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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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.
Jerry F. Kerrisk, John O. Barner, Roy L. Petty
Nuclear Technology | Volume 30 | Number 3 | September 1976 | Pages 361-375
Technical Paper | Uranium Resource / Fuel | doi.org/10.13182/NT76-A31650
Articles are hosted by Taylor and Francis Online.
Cladding ovalities or localized oval regions in the cladding have been observed in many advanced liquid-metal fast breeder reactor fuel elements. The occurrence of ovalities can be related to an internal fuel element mechanism, and in particular to a localized nonaxisymmetric fuel-cladding mechanical interaction resulting from fuel cracking and rearrangement. Elastic calculations of the cladding shape in the vicinity of an ovality have been performed using a simplified model of the fuel-cladding mechanical interaction. A comparison between the calculated and measured ovality shapes shows good agreement. The size of ovalities as measured at room temperature has also been related to the size at operating conditions. Both membrane and bending stresses that are associated with ovalities have been calculated. Ovalities observed in advanced fuel elements increase in size with increasing burnup, but are independent of cladding thickness, gap size, and peak linear power. Data from a pair of similar elements with annealed and cold-worked cladding may indicate a significant inelastic deformation associated with ovalities.