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Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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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.
Uldis Potapovs, J. Russell Hawthorne, Charles Z. Serpan, Jr.
Nuclear Technology | Volume 5 | Number 6 | December 1968 | Pages 389-409
Technical Paper and Note | doi.org/10.13182/NT68-A27965
Articles are hosted by Taylor and Francis Online.
Embrittlement of the Army SM-1A reactor pressure vessel, as modified by the recently completed in-place anneal, was assessed, and an analysis made of its reembrittlement behavior with subsequent radiation service. Experimental results from a surveillance program covering one complete irradiation and annealing cycle are presented, together with a summary of experimental information on the annealing response of the vessel steel (A350-LF1, Modified) from accelerated irradiation programs. These data indicate a 0°F maximum pressure vessel wall Charpy- V 30-ft-lb transition temperature after the in-place anneal vs a −80°F preservice transition temperature (based on the notch ductility properties of a duplicate ring forging). The maximum Charpy- V 30-ft-lb transition temperature of the pressure vessel before the annealing operation was estimated at 190° F. A projection of postanneal pressure vessel lifetime in terms of neutron fluence >0.5 MeV was derived from spectra calculations and the experimentally predicted reirradiation response of the pressure vessel steel. The maximum permissible vessel wall fluence is estimated at 5.5 × 1019 n/cm2 (>0.5 MeV). This is comparable to-124.7 MW-y of reactor operation.