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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.
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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.”
Yuh-Ming Ferng, Tay-Jian Liu, Chien-Hsiung Lee
Nuclear Technology | Volume 116 | Number 1 | October 1996 | Pages 66-77
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35312
Articles are hosted by Taylor and Francis Online.
Thermal-hydraulic responses in the station blackout experiment conducted at the IIST facility are simulated through the use of the advanced system code RELAP5/MOD3. Typical behaviors occurring in the IIST station blackout transient are characterized by secondary boiloff, primary saturation and pressurization, and subsequent core uncovery and heatup. As the coolant inventory within the steam generator secondary system boils dry, the primary system pressure increases as a result of degradation of the heat removal ability of the steam generator secondary side. This pressurization phenomenon causes the pressurizer safety valve to open and the primary coolant to deplete through the valve, causing the core to eventually become uncovered. The same response can be exactly simulated by the current model. The current calculated results show fairly good agreement with the experimental data, but the timing of the events occurring in the station blackout transient is calculated earlier than the measured value. The overall comparison of key parameters between the calculated results and IIST test data, however, reveals that the current RELAP5/MOD3 model can provide reasonable station blackout modeling for simulating longterm system behavior.