Europium diffusion in IG-110 nuclear graphite

Weilert, Taylor M.; Walton, Kyle L.; Loyalka, Sudarshan K.; Brockman, John Douglas

doi:10.1016/j.jnucmat.2022.153544

Europium diffusion in IG-110 nuclear graphite

Journal Article · Sun Jan 16 23:00:00 EST 2022 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2022.153544· OSTI ID:1977375

Weilert, Taylor M. ^[1]; Walton, Kyle L. ^[2]; Loyalka, Sudarshan K. ^[2]; Brockman, John Douglas ^[2]

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

Europium diffusion in graphite has been recognized to be of interest in high-temperature gas reactor safety analysis, particularly as an indicator of strontium diffusion. However, no measurements of europium diffusion coefficients have been reported in the literature. In this work, the effective diffusion coefficient of europium was measured using a time-release method. Natural europium was loaded into pre-milled unirradiated IG-110 graphite spheres using a pressurized acid digestion vessel. The time-release experiments were performed in the temperature range 1823 K – 1973 K using a SiC diffusion cell connected to an inductively-coupled plasma mass spectrometer (ICP-MS) via a He gas line. Finally, the results of this work are: D_{Eu, IG-110} = (1.5 x 10^-3m²/s) exp $$(\frac{-2.87\mathrm{x}10^{5} J/mol}{RT})$$ This effective diffusion coefficient can be used to aid in predictive modelling of europium transport in HTGRs.

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:: 1977375

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: C Vol. 561; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (21)

