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Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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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.”
T. Ozawa, T. Abe
Nuclear Technology | Volume 156 | Number 1 | October 2006 | Pages 39-55
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT156-39
Articles are hosted by Taylor and Francis Online.
Annular fuel is very beneficial for fast reactors because of its availability for both high power and high burnup. Most of the annular pellets irradiated up to high burnup showed central-hole shrinkage due to deformation and restructuring during irradiation. This shrinkage has a great influence on power-to-melt, which is a main factor in deciding the maximum power in the fuel design. To predict precisely the central-hole shrinkage during irradiation, the CEPTAR code was developed and verified by using the results of various experiments. In this code, the central-hole diameter is decided in accordance with the law of conservation of mass by using the radial profile of fuel density computed with the void migration model, and its deformation caused by the thermal expansion, swelling, and creep is computed by stress-strain analysis using the approximation of plane strain. Furthermore, this code can also estimate the effect of joint oxide gain (JOG) observed in a gap between the cladding and the fuel pellet with high burnup, which tends to decrease the fuel swelling and to improve the gap conductance due to deposition of solid fission product to the JOG layer. In this paper, an outline of the CEPTAR code and the results of verification are presented.