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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.”
Kazuaki Kitoh, Seiichi Koshizuka, Yoshiaki Oka
Nuclear Technology | Volume 135 | Number 3 | September 2001 | Pages 252-264
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT01-A3220
Articles are hosted by Taylor and Francis Online.
In past designs of supercritical water-cooled reactors, the core flow rate has had to be kept high enough to satisfy the minimum deterioration heat flux ratio criterion where the deterioration heat flux is a function of the core flow rate. Refinement of transient criteria related to the fuel rod design is undertaken, and new dominant transient criteria are proposed in which the cladding temperature is <610°C for Type 316 stainless steel and <840°C for Inconel 700 to reduce the balance of the plant and improve the thermal efficiency. The safety analysis for the high-temperature core using these new criteria is carried out. All the analyzed events satisfy the new criteria. A new formula for the heat transfer correlation at supercritical pressure is proposed based on numerical simulation.