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    Neutron Radiography of Nuclear Fuels at the Battelle Research Reactor


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    The development and use of neutron radiography at the Battelle Research Reactor (BRR) are described. Neutron radiography was conducted in the reactor pool and in a facility located outside the reactor pool. Neutron radiographs were obtained by both the direct and transfer techniques. In general, indium conversion screens were perferred. The handling techniques included still and scanning methods. The problems encountered while working in water are also described.

    The uses of neutron radiographs of nuclear fuel materials include determination of the physical condition of the material, dimensional data, enrichment, and burn-up. Neutron radiographs were used to determine the location of PuO2 particles, less than 50 μm in size, in a UO2-PuO2 fuel material. Dimensions were determined to ± 50 μ when measurements were made. Neutron radiography was a useful tool in nuclear fuel development work at the BRR.


    neutron radiography, nondestructive tests, nuclear fuels, nuclear research and test reactors, neutron counters

    Author Information:

    Kok, KD
    Researcher, Battelle Columbus Laboratories, Columbus, Ohio

    Committee/Subcommittee: E07.05

    DOI: 10.1520/STP33922S