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Experimental Evaluation of the Differential die-Away Pulsed-Neutron Technique for the Fissile Assay of Hot Irradiated Fuel Waste

机译:用于热辐照燃料废物裂变分析的差模离心脉冲中子技术的实验评价

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Hot irradiated fuel waste packages containing self neutron sources up to 10 exp 7 n/s may be assayed successfully with a 25-mg exp 239 Pu detection sensitivity using a differential die-away fissile assay system based on a Sandia-designed 14-MeV neutron generator. With a minor design change, our system can accommodate contact gamma dose rates up to 10 exp 4 R/h with no loss of fissile assay sensitivity. (ERA citation 07:042622)

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