Title:
Validation of Transmission Densitometry for Holdup Characterization in Salt-Wetted MSR Components
Validation of Transmission Densitometry for Holdup Characterization in Salt-Wetted MSR Components
Author(s)
Bruner, Jesse
Advisor(s)
Dewji, Shaheen
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Abstract
In-situ measurements of Molten Salt Reactor (MSR) salt deposits, known as holdup, may be performed using various non-destructive assay (NDA) techniques during operation, reprocessing, or after draining. In this project, we evaluate the efficacy of using transmission densitometry for characterization of non-radioactive holdup in salt-wetted reactor components at a laboratory scale. Specifically, the sensitivity of a 2x2 NaI(Tl) scintillation detector is evaluated through the measurement of gamma-ray transmission through variable deposition thicknesses in salt-wetted components. Measurements are performed with Ba-133, Co-57, Co-60, and Cs-137 gamma-ray sources, with pipe segments and a heat exchanger composed of stainless-steel alloy 316 (SS316). This technique is shown to be sensitive to detecting density changes in a pipe segment and heat exchanger due to FLiNaK(+EuF3) holdup inside of each component using the relationship between the transmission source energies, the attenuation properties of the metals and salt, and the detection efficiency. Experimental results are used to inform a Monte-Carlo transport model in the radiation transport code, MCNP, capable of simulating the detector response with parameterization of geometry, salt composition, and deposition profile.
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Date Issued
2024-11-20
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Text
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Thesis