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首页> 美国政府科技报告 >Monte Carlo Calculational Design of an NDA Instrument for the Assay of Waste Products from High Enriched Uranium Spent Fuels
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Monte Carlo Calculational Design of an NDA Instrument for the Assay of Waste Products from High Enriched Uranium Spent Fuels

机译：用于高浓度铀废燃料废物检测的NDa仪器的monte Carlo计算设计

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The Monte Carlo design of the waste assay region of a dual assay system, to be installed at the Fluorinal and Storage Facility, is described. The instrument will be used by the facility operator to assay high-enriched spent fuel packages and waste solids produced from dissolution of the fuels. The fissile content discharged in the waste is expected to vary between 0 and 400 g of exp 235 U. Material accountability measurements of the waste must be obtained in the presence of large neutron (0.5 x 10 exp 6 n/s) and gamma (50,000 R/hr) backgrounds. The assay system employs fast-neutron irradiation of the sample, using a 5 mg exp 252 Cf source, followed by delayed neutron counting after the source is transferred to storage. Calculations indicate a +-4-g (2 sigma) assay for a waste canister containing 300 g of exp 235 U is achievable with an end-of-life (1 mg) exp 252 Cf source and a background rate of 0.5 x 10 exp 6 n/s. (ERA citation 05:006626)

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