Initial examination of fuel compacts and triso particles from the US AGR-2 irradiation test

John D. Hunn, Charles A. Baldwin, Fred C. Montgomery, Tyler J. Gerczak, Robert N. Morris, Grant W. Helmreich, Paul A. Demkowicz, Jason M. Harp, John D. Stempien

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

5 Scopus citations

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 due to indications that they may have contained particles that released cesium due to 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.

Original languageEnglish
Title of host publicationInternational Topical Meeting on High Temperature Reactor Technology, HTR 2016
PublisherAmerican Nuclear Society
Pages400-410
Number of pages11
ISBN (Electronic)9780894487323
StatePublished - 2016
Event8th International Topical Meeting on High Temperature Reactor Technology, HTR 2016 - Las Vegas, United States
Duration: Nov 6 2016Nov 10 2016

Publication series

NameInternational Topical Meeting on High Temperature Reactor Technology, HTR 2016

Conference

Conference8th International Topical Meeting on High Temperature Reactor Technology, HTR 2016
Country/TerritoryUnited States
CityLas Vegas
Period11/6/1611/10/16

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