Round-robin analysis of highly depleted lithium for Generation IV nuclear reactor applications

Sean R. Scott, Johnny Williams, Sara Mastromarino, Norbert Gajos, Christian Berry, Ian Anderson, Steven Shen, Trent R. Graham, Cole Hexel, Josh Wimpenny, Jacob Brookhart, Alan Kruizenga

Research output: Contribution to journalArticlepeer-review

Abstract

Lithium reference materials containing unnaturally high abundances of 7Li are not currently available, which poses quality control problems for highly depleted lithium materials (i.e., depleted in 6Li) required for Generation IV nuclear reactors. This study presents an interlaboratory comparison of a lithium carbonate (NIST SRM924a) containing nominally natural isotopic abundances (∼92.4 % Li-7) and a highly depleted lithium hydroxide material (∼99.95 % Li-7). The natural lithium isotope abundances of NIST SRM924a are confirmed, and the 6Li/7Li ratio of the lithium hydroxide ranged from 0.000399 to 0.000436 with an average of 0.000428 ± 0.000023 (2SD, n = 9). Going forward this material can be used as quality control for analytical work involving highly depleted lithium.

Original languageEnglish
Article number113664
JournalNuclear Engineering and Design
Volume429
DOIs
StatePublished - Dec 1 2024

Funding

This work was supported under the U.S. Department of Energy (DOE) Gateway for Accelerated Innovation in Nuclear (GAIN) program administered by Idaho National Laboratory (Voucher 23-31236). NMR spectroscopy was performed, in part, using resources at the Environmental Molecular Sciences Laboratory (EMSL, grid.436923.9), a DOE Office of Science User Facility sponsored by the Office of Biological and Environmental Research at PNNL. Pacific Northwest National Laboratory is a multi-program national laboratory operated for the U.S. DOE by Battelle Memorial Institute under contract number DE-AC05-76RL01830. Dr. Jehanne Gillo at the Office of Science Isotope Program is acknowledged for organizing national lab participants. Two reviewers are acknowledged for their comments on the initial submission of the manuscript. This work was supported under the U.S. Department of Energy (DOE) Gateway for Accelerated Innovation in Nuclear (GAIN) program administered by Idaho National Laboratory. Pacific Northwest National Laboratory is a multi-program national laboratory operated for the U.S. DOE by Battelle Memorial Institute under contract number DE-AC05-76RL01830. Dr. Jehanne Gillo at the Office of Science Isotope Program is acknowledged for organizing national lab participants. Two reviewers are acknowledged for their comments on the initial submission of the manuscript.

FundersFunder number
Biological and Environmental Research
Pacific Northwest National Laboratory
U.S. Department of Energy
Office of Science
BattelleDE-AC05-76RL01830
Idaho National Laboratory23-31236

    Keywords

    • Lithium
    • Mass Spectrometry
    • Molten Salt Reactors

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