Year
2023
File Attachment
finalpaper_542_0512011235.pdf431.64 KB
Abstract
Molten salts play a crucial role as electrolytes in the pyroprocessing of spent nuclear fuels, as well
as being used as fuel salt in molten salt reactors (MSRs). These salts contain special nuclear
materials that are dissolved within them, and accurate knowledge and monitoring of their inventory
is necessary for nuclear materials accounting and safeguards purposes. However, determining the
total mass of molten salts is a difficult task due to the complicated shapes of containers in
pyroprocessing, and density variation caused by fission, on-line refueling, temperature differential,
and changes in composition over time during an MSR operation. In recent years, an innovative
technique called radioactive tracer dilution (RTD) coupled with gamma spectroscopy has been
proposed and evaluated as a potential means of accurately measuring the total mass of molten salt
for pyroprocessing of spent nuclear fuels. In this study, 22Na was used as a radioactive tracer, and
LiCl-KCl based tracer salt that bears 22NaCl was prepared and spiked into the molten LiCl-KClUCl3 salt for uranium electrorefining, a critical step for pyroprocessing. To evaluate the potential
application of the 22Na based RTD for mass monitoring of the molten salt system in MSRs, a small
amount of MgCl2-KCl-UCl3 (depleted uranium) fuel salt was irradiated in-core in a research
reactor at The Ohio State University and then analyzed for the fission products’ gamma spectrum.
The primary objective of this irradiation was to evaluate the potential gamma spectrum
interference at 1274.5 keV of 22Na peak as well as the low energy peaks from 154Eu. In this paper,
the feasibility and challenges of 22Na-based radioactive tracer dilution for mass measurement of
molten salt systems were summarized, and some approaches for addressing the challenges were
proposed for future research.