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*Small pieces of indium foil have been universally adopted by many nuclear facilities for the purpose of screening personnel exposed in criticality accidents because any neutron-induced activity of indium foil can be measured with survey meters. The authors performed experiments in which the counting efficiency of a survey meter to radiation from activated indium foil was evaluated using a 252 Cf neutron source. In those experiments pieces of indium foil were irradiated outside an aluminum tube containing a 252 Cf source, all of which was placed inside an annular PMMA cylinder moderator. The count rates to indium activity were then measured with a portable GM survey meter. Reference values of the activity of 115m In and 116m In were evaluated using measurements with a germanium detector and MCNP-4C2 calculations, resulting in the counting efficiency of a survey meter being evaluated to be 0.6 %. This result then allowed appropriate doses to be converted from the count rates to be applied in the screening procedure.

Relationship between Induced Indium Activity and Count Rates of Survey Meters Used to Screen Personnel Exposed in Criticality Accidents