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A new non-destructive method for evaluating  137 Cs activity in spent nuclear fuels was proposed and experimentally demonstrated for physical measurements in burnup credit implementation.  137 Cs activities were quantified using gamma ray measurements and numerical detector response simulations without reference fuels, in which  137 Cs activities are well known. Fuel samples were obtained from a lead use assembly (LUA) irradiated in a commercial pressurized water reactor (PWR) up to 53 GWd/t. Gamma rays emitted from the samples were measured using a bismuth germinate (BGO) scintillation detector through a collimator attached to a hot cell. The detection efficiency of gamma rays with the detector was calculated using the PHITS particle transport calculation code considering the measurement geometry. The relative activities of  134 Cs,  137 Cs, and  154 Eu in the sample were measured with a high-purity germanium (HPGe) detector for more accurate simulations of the detector response for the samples. The absolute efficiency of the detector was calibrated by measuring a standard gamma ray source in another geometry.  137 Cs activity in the fuel samples was quantified using the measured count rate and detection efficiency. The quantified  137 Cs activities agreed well with those estimated using the MVP-BURN depletion calculation code.

Absolute quantification of 137 Cs activity in spent nuclear fuel with calculated detector response function