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Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
Meeting Spotlight
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.
Kurt Goldmann, John M. Mckee
Nuclear Technology | Volume 6 | Number 4 | April 1969 | Pages 321-331
Technical Papers and Note | doi.org/10.13182/NT69-A28340
Articles are hosted by Taylor and Francis Online.
Liquid potassium was circulated between 1200 and 1600°F in 31 Type-316 stainless-steel thermal convection loops and one forced circulation loop. Each loop contained a string of niobium-1% zirconium (Nb-1% Zr) alloy and stainless-steel test specimens positioned along the entire heated leg. To follow corrosion as a function of time and temperature, the test specimens were examined at 500 to 2500 h intervals. Controlled additions of interstitial impurities to the potassium were made in some thermal convection loops at the start of the test. Oxygen additions to the potassium sharply accelerated the initial rate of Nb-1% Zr surface removal but produced no identifiable oxide film or microstructural changes. The initially high weight-loss rates, observed in oxygen addition loops, decayed rapidly with time, returning essentially to normal rates (in the absence of further oxygen additions) after 2500 h. Oxygen additions produced very little effect on the stainless-steel corrosion rates, presumably due to rapid gettering of the added oxygen by the Nb-1% Zr. Similar tests in a forced circulation loop, with potassium velocities past the test specimens 18 times higher than in the thermal convection loops, showed that any effects of velocity on the Nb-1% Zr corrosion rate were far overshadowed by effects that are assumed to be related to oxygen in the potassium.