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Division Spotlight
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.
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.
James M. Taub
Nuclear Technology | Volume 28 | Number 1 | January 1976 | Pages 77-86
Technical Paper | Fuels for Pulsed Reactor / Fuel | doi.org/10.13182/NT76-A31540
Articles are hosted by Taylor and Francis Online.
The use of pulsed reactors for the evaluation of materials and components has been on the increase and pulsed reactors to handle large components are under consideration. Pulsed reactors currently operate at a 30 to 50 u sec pulse width and a neutron yield of 5 × 1016 fission/pulse; improved capability would move toward even smaller pulse widths and neutron yields in the 1017 fission/pulse range. The gamma phase U—10 Mo alloy with highly enriched uranium has been the fuel alloy used in most pulsed reactors. The fabrication of U—10 Mo alloy fuel plates for the new SPR-III reactor at Sandia Laboratories, Albuquerque, New Mexico, required a detailed review of all processing operations because of the highly enriched uranium and the related criticality considerations. It was necessary to cast the maximum allowable mass of highly enriched uranium (36 kg) in order to make a single fuel plate. The low carbon impurity level specified was obtained with the formulation of a new and highly successful composite coating material for graphite crucibles and molds. The plate distortions which occur in water quenching the alloy from the 950°C gamma phase to room temperature were eliminated by quenching between cold platens in a hydraulic press. Typical mechanical properties obtained on cast, heat treated plates were 930 MPa yield strength, 940 MPa tensile strength, 12.9% elongation in 25.4 mm, and 35.4% reduction in area.