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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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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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.
R. E. Williford, D. D. Lanning, C. L. Mohr
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 340-350
Nuclear Fuel | doi.org/10.13182/NT82-A32862
Articles are hosted by Taylor and Francis Online.
An alternate thermal-mechanical behavior model for cracked UO2 pelletized fuel is presented. It is recognized that fuel cracking and relocation cause some of the initial pellet-cladding gap (the “free area”) to be moved into the fuel in the form of cracks. The introduction of this free area into the fuel causes the fuel effective thermal conductivity and effective elastic moduli to be simultaneously reduced to values significantly less than laboratory data for solid pellets. Hooke’s Law and a crack compliance model are used to deduce the effective fuel conductivity and moduli from simultaneous in-reactor measurements of rod power, fuel center temperature, and cladding elongation. The fuel-cladding “gap” is considered as another “crack,” and is also described by the crack compliance model, which predicts that there is always some finite amount of fuel-cladding contact. The primary thermal mechanical feedback mechanism is found to be due to crack closure effects on fuel effective thermal conductivity, rather than gap closure effects on gap conductance.