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Title: Redistribution of radionuclides in irradiated AGR-1 UCO TRISO fuel after 1800 °C safety testing

Abstract

Release of radionuclides from intact tristructural-isotropic (TRISO) coated particle fuel at normal and accident conditions is a primary metric of fuel performance. The distribution of fission products and actinides in the TRISO layers of individual particles provides insight on radionuclide transport and release behavior and was determined using scanning electron microscopy analysis. Particles were isolated from an irradiated fuel compact (AGR-1 Compact 4-4-2) and analyzed as-irradiated or after individual particle safety-testing at 1800 °C for 650 h. Particles were selected for comparison based on their remaining 110mAg fission product inventory. These comparisons corroborated the observation that the 110mAg inventory is a marker for relative irradiation temperature based on observed radionuclide distribution in the SiC layer. The comparison also indicated that the in-pile behavior influences the fission product and actinide species interactions with the TRISO layers during high temperature exposure after irradiation. The analysis confirms both palladium and uranium diffusion, as well as other species, are active in the UCO TRISO fuel system at 1800 °C and that palladium transport is active at lower temperatures relative to uranium. While diffusion across the SiC layer was observed, the intact nature of the SiC layer after the 1800 °C, 650-h exposure indicates themore » SiC layer maintained its functionality as a fission product barrier by mitigating release of radionuclides at beyond accident margin temperatures.« less

Authors:
ORCiD logo [1];  [1]; ORCiD logo [1];  [1]; ORCiD logo [1]; ORCiD logo [1]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1661266
Grant/Contract Number:  
AC05-00OR22725
Resource Type:
Journal Article: Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 542; Journal Issue: 0; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
TRISO; AGR; Post-irradiation examination; Fission products; Silicon Carbide

Citation Formats

Gerczak, Tyler J., Seibert, Rachel, Hunn, John D., Baldwin, Charles, Montgomery, Fred C., and Morris, Robert Noel. Redistribution of radionuclides in irradiated AGR-1 UCO TRISO fuel after 1800 °C safety testing. United States: N. p., 2020. Web. doi:10.1016/j.jnucmat.2020.152453.
Gerczak, Tyler J., Seibert, Rachel, Hunn, John D., Baldwin, Charles, Montgomery, Fred C., & Morris, Robert Noel. Redistribution of radionuclides in irradiated AGR-1 UCO TRISO fuel after 1800 °C safety testing. United States. doi:10.1016/j.jnucmat.2020.152453.
Gerczak, Tyler J., Seibert, Rachel, Hunn, John D., Baldwin, Charles, Montgomery, Fred C., and Morris, Robert Noel. Tue . "Redistribution of radionuclides in irradiated AGR-1 UCO TRISO fuel after 1800 °C safety testing". United States. doi:10.1016/j.jnucmat.2020.152453.
@article{osti_1661266,
title = {Redistribution of radionuclides in irradiated AGR-1 UCO TRISO fuel after 1800 °C safety testing},
author = {Gerczak, Tyler J. and Seibert, Rachel and Hunn, John D. and Baldwin, Charles and Montgomery, Fred C. and Morris, Robert Noel},
abstractNote = {Release of radionuclides from intact tristructural-isotropic (TRISO) coated particle fuel at normal and accident conditions is a primary metric of fuel performance. The distribution of fission products and actinides in the TRISO layers of individual particles provides insight on radionuclide transport and release behavior and was determined using scanning electron microscopy analysis. Particles were isolated from an irradiated fuel compact (AGR-1 Compact 4-4-2) and analyzed as-irradiated or after individual particle safety-testing at 1800 °C for 650 h. Particles were selected for comparison based on their remaining 110mAg fission product inventory. These comparisons corroborated the observation that the 110mAg inventory is a marker for relative irradiation temperature based on observed radionuclide distribution in the SiC layer. The comparison also indicated that the in-pile behavior influences the fission product and actinide species interactions with the TRISO layers during high temperature exposure after irradiation. The analysis confirms both palladium and uranium diffusion, as well as other species, are active in the UCO TRISO fuel system at 1800 °C and that palladium transport is active at lower temperatures relative to uranium. While diffusion across the SiC layer was observed, the intact nature of the SiC layer after the 1800 °C, 650-h exposure indicates the SiC layer maintained its functionality as a fission product barrier by mitigating release of radionuclides at beyond accident margin temperatures.},
doi = {10.1016/j.jnucmat.2020.152453},
journal = {Journal of Nuclear Materials},
issn = {0022-3115},
number = 0,
volume = 542,
place = {United States},
year = {2020},
month = {12}
}

Journal Article:
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