ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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.
P. J. Ring, K. D. Challenger, H. J. Busboom
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 64-74
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31176
Articles are hosted by Taylor and Francis Online.
Burst rupture tests have been carried out on irradiated fuel pin cladding to determine the effect of intergranular attack on burst rupture strength and ductility and so to assess the ability of the weakened cladding to withstand power surge or loss of coolant conditions. The results from this series of tests indicate that the burst rupture strength or yield strength is not drastically reduced by localized attack extending through as much as 35% of the cladding thickness. Ductility values, however, do appear to be substantially reduced. In terms of reactor operation, this suggests that in a transient stress situation the cladding would be able to withstand higher stresses than previously predicted using a wall thinning criteria, based on the maximum depth of cladding attack, but would tolerate far less deformation than unattacked cladding before failure.