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Title: Initial examination of fuel compacts and TRISO particles from the US AGR-2 irradiation test

Abstract

Post-irradiation examination was completed on two as-irradiated compacts from the US Advanced Gas Reactor Fuel Development and Qualification Program’s second irradiation test. These compacts were selected for examination because there were indications that they may have contained particles that released cesium through a failed or defective SiC layer. The coated particles were recovered from these compacts by electrolytic deconsolidation of the surrounding graphitic matrix in nitric acid. The leach-burn-leach (LBL) process was used to dissolve and analyze exposed metallic elements (actinides and fission products), and each particle was individually surveyed for relative cesium retention with the Irradiated Microsphere Gamma Analyzer (IMGA). Data from IMGA and LBL examinations provided information on fission product release during irradiation and whether any specific particles had below-average retention that could be related to coating layer defects or radiation-induced degradation. A few selected normal-retention particles and six with abnormally-low cesium inventory were analyzed using X-ray tomography to produce three-dimensional images of the internal coating structure. Four of the low-cesium particles had obviously damaged or degraded SiC, and X-ray imaging was able to guide subsequent grinding and polishing to expose the regions of interest for analysis by optical and electron microscopy. Additional particles from each compact weremore » also sectioned and examined to study the overall radiation-induced microstructural changes in the kernel and coating layers.« less

Authors:
ORCiD logo [1];  [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1];  [2];  [2];  [2]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  2. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1435300
Grant/Contract Number:  
AC05-00OR22725
Resource Type:
Journal Article: Accepted Manuscript
Journal Name:
Nuclear Engineering and Design
Additional Journal Information:
Journal Volume: 329; Journal Issue: C; Journal ID: ISSN 0029-5493
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; High-temperature gas-cooled reactor (HTGR) fuel; Tristructural isotropic (TRISO) particles; Post-irradiation examination (PIE); Cesium release; SiC failure

Citation Formats

Hunn, John D., Baldwin, Charles A., Montgomery, Fred C., Gerczak, Tyler J., Morris, Robert Noel, Helmreich, Grant W., Demkowicz, Paul, Harp, Jason, and Stempien, John. Initial examination of fuel compacts and TRISO particles from the US AGR-2 irradiation test. United States: N. p., 2017. Web. doi:10.1016/j.nucengdes.2017.09.017.
Hunn, John D., Baldwin, Charles A., Montgomery, Fred C., Gerczak, Tyler J., Morris, Robert Noel, Helmreich, Grant W., Demkowicz, Paul, Harp, Jason, & Stempien, John. Initial examination of fuel compacts and TRISO particles from the US AGR-2 irradiation test. United States. doi:10.1016/j.nucengdes.2017.09.017.
Hunn, John D., Baldwin, Charles A., Montgomery, Fred C., Gerczak, Tyler J., Morris, Robert Noel, Helmreich, Grant W., Demkowicz, Paul, Harp, Jason, and Stempien, John. Sat . "Initial examination of fuel compacts and TRISO particles from the US AGR-2 irradiation test". United States. doi:10.1016/j.nucengdes.2017.09.017.
@article{osti_1435300,
title = {Initial examination of fuel compacts and TRISO particles from the US AGR-2 irradiation test},
author = {Hunn, John D. and Baldwin, Charles A. and Montgomery, Fred C. and Gerczak, Tyler J. and Morris, Robert Noel and Helmreich, Grant W. and Demkowicz, Paul and Harp, Jason and Stempien, John},
abstractNote = {Post-irradiation examination was completed on two as-irradiated compacts from the US Advanced Gas Reactor Fuel Development and Qualification Program’s second irradiation test. These compacts were selected for examination because there were indications that they may have contained particles that released cesium through a failed or defective SiC layer. The coated particles were recovered from these compacts by electrolytic deconsolidation of the surrounding graphitic matrix in nitric acid. The leach-burn-leach (LBL) process was used to dissolve and analyze exposed metallic elements (actinides and fission products), and each particle was individually surveyed for relative cesium retention with the Irradiated Microsphere Gamma Analyzer (IMGA). Data from IMGA and LBL examinations provided information on fission product release during irradiation and whether any specific particles had below-average retention that could be related to coating layer defects or radiation-induced degradation. A few selected normal-retention particles and six with abnormally-low cesium inventory were analyzed using X-ray tomography to produce three-dimensional images of the internal coating structure. Four of the low-cesium particles had obviously damaged or degraded SiC, and X-ray imaging was able to guide subsequent grinding and polishing to expose the regions of interest for analysis by optical and electron microscopy. Additional particles from each compact were also sectioned and examined to study the overall radiation-induced microstructural changes in the kernel and coating layers.},
doi = {10.1016/j.nucengdes.2017.09.017},
journal = {Nuclear Engineering and Design},
number = C,
volume = 329,
place = {United States},
year = {Sat Oct 21 00:00:00 EDT 2017},
month = {Sat Oct 21 00:00:00 EDT 2017}
}

Journal Article:
Free Publicly Available Full Text
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