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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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Latest News
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
R. S. Pathania, E. G. McVey
Nuclear Technology | Volume 55 | Number 1 | October 1981 | Pages 178-190
Technical Paper | Materials Performance in Nuclear Steam Generator / Material | doi.org/10.13182/NT81-A32840
Articles are hosted by Taylor and Francis Online.
Denting of steam generator tubes due to rapid corrosion of carbon steel support plates is a serious problem in many reactors on sea or brackish water locations. The objective of this program was to assess the effectiveness of sodium phosphate in minimizing corrosion and denting during leakage of seawater into a steam generator. Corrosion tests at 300°C were conducted on (a) electrically heated tubes of Alloy 800 equipped with crevice devices and exposed to dilute solutions of seawater and sodium phosphate, and (b) Alloys 800 and 600 tubes with carbon steel sleeves exposed to concentrated solutions of seawater and sodium phosphate + seawater. Exposure of heated tubes to seawater caused denting under carbon steel crevices. Addition of sodium phosphate to seawater prevented denting. Concentration factors within crevices were estimated by comparing the corrosion rates from heat transfer and isothermal tests; estimates ranged from 3700 to 6900, depending on the assumptions. Only shallow pitting was observed on the Alloys 800 and 600 tubes