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College of Engineering
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dissertation
6
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Nuclear engineering
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"ir_etd"
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Title
Setname
Type
1
A novel multilevel safety-factor centered framework for optimized utilization of research reactors
ir_etd
Text
2
Analysis of process monitoring to support safety and safeguards requirements for a spent nuclear fuel electrorefiner
ir_etd
Text
3
Development of online oxide ion sensor for continuous monitoring of molten nitrate salts for solar energy power plants
ir_etd
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4
The effect of annealing on the reversal of amorphization in plutonium tetrafluoride
ir_etd
Text
5
Effect of pellet-cladding interaction (PCI) and degradation mechanisms on spent nuclear fuel rod mechanical performance during transportation
ir_etd
Text
6
Effects of low fluence neutron bombardment on material properties of aluminum 2024 T-3 and aluminum wire
ir_etd
Text
7
Measurement of thermodynamic properties of rare earth chlorides in molten LiCl-KCl eutectic Salt for waste minimization from pyrochemical processing of spent nuclear fuel
ir_etd
Text
8
Monte Carlo modeling of neutron dosimetry and relative biological effectiveness for the University of Washington Clinical Neutron Therapy System
ir_etd
Text
9
Multiscale modeling of the dosimetric and relative biological effectiveness of diagnostic X-Rays and high linear energy transfer particles
ir_etd
Text
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25
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9