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Division Spotlight
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.
L. A. Lawrence, J. A. Christensen
Nuclear Technology | Volume 12 | Number 4 | December 1971 | Pages 367-374
Technical Paper | Fuel | doi.org/10.13182/NT71-A30986
Articles are hosted by Taylor and Francis Online.
For UO2-25 wt% PuO2, the quantity kdT was established at 49 ± 5 W/cm, where Ts = 700°C, k is the fuel thermal conductivity, and Ts and Tm refer to fuel surface and melt temperatures, respectively. This result is obtained from measurements on six individual fuel pins. Each pin was surrounded by a calorimeter consisting of a heavy-walled aluminum sleeve with thermocouples at two radial positions. Heat generation rates measured calorimetrically were supplemented by postirradiation bumup analyses for 140 Ba, 141 Ce, and 95Zr. Fuel pins were irradiated for 10 h at steady-state peak heat ratings after which they were rapidly quenched to preserve structures representative of peak power operation. Fractional fuel melting was correlated with heat rating and the correlation extrapolated to zero melting to yield melting heat rating. Flux depression corrections are required to apply these measurements, which were made in a thermal flux, to fast flux environments. These were obtained by measuring radial burnup profiles in several irradiated cross sections and numerically integrating the results.