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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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.
Douglas C. Hunt, Deanne Dickinson
Nuclear Technology | Volume 30 | Number 2 | August 1976 | Pages 190-214
Technical Paper | Criticality Array Data and Calculational Method / Chemical Processing | doi.org/10.13182/NT76-A31615
Articles are hosted by Taylor and Francis Online.
The , albedo, interaction potential, weighted interaction Oak Ridge Gaseous Diffusion Plant solid-angle, s/v surface density, fraction critical surface density, and equilateral hyperbola methods are compared by attempting to apply them to 14 different example arrays. The example arrays are distinguished by the type of fissile material in the array units and by the number of units in each array. Arrays with units of Pu(95) metal, U(93) metal, damp U(93)O2, dry Pu(95)O2, U(93)O2(NO3)2 solution, Pu(95)(NO3)4 solution, or U(5)O2F2 solution are considered. It is concluded that if the user has access to a Monte Carlo code such as KENO, he is better off using it than any of the other models for criticality evaluations of specific problems. The remainder of the models are most useful in establishing possible designs for a fissile storage or processing facility. The albedo method is found to be the preferred solid-angle technique, while the s/v surface density method and the method are the most comprehensive and useful of the semiempirical techniques. The s/v method is easier to apply and covers more possible contingencies (e.g., array flooding or persons in arrays), while the method is more difficult to use but has added flexibility, broader applicability, and yields more analytical scaling relations between array parameters.