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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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.
J. W. Prados, J. L. Scott
Nuclear Technology | Volume 2 | Number 5 | October 1966 | Pages 402-414
Technical Paper and Note | doi.org/10.13182/NT66-A27617
Articles are hosted by Taylor and Francis Online.
A mathematical model for investigating the irradiation behavior of pyrolytic-carbon-coated fuel microspheres has been formulated. The model can be used to study the influence on coated-particle life of a number of design parameters, such as fuel particle density, number of coating layers, and coating thickness, density, and strength. For typical two-layer coated particles, the model predicts two modes of coating failure: 1) failure initiated at the inner coating surface from the combined effects of fuel swelling, fission-gas pressure, and outer coating shrinkage; and 2) failure initiated at the outer coating surface resulting from anisotropic thermal expansion and fast-neutron damage to the pyrolytic carbon structure. To assure long-term irradiation stability, a coated-particle design must incorporate: 1) free volume to accommodate fission gas and fuel swelling; and 2) an outer coating material that exhibits small dimensional changes under fast-neutron irradiation.