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
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.
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
Jan 2024
Latest Journal Issues
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.”
Panos J. Karditsas, Neill P. Taylor
Fusion Science and Technology | Volume 44 | Number 1 | July 2003 | Pages 227-231
Technical Paper | Fusion Energy - Divertor and Plasma-Facing Components | doi.org/10.13182/FST03-A338
Articles are hosted by Taylor and Francis Online.
As part of the European Power Plant Conceptual Study, two different divertor designs were proposed, based on previous work on HETS (High Efficiency Thermal Shield) performed at FZK and ENEA. The coolant is helium gas at pressures in the range 10-14 MPa and the inlet temperatures are in the range of 500-800°C. The geometrical complexity of the designs made prediction of heat transfer coefficients, needed for conducting thermal and structural analysis, difficult, and the calculated values from empirical correlations uncertain. This paper presents and summarises results of thermal-fluid calculations performed on both divertor concepts and gives estimates of effective values of heat transfer coefficients based on the local flow conditions and temperature distributions. The agreement of calculations with experimental values for similar conditions, inspires confidence in results from such calculations, and demonstrates that computational fluid dynamic finite element codes can accurately predict behaviour, and can be used to optimise the designs.