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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.
M. Kangilaski, F. R. Shober
Nuclear Technology | Volume 5 | Number 4 | October 1968 | Pages 283-285
Technical Paper and Note | Technical Note | doi.org/10.13182/NT68-A28032
Articles are hosted by Taylor and Francis Online.
Prediction of the room-temperature fatigue life of Type-347 stainless steel, irradiated to 5.5 × 1021 and 11 × 1021 n/cm2, was attempted from tensile tests and the use of Manson's relationship. It was found that the total strain vs cycles-to-failure for irradiated Type-347 stainless steel can be predicted reasonably well for total strains of 1 to 2% at both levels of irradiation. However, the predicted fatigue lives were conservative for total strains that are <1% for material irradiated to a fast fluence of 11 × 1021 n/cm2. Not enough experimental data points were available to correlate the measured fatigue life with predicted fatigue life at total strains of <1% for stainless steel irradiated to a fast fluence of 5.5 × 1021 n/cm2.
