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• W2103453978 abstract "There are various motives for quantifying plutonium (Pu) in spent fuel assemblies by means of nondestructive assay (NDA) including the following: strengthening the capability of the International Atomic Energy Agency (IAEA) to safeguard nuclear facilities; quantifying shipper/receiver difference; determining the input accountability value at pyrochemical processing facilities; providing quantitative input to burn-up credit assessments and final safeguards measurements at a long-term repository. In order to determine Pu mass in spent fuel assemblies, thirteen NDA techniques were identified that provide information about the composition of an assembly. A key motivation of the present research is the realization that none of these techniques, in isolation, is capable of both (1) quantifying the Pu mass of an assembly and (2) detecting the diversion of a significant number of rods. It is therefore anticipated that a combination of techniques will be required. A 5 year effort funded by the Next Generation Safeguards Initiative (NGSI) of the U.S. DOE was recently started in pursuit of these goals. The first two years of the plan calls for researching all thirteen techniques using Monte Carlo modeling while the final three years involves fabricating hardware and measuring spent fuel. Here, we present the work in two main parts: (1) an overview of this NGSI effort describing the motivations and approach being taken; (2) The preliminary results for one of the NDA techniques - Passive Neutron Albedo Reactivity (PNAR). The PNAR technique functions by using the intrinsic neutron emission of the fuel (primarily from the spontaneous fission of curium) to self-interrogate any fissile material present. Two separate measurements of the spent fuel are made, one with and one without a cadmium (Cd) layer surrounding the fuel assembly. The ratios of the Singles, Doubles and Triples count rates obtained in each case are analyzed; known as the Cd ratios. The primary differences between the two measurements are the neutron energy spectrum and fluence rate in the spent fuel, along with some impact on the detection efficiency which is a consequence of the change in the emerging spectrum. The presence of the Cd layer surrounding the spent fuel assembly hardens the neutron energy spectrum. If the geometry of the measurement situation is unchanged between the two measurements, the change in the Cd ratio between these two measurements can be related to the reactivity of the fuel assembly which in turn can be related to the fissile content." @default.
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• W2103453978 date "2009-01-01" @default.
• W2103453978 modified "2023-09-27" @default.
• W2103453978 title "Nondestructive Determination of Plutonium Mass in Spent Fuel: Preliminary Modeling Results using the Passive Neutron Albedo Reactivity Technique - 10413" @default.
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