Abstract
Application of the CR-39 solid state nuclear track detector for verification of spent CANDU (Canada Deuterium Uranium) fuel was investigated. A new method based on simultaneous measurement of thermal and fast neutron flux distributions in the lateral plane near the front end of the fuel bundle matrix is proposed. A pilot experiment was performed to determine the detector's response to thermal and fast neutrons in near real conditions. Thermal neutron flux spatial distribution was determined in the spent fuel pit of the KANUPP nuclear power plant (Pakistan). A strong near-neighbour effect was found. It was proved that one day of irradiation time is sufficient for in situ measurements. Further improvements of the method are proposed.
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