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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.
David W. Varela, William E. Kastenberg, Vijay K. Dhir
Nuclear Technology | Volume 49 | Number 1 | June 1980 | Pages 102-114
Technical Paper | Nuclear Power Reactor Safety / Reactor Siting | doi.org/10.13182/NT80-A32511
Articles are hosted by Taylor and Francis Online.
The implications of in-channel fuel plugging subsequent to a transient overpower accident in a liquid-metal fast breeder reactor have been investigated. The potential for cooling plugged coolant channels was examined by assuming the formation of a porous blockage in several adjacent subassemblies (from flat-to-flat) at axial locations near the upper plane of the active core. The results of a thermal-hydraulic analysis indicate that for this plugging pattern melting of the blockages with possible melting of the plugged subassemblies will occur. Molten blockages may reenter the active part of the core. Neutron transport calculations indicate that hydro-dynamic disassembly of the core as a direct result of gravity-driven reentry of molten blockages into the active core is unlikely. However, substantial melting and relocation of fuel in the plugged subassemblies could result in a power surge, causing pin failures in previously undamaged subassemblies, and raising again the possibility of hydrodynamic disassembly or whole core propagation. The possibility of fuel melting is directly dependent on the nature and amount of plugging. Further research is needed in this area, as the conditions for plugging are uncertain at the present time.