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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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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Researchers use one-of-a-kind expertise and capabilities to test fuels of tomorrow
At the Idaho National Laboratory Hot Fuel Examination Facility, containment box operator Jake Maupin moves a manipulator arm into position around a pencil-thin nuclear fuel rod. He is preparing for a procedure that he and his colleagues have practiced repeatedly in anticipation of this moment in the hot cell.
W. Jordan, W. L. Bradley, D. L. Olson
Nuclear Technology | Volume 29 | Number 2 | May 1976 | Pages 209-214
Material | doi.org/10.13182/NT76-A31580
Articles are hosted by Taylor and Francis Online.
The effect of stress on the rate of liquid lithium penetration of Armco iron grain boundaries has been determined over a temperature range of 838 to 965 K. The rate of liquid lithium penetration of the Armco iron grain boundary was found to increase with increasing stress for a stress range of 12 to 28 MPa. Specimens stressed to only 12 MPa experienced as much as fifty times the penetration rate of similarly unstressed specimens. The penetration distance has been found to be a single-valued function of creep strain for various combinations of time, temperature, and stress. This relationship of total penetration to total creep strain suggests that the role of stress may be to produce creep strain that ruptures a protective film at the surface, allowing the corrosion rate to proceed at an accelerated rate.