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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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.
J. L. Krankota, J. S. Armijo
Nuclear Technology | Volume 24 | Number 2 | November 1974 | Pages 225-233
Technical Paper | Material | doi.org/10.13182/NT74-A31477
Articles are hosted by Taylor and Francis Online.
Recent data and published data on the de-carburization kinetics of Cr—1% Mo steel in sodium from 800 to 1300°F were correlated by expressing changes in bulk carbon content of samples of different thicknesses and geometry as carbon loss per unit of surface area exposed to sodium. This parameter, when plotted as a function of the square root of time, produced straight lines consistent with the expected diffusion control of the decarburization process. New data from this investigation yielded a decarburization rate constant that was in excellent agreement with the correlation obtained from the published data. A design curve prepared from the correlation was used to predict the end-of-life carbon contents of typical steam generator tubes in sodium systems.