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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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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August 2024
Nuclear Technology
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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.”
Bartlomiej Z. Wierzbicki, Steven P. Antal, Michael Z. Podowski
Nuclear Technology | Volume 158 | Number 2 | May 2007 | Pages 261-274
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT07-A3841
Articles are hosted by Taylor and Francis Online.
The ability to predict the shape of gas/liquid interface is important for various multiphase flow and heat transfer applications. Specific issues of interest to nuclear reactor thermal hydraulics include the evolution of the shape of bubbles attached to solid surfaces during nucleation, bubble/surface interactions in complex geometries, etc. The development of an innovative approach to model the time-dependent shape of gas/liquid interfaces is discussed. The proposed approach combines a modified level-set method with an advanced computational fluid dynamics code, NPHASE. The coupled numerical solver can be used to simulate the evolution of gas/liquid interfaces in two-phase flows for a variety of geometries and flow conditions.The novel aspects of the work include the development of direct coupling between the level-set algorithm and the finite-volume code NPHASE, the development of a novel mass conservation algorithm for the level-set method, the analysis of the influence of fluid physical properties on the predicted bubble flow conditions, and the use of a three-dimensional model to simulate gas bubble flow in channels of various geometries and orientations.