heating tests is as follows:1. The presence of a strong thermal contact resistance at the solid UF6-steel interface.2. The rupture of the solid crust at the top of the container, a crust formed during container cooling after filling, for a pressure reaching 1.5 bars (triple point). This leads to the beginning of boiling heat transfer and notably film boiling, followed by transition boiling and nucleate boiling.3. The appearance of the liquid stratification with the beginning of nucleate boiling. It can accelerate the rise in pressure because of the reduction of mass transfer by condensation to the liquid-gas interface. This stratification is preserved with the natural convection regime that replaces the nucleate boiling after the end of heating.4. After rupture of the upper UF6 crust, the pressure increase may be delayed by different wetting of the UF6 on the steel wall.Also, these tests were allowed to build and validate a scenario that has been reproduced in a numerical model.