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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
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.
L. C. Walters, C. M. Walter
Nuclear Technology | Volume 46 | Number 1 | November 1979 | Pages 134-148
Technical Paper | Material | doi.org/10.13182/NT79-A32386
Articles are hosted by Taylor and Francis Online.
Irradiation-induced creep and swelling of stain-less-steel Experimental Breeder Reactor II (EBR-II) components have been the subjects of intense surveillance programs during the operation of the EBR-II. Dilation, length change, and bow due to creep and swelling of stainless-steel ducts have all been of concern during the operation of the EBR-II, but in no instance have significant reliability or safety problems arisen due to these phenomena. Driver-fuel elements of two different designs have been irradiated to cladding breach. It was demonstrated that metal driver fuel is capable of high burnup when designed for interconnected porosity prior to fuel-cladding contact. Cladding breaches were found either adjacent to the fuel column or in the fuel-restrainer dimpler. The breach mode was intergranular cracking at both locations.