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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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.
Lutz W. Dahlke, Maurice Robkin
Nuclear Technology | Volume 12 | Number 4 | December 1971 | Pages 407-414
Technical Note | Analysis | doi.org/10.13182/NT71-A30992
Articles are hosted by Taylor and Francis Online.
A high-resolution neutron radiographic system has been developed at the University of Washington Nuclear Reactor to radiograph mixed oxide particle fuels. The method was tested without fuel using TiO2, Eu2O3, and RhO2 mixtures as analogs for the oxides of U, 239Pu, and 240Pu, respectively. These analogs have microscopic cross sections similar to the fuel isotopes. Two weight percent PuO2-UO2 fuel rod radiographic analogs were built containing PuO2 analog particle diameter distributions from 0 to 800 μm. These radiographic analogs were radiographed with resonant energy neutrons using the activation transfer neutron detection technique to examine both the homogeneity of the mixed oxide and the imaging of the various diameter PuO2 analog particles. A divergent neutron collimator was designed to successfully complete this study. Also, an experiment was performed to determine the contrast sensitivity of neutron radiography for the radiographic discrimination between the analog for 239PuO2 and the analog for 240PuO2.