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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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.”
Lance J. Agee
Nuclear Technology | Volume 128 | Number 2 | November 1999 | Pages 131-138
Technical Paper | RETRAN | doi.org/10.13182/NT99-A3020
Articles are hosted by Taylor and Francis Online.
An overview is presented of the important RETRAN related events that have occurred since the previous International RETRAN Conference, which was held in October 1995. First, an overview is given of the general state of the industry, focusing on problems with the implementation of new reactor fuels and the formation at the Electric Power Research Institute (EPRI) of the Robust Fuel Program. Second, the conclusion from the EPRI-sponsored design review of RETRAN-3D is given, as well as the status of RETRAN related licensing submittals to the U.S. Nuclear Regulatory Commission and the current status of the RETRAN-3D licensing submittal. Third, GPU Nuclear Corporation's use of RETRAN-3D and a cross-comparison of RETRAN-02 licensing analyses for all Three Mile Island Chapter 14 (Chapter 15 for most plants) events are summarized. Fourth, a vision of the future is outlined, which includes the evolving integration of EPRI codes into interactive suites similar to CPM-3, CORETRAN, and RETRAN-3D. Also outlined are the evolution of RETRAN for balance-of-plant analysis, supporting CHECWORKS leak applications, and the use of the thermal-hydraulic engine in operator training simulators.