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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.
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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.
G. W. Keilholtz, R. E. Moore, M. F. Osborne
Nuclear Technology | Volume 4 | Number 5 | May 1968 | Pages 330-336
Technical Paper and Note | doi.org/10.13182/NT68-A26398
Articles are hosted by Taylor and Francis Online.
Solid cylindrical specimens (½- × ½-in.) of the monocarbides of Ti, Zr, Ta, Nb, and W, made by 1) hot pressing, 2) slip casting and sintering, and 3) explosion-pressing and sintering, were irradiated at 300 to 700°C. Fast-neutron (> 1 MeV) exposures ranged from 0.8 to 5.4 × 1021 n/cm2 in a fast-neutron flux profile which ranged from 0.6 to 2.6 × 1014 n/(cm2 sec). The order of decreasing fracture of specimens made by 1) and 2) was Ta, Zr, Nb, Ti, and W. Specimens made by 3) not only fractured at lower neutron doses than those made by 1) and 2), but there was also less difference in gross damage among the five carbides. Tungsten carbide expanded in volume by ∼0.6% and the other carbides by 2 to 3% upon exposure to fast doses of 1 to 2 × 1021 n/cm2. Higher doses produced either a decrease in volume toward the initial volume or no further change. Volume changes represented crystal volume changes since there was no grain boundary separation. Less than 50% of the crystal expansion was accounted for by increases in lattice parameters. The major cause of damage to carbides is postulated to result from point defects produced by fast neutrons. It is suggested that most of the initial volume expansion is caused by the formation of defect agglomerates too large to affect measured values of the lattice parameters. Slow neutrons of the irradiation spectrum may have contributed to premature fracturing of explosion-pressed specimens through absorptions by added Co and Ni binder at the grain boundaries.