Spent fuel nondestructive assay integrated characterization from active neutron, passive neutron, and passive gamma

Spent nuclear fuel comprises a wide range of irradiated isotopic material compositions, and characterization through nondestructive measurements is beneficial in verifying declared parameters before the fuel is placed in storage, final disposal, and/or reprocessed. This paper discusses results from...

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Veröffentlicht in:Nuclear instruments & methods in physics research. Section A, Accelerators, spectrometers, detectors and associated equipment Accelerators, spectrometers, detectors and associated equipment, 2020-12, Vol.988
Hauptverfasser: Trellue, Holly Renee, McMath, Garrett Earl, Trahan, Alexis Chanel, Favalli, Andrea, Burr, Thomas Lee, Sjoland, Anders, Backstrom, Ulrika
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container_title Nuclear instruments & methods in physics research. Section A, Accelerators, spectrometers, detectors and associated equipment
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creator Trellue, Holly Renee
McMath, Garrett Earl
Trahan, Alexis Chanel
Favalli, Andrea
Burr, Thomas Lee
Sjoland, Anders
Backstrom, Ulrika
description Spent nuclear fuel comprises a wide range of irradiated isotopic material compositions, and characterization through nondestructive measurements is beneficial in verifying declared parameters before the fuel is placed in storage, final disposal, and/or reprocessed. This paper discusses results from three nondestructive assay instruments, including passive gamma, passive neutron, and active neutron methods, that measured fifty spent fuel assemblies at the Clab interim storage facility in Sweden. Here, integrated analysis of the measurements from the three different instruments allowed parametric assessments of cooling time, burnup, neutron multiplication, fissile mass, initial enrichment, and decay heat of each individual fuel assembly. Passive gamma measurements were found to be the most beneficial in predicting cooling time, passive neutron for determining burnup, active neutron in estimating initial enrichment, and both passive and total neutron for multiplication correlations. Fissile mass was best estimated using any combination of any two of the instruments such that corrections for isotopic changes in the fuel could be accounted for with the first set of measurements and multiplication of the assembly in the second. In conclusion, the nondestructive assay technologies demonstrated through this effort enhance the characterization of spent nuclear fuel assemblies.
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subjects Differential die-away
International safeguards
Nondestructive assay
NUCLEAR PHYSICS AND RADIATION PHYSICS
Spent fuel characterization
title Spent fuel nondestructive assay integrated characterization from active neutron, passive neutron, and passive gamma
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