ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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!
Latest Magazine Issues
Jul 2024
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Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
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.”
Ralf Wittmaack
Nuclear Technology | Volume 137 | Number 3 | March 2002 | Pages 194-212
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT02-A3268
Articles are hosted by Taylor and Francis Online.
To reduce the radiological consequences of postulated severe accidents, the design of future European nuclear reactors includes measures to avoid basemat penetration in case of a core meltdown. The considered retention schemes include a temporary retention of the debris in the reactor pit followed by the spreading of the accumulated molten corium with subsequent flooding and cooling.To contribute to the verification of such concepts, numerical simulations of the spreading process were performed with the CORFLOW code. These are based on an extensive verification and validation effort, i.e., the code has also been applied successfully to several flow, heat transfer, and phase transition problems of water, glycerol, cerrotru- (low-melting Bi-Sn alloy), and thermite- and corium-melts.Physical and numerical methods are described as well as code applications to analytical solutions, spreading experiments, and reactor corium-spreading processes.