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Neutron dosimeter materials development and characterization
In 1971, the Isotope Research Materials Laboratory (IRML) at the Oak Ridge National Laboratory (ORNL), began a neutron dosimeter development program. The main goal of the program is to produce neutron dosimeter materials for use in determining the neutron energy spectra, flux, fluence and burnup in fast reactor environments. Since 1971, many developments have been made which have reduced the fabrication cost and improved the characterization of the dosimeter materials. The IRML program, which now includes preparation of dosimeters that can be used in light water, controlled thermonuclear as well as fast breeder reactor environments, will be summarized with particular emphasis on materials development and characterization