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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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.
G. R. Handley
Nuclear Technology | Volume 14 | Number 1 | April 1972 | Pages 71-75
Technical Paper | Session on Physics of Nuclear Materials Safeguards / Fuel | doi.org/10.13182/NT72-A31100
Articles are hosted by Taylor and Francis Online.
The criticality safety of water-sprinkled arrays of enriched uranium metal on 20-in. center-to-center spacing was investigated using KENO, a multigroup Monte Carlo criticality calculation program. The effects of array size and unit apparent density on the optimum-density interspersed water moderation were analyzed. It was shown that larger arrays of enriched uranium require a lower density of interspersed hydrogenous moderator for optimum moderation than do similar smaller arrays. Also, it was shown that when the density of dry uranium metal units is decreased from full density without changing the mass or the center-to-center spacing of the units, while maintaining optimum interspersed hydrogenous moderation, the neutron multiplication of the array at first decreases, then increases beyond that of the array of full density units. The initial decrease of the neutron multiplication of the array may not be true in general for all arrays.