Diffusion of cesium in oxidized and unoxidized IG-110 nuclear graphite

Weilert, T. M.; Walton, K. L.; Loyalka, S. K.; Brockman, J. D.

doi:10.1016/j.jnucmat.2022.153949

Diffusion of cesium in oxidized and unoxidized IG-110 nuclear graphite

Journal Article · Wed Jul 27 00:00:00 EDT 2022 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2022.153949· OSTI ID:2417707

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Univ. of Missouri, Columbia, MO (United States); OSTI
Univ. of Missouri, Columbia, MO (United States)

Time-release diffusion measurements of cesium have been conducted over the temperature range 1073 K – 1973 K on oxidized and unoxidized IG-110 graphite. Four cesium concentrations were tested to investigate the concentration dependence of the diffusion coefficient. Two levels of oxidation were tested and compared to unoxidized concentration-matched sets to explore the effects of graphite oxidation. Here, the results demonstrate that cesium diffusion coefficient in unoxidized IG-110 graphite is independent of concentration within the range 34 – 163 µg Cs/g_graphite. Above this, the effective cesium diffusion coefficient changes with concentration. The diffusion coefficient was increased by a factor of 2–12 in the oxidized set with 7.8% mass loss. These results can be used to aid predictive modeling of cesium diffusion in HTGR cores.

View Accepted Manuscript (DOE)

Research Organization:: Univ. of Missouri, Columbia, MO (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE), Nuclear Energy University Program (NEUP)

Grant/Contract Number:: NE0000118

OSTI ID:: 2417707

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: C Vol. 570; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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