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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.
J. F. Bates, M. M. Paxton, J. L. Straalsund
Nuclear Technology | Volume 20 | Number 2 | November 1973 | Pages 134-135
Technical Note | Material | doi.org/10.13182/NT73-A31349
Articles are hosted by Taylor and Francis Online.
The thermal densification of austenitic stainless steel and the effect of minor alloy variations on this phenomenon have been investigated. Increasing the carbon content of AISI Type-316 stainless steel can produce density changes >0.1% after aging at 1500°F for 100 h. Large additions of phosphorus (0.04 wt%), boron (0.006 wt%), and nitrogen (0.13 wt%) produce no significant density change upon aging. It was concluded that the thermal densification phenomenon observed in austenitic stainless steels is due to the formation of carbides and is linear with the carbon content of the alloy.
