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Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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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.
L. A. Lawrence, D. C. Hata, J. W. Weber
Nuclear Technology | Volume 42 | Number 2 | February 1979 | Pages 195-206
Technical Paper | Thorium Fuel Cycle in a Breeder Economy / Material | doi.org/10.13182/NT79-A32150
Articles are hosted by Taylor and Francis Online.
A significant reduction in and a change in the character of fuel-cladding chemical interaction (FCCI) due to a reduction in the oxygen-to-metal ratio (O/M) was established for uranium-plutonium mixed-oxide fuels clad with 20% cold-worked Type 316 stainless steel irradiated in the Experimental Breeder Reactor II. Fuel pins from the Hanford Engineering Development Laboratory P-23C subassembly at initial fuel O/Ms of 1.94, 1.95, and 1.97 were examined at peak burnups of 1.1, 2.5, and 3.6 at.%. The depth of FCCI increased with increasing burnup and temperature, but the relative effects of fuel O/M did not change. An approximate three-fold reduction in FCCI resulted from a reduction in fuel O/M from 1.97 to 1.95 at ∼3.6 at.%) burnup. The peak FCCI in the lower O/M fuel was ∼5 μm and appeared as a preferential loss of cladding at grain boundaries and slip planes on the cladding inner surface. In contrast, the typical FCCI in the higher O/M (1.97) fuel pin was matrix in character, and penetrated ∼14 μm into the cladding. Thus, FCCI in mixed-oxide fuel can be reduced to negligible levels by lowering the O/M during manufacture of the fuel.