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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.
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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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.
Henry J. Petroski, John L. Glazik, Jr.
Nuclear Technology | Volume 51 | Number 3 | December 1980 | Pages 303-316
Technical Paper | Mechanics Applications to Fast Breeder Reactor Safety / Reactor | doi.org/10.13182/NT80-A32569
Articles are hosted by Taylor and Francis Online.
A simple model for the cracked cylindrical shell, which employs only familiar concepts from applied mechanics, gives insight into the effects of cracks on structural response. The model provides analytical expressions for plane-strain bending deformations induced by the cracks and enables qualitative and quantitative generalizations to be made about the effects of different sizes and numbers of cracks and different loading conditions. These bending deformations, which are absent in a uniformly pressurized flawless shell, can dominate the response of a deeply cracked shell. The simple model may be calibrated with only two static deflection measurements made on a real shell or determined from a finite element model Then the dynamic response is easily established for arbitrary time-dependent loadings. The predictions of the simple model are in agreement with finite element results and provide conservative bounds on the additional elastic bending deflections induced by cracks in reactor vessels, piping, and other shell-like components.