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- W1971293683 abstract "A modulated 252Cf source assay system “Shuffler” based on fast-or-thermal-neutron interrogation combined with delayed-neutron counting has been developed for the assay of fissile material. The 252Cf neutron source is repetitively transferred from the interrogation position to a shielded position while the delayed neutrons are counted in a high efficiency 3He neutron well-counter. For samples containing plutonium, this well-counter is also used in the passive coincidence mode to assay the effective 240Pu content. The design of an optimized neutron tailoring assembly for fast-neutron interrogation using a Monte Carlo Neutron Computer Code is described. The Shuffler system has been applied to the assay of fuel pellets, inventory samples, irradiated fuel and plutonium mixed-oxide fuel. The system can assay samples with fissile contents from a few milligrams up to several kilograms using thermal-neutron interrogation for the low mass samples and fast-neutron interrogation for the high mass samples. Samples containing 235U−238U, or 233U−Th, or UO2−PuO2 fuel mixtures have been assayed with the Shuffler system." @default.
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- W1971293683 date "1978-06-01" @default.
- W1971293683 modified "2023-09-26" @default.
- W1971293683 title "A 252Cf based nondestructive assay system for fissile material" @default.
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- W1971293683 doi "https://doi.org/10.1016/0029-554x(78)90057-5" @default.
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