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Division Spotlight
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.
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.”
Gordon Kohse, David Carpenter, Yi Yuan, Pavel Hejzlar, Mujid Kazimi
Nuclear Technology | Volume 160 | Number 1 | October 2007 | Pages 150-168
Technical Paper | Annular Fuel | doi.org/10.13182/NT07-A3889
Articles are hosted by Taylor and Francis Online.
This paper describes an irradiation test of high-power-density internally and externally cooled annular fuel samples in the 5-MW Massachusetts Institute of Technology (MIT) research reactor MITR-II. The design of the irradiation facility is briefly reviewed, with an emphasis on the thermal-hydraulic behavior of the irradiation capsules. The irradiation test is described, including the thermal history of the two irradiated samples. A discussion of the observed asymmetrical temperature profiles is provided. Results of preliminary postirradiation examination consisting of collimated gamma scans of the irradiation capsules to confirm burnup estimates and estimate fission gas release (FGR) are also presented. It is concluded that the vibropacked fuel samples' FGR is below 1%, and that is within the predictable range by a specially equipped FRAPCON model.