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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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. Karsten, G. Mühling, H. Plitz
Nuclear Technology | Volume 28 | Number 2 | February 1976 | Pages 208-215
Technical Paper | Fuel | doi.org/10.13182/NT76-A31561
Articles are hosted by Taylor and Francis Online.
The carbide fuel which will be introduced into the SNR for the first time after 1980, will be helium bonded, with a low linear heat rating and fuel density. This design appears to be the least problematic one for a medium burnup goal. The restriction to a moderate design arises to a certain extent from economical and safety reasons, but mainly can be attributed to uncertainties in extrapolation to a very high performance level. This can be demonstrated in a general discussion valid for both oxide and carbide. Due to the fact that the fuel elements of a large power plant with a peak burnup of 100 MWd/kg will undergo radiation damages, which cannot be demonstrated by experimental fuel pins in test (DFR, Rapsodie) or demonstration reactors (SNR, PFR, etc.) for the first generation, licensable maximum burnups will be in the range of 70 MWd/kg. It is impossible to perform tests outside the future large power plants with a relevant neutron dose-to-fuel burnup ratio. Therefore, in the German program a continuous development has been underway since 1968, in which separate medium burnups and neutron doses are demonstrated in test and demonstration reactors. In addition, the fuel fabrication process will be steadily improved in a pilot fabrication plant.