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Evaluation of NDA Techniques for Quantification of the Plutonium Content in Mixed-Oxide Spent Nuclear Fuel by Destructive Analysis
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Monte-Carlo Burnup Calculation Uncertainty Quantification and Propagation Determination
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Safeguards System Development for a Pebble-Fueled HTGR
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Use of Self-Interrogation Neutron Resonance Densitometry to Measure the Fissile Content in a BWR 9×9 Spent Fuel Assembly
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