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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.
Lee A. James
Nuclear Technology | Volume 26 | Number 1 | May 1975 | Pages 46-53
Technical Paper | Material | doi.org/10.13182/NT75-A24403
Articles are hosted by Taylor and Francis Online.
Linear-elastic fracture mechanics techniques were employed to characterize the crack growth behavior of SA-351 Grade CF8 cast stainless steel over the temperature range 75 to 1200°F (24 to 649° C). In general, crack growth rates increased with increasing test temperature. The crack growth rates in the cast material generally fell within or below the scatter bands for wrought Types 304 and 316 material tested under similar conditions, implying that data obtained on wrought material would likely yield conservative results for crack growth analyses on cast structures.
