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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.
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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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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.
Keith E. Asmussen, Paul Wälti
Nuclear Technology | Volume 15 | Number 3 | September 1972 | Pages 359-365
Technical Paper | Reactor | doi.org/10.13182/NT72-A16033
Articles are hosted by Taylor and Francis Online.
The plutonium loadings were determined for a test element for irradiation in the Peach Bottom HTGR. The test element is a graphite circular cylinder with an array of eight fuel rods in a circular pattern. The fuel rods contain dense spherical kernels of PuO2 or PuO2/3 ThO2. Be cause of the strong Pu resonances, the heterogeneity effects in the test element are strongly marked. A code for treating this rather complicated problem rigorously was not available. Thus the problem was simulated within a onedimensional transport code by equating three collision probabilities. The heterogeneities were seen to result in significant grain selfshielding, rod selfshielding, and mutual shielding of the rods. The Pu loading for the central fuel body of the test element was determined to be 19.0 g.