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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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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.
J. R. Coombe, R. P. Shogan
Nuclear Technology | Volume 9 | Number 3 | September 1970 | Pages 396-401
Material | Symposium on Theoretical Models for Predicting In-Reactor Performance of Fuel and Cladding Material | doi.org/10.13182/NT70-A28793
Articles are hosted by Taylor and Francis Online.
The effect of temperature on radiation characteristics and subsequent material properties after cryogenic temperature irradiation is analyzed. To date the materials tested have included hot pressed block beryllium, Ti-5% Al-2.5% Sn ELI (Al10AT), and an aluminum alloy 2219. These materials have been irradiated at liquid nitrogen temperatures (140°R) and tensile tested without any intervening warm-up. Some of the liquid nitrogen irradiated and tested material data as well as room temperature data are presented. The properties investigated have included ultimate tensile strength, percent elongation, and fracture toughness. Usually, ductility and the decrease in the magnitude of this property as a function of irradiation is of more vital interest to the designer. The experimental program conducted for some of the NERVA candidate materials is reported and areas of additional investigations for application to advanced NERVA designs are briefly discussed.