Experimental evaluation of the differential die-away pulsed-neutron technique for the fissile assay of hot irradiated fuel waste
Description:
Hot irradiated fuel waste packages containing self neutron sources up to 10/sup 7/ n/s may be assayed successfully with a 25-mg /sup 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/sup 4/ R/h with no loss of fissile assay sensitivity.
Date:
January 1, 1982
Creator:
Caldwell, J.T. & Kunz, W.E.
Item Type:
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Partner:
UNT Libraries Government Documents Department