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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
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 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. 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.”
Brian L. Smith
Nuclear Technology | Volume 175 | Number 3 | September 2011 | Pages 663-680
Technical Paper | NURETH-13 Special / Thermal Hydraulics | doi.org/10.13182/NT11-A12514
Articles are hosted by Taylor and Francis Online.
Within the framework of the responsibilities of the Organisation for Economic Co-operation and Development/Nuclear Energy Agency (NEA), three international writing groups (WGs) were set up in 2003 to produce state-of-the-art reports on specific aspects of the use of computational fluid dynamics (CFD) in addressing nuclear reactor safety (NRS) issues. Three reports followed on (a) the use of best practice guidelines in producing reliable computational results, (b) the status of the validation database for single-phase CFD applications to NRS, and (c) the extensions needed to the codes for application to two-phase NRS problems. The present paper summarizes the contents of the second of these documents and reports on the more recent activity of establishing a Web portal to act as a dynamic database for the material contained in the document. The Web pages can be reached via the NEA Web site and have been constructed using Wiki software, which enables users to readily find information they need in their respective application areas via active links, as well as to interactively support the maintenance of the site by contributing to the regular updating of the material. As a result of this endeavor, an up-to-date access point to the validation databases cataloged by the WG has been established, and a means has been provided for users to contribute with new material, thus keeping the information topical.