Calibration of a system for measurements of diffusion coefficients of fission products in HTGR/VHTR core materials Carter, Lukas M.; Brockman, John D.; Loyalka, Sudarshan K. Journal of Radioanalytical and Nuclear Chemistry, Vol. 307, Issue 3 https://doi.org/10.1007/s10967-015-4633-0	journal	December 2015
Laboratory determinations of strontium diffusion coefficients in graphite Sandalls, F. J.; M. R. Walford, mrs. Journal of Nuclear Materials, Vol. 62, Issue 2-3 https://doi.org/10.1016/0022-3115(76)90023-4	journal	November 1976
Distribution of fission products in irradiated graphite materials of HTGR fuel assemblies: Third and fourth OGL-1 fuels Hayashi, K.; Kikuchi, T.; Kobayashi, F. Journal of Nuclear Materials, Vol. 136, Issue 2-3 https://doi.org/10.1016/0022-3115(85)90008-X	journal	November 1985
In-pile release behavior of metallic fission products in graphite materials of an htgr fuel assembly Hayashi, K.; Kobayashi, F.; Minato, K. Journal of Nuclear Materials, Vol. 149, Issue 1 https://doi.org/10.1016/0022-3115(87)90498-3	journal	June 1987
Release behavior of metallic fission products from HTGR fuel particles at 1600 to 1900°C Minato, Kazuo; Ogawa, Toru; Fukuda, Kousaku Journal of Nuclear Materials, Vol. 202, Issue 1-2 https://doi.org/10.1016/0022-3115(93)90027-V	journal	June 1993
A novel approach to fabricating fuel compacts for the next generation nuclear plant (NGNP) Pappano, P. J.; Burchell, T. D.; Hunn, J. D. Journal of Nuclear Materials, Vol. 381, Issue 1-2 https://doi.org/10.1016/j.jnucmat.2008.07.032	journal	October 2008
Measurement of cesium diffusion coefficients in graphite IG-110 Carter, L. M.; Brockman, J. D.; Loyalka, S. K. Journal of Nuclear Materials, Vol. 460 https://doi.org/10.1016/j.jnucmat.2015.01.055	journal	May 2015
First high temperature safety tests of AGR-1 TRISO fuel with the Fuel Accident Condition Simulator (FACS) furnace Demkowicz, Paul A.; Reber, Edward L.; Scates, Dawn M. Journal of Nuclear Materials, Vol. 464 https://doi.org/10.1016/j.jnucmat.2015.05.006	journal	September 2015
ICP-MS measurement of diffusion coefficients of Cs in NBG-18 graphite Carter, L. M.; Brockman, J. D.; Robertson, J. D. Journal of Nuclear Materials, Vol. 466 https://doi.org/10.1016/j.jnucmat.2015.08.023	journal	November 2015
ICP-MS measurement of iodine diffusion in IG-110 graphite for HTGR/VHTR Carter, L. M.; Brockman, J. D.; Robertson, J. D. Journal of Nuclear Materials, Vol. 473 https://doi.org/10.1016/j.jnucmat.2016.03.001	journal	May 2016
Diffusion of cesium and iodine in compressed IG-110 graphite compacts Carter, L. M.; Brockman, J. D.; Robertson, J. D. Journal of Nuclear Materials, Vol. 476 https://doi.org/10.1016/j.jnucmat.2016.04.024	journal	August 2016
ICP-MS measurement of silver diffusion coefficient in graphite IG-110 between 1048K and 1284K Carter, L. M.; Seelig, J. D.; Brockman, J. D. Journal of Nuclear Materials, Vol. 498 https://doi.org/10.1016/j.jnucmat.2017.10.009	journal	January 2018
Measurement of effective Sr diffusion coefficients in IG-110 graphite Weilert, T. M.; Walton, K. L.; Loyalka, S. K. Journal of Nuclear Materials, Vol. 555 https://doi.org/10.1016/j.jnucmat.2021.153102	journal	November 2021
Effective diffusivity of Ag and migration of Pd in IG-110 graphite Weilert, T. M.; Walton, K. L.; Loyalka, S. K. Journal of Nuclear Materials, Vol. 559 https://doi.org/10.1016/j.jnucmat.2021.153427	journal	February 2022
Initial examination of fuel compacts and TRISO particles from the US AGR-2 irradiation test Hunn, John D.; Baldwin, Charles A.; Montgomery, Fred C. Nuclear Engineering and Design, Vol. 329 https://doi.org/10.1016/j.nucengdes.2017.09.017	journal	April 2018
The AGR-3/4 fission product transport irradiation experiment Collin, Blaise P.; Demkowicz, Paul A.; Petti, David A. Nuclear Engineering and Design, Vol. 327 https://doi.org/10.1016/j.nucengdes.2017.12.016	journal	February 2018
Status of the very high temperature reactor system Fütterer, Michael A.; Fu, Li; Sink, Carl Progress in Nuclear Energy, Vol. 77 https://doi.org/10.1016/j.pnucene.2014.01.013	journal	November 2014
Suitability of binary oxides for molecular-beam epitaxy source materials: A comprehensive thermodynamic analysis Adkison, Kate M.; Shang, Shun-Li; Bocklund, Brandon J. APL Materials, Vol. 8, Issue 8 https://doi.org/10.1063/5.0013159	journal	August 2020
Numerical Study on Hydrogen Flow Behavior in Two Compartments with Different Connecting Pipes Liu, HanChen; Cao, XueWu Science and Technology of Nuclear Installations, Vol. 2017 https://doi.org/10.1155/2017/4709503	journal	January 2017
Diffusion of Lanthanides and Actinides from Graphite at High Temperatures Orth, C. J. Nuclear Science and Engineering, Vol. 9, Issue 4 https://doi.org/10.13182/NSE61-A25905	journal	April 1961
Coated Particle fuel for high Temperature gas Cooled Reactors Verfondern, Karl; Nabielek, Heinz; Kendall, James M. Nuclear Engineering and Technology, Vol. 39, Issue 5 https://doi.org/10.5516/NET.2007.39.5.603	journal	October 2007

Similar Records

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 · OSTI ID:2417707

Comparative analysis of microstructure and reactive sites for nuclear graphite IG-110 and graphite matrix A3

Journal Article · Fri Oct 04 00:00:00 EDT 2019 · Journal of Nuclear Materials · OSTI ID:1605205

Post-irradiation Experiment on IG-110 and A3-3 Graphites for HTGR - 18494

Conference · Mon Nov 14 23:00:00 EST 2016 · OSTI ID:23032663

Related Subjects

36 MATERIALS SCIENCE
Diffusion coefficient
Europium
Graphite
HTGR
IG-110
Materials Science
Nuclear Science & Technology

Europium diffusion in IG-110 nuclear graphite

Citation Formats

References (21)

Similar Records

Related Subjects