Electron microscopic evaluation and fission product identification of irradiated TRISO coated particles from the AGR-1 experiment: A preliminary review

I. J. Van Rooyen, D. E. Janney, B. D. Miller, P. A. Demkowicz, Jessica McQuiston

Research output: Contribution to journalArticle

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Abstract

Post-irradiation examination of coated particle fuel from the AGR-1 experiment is in progress at Idaho National Laboratory and Oak Ridge National Laboratory. In this paper a brief summary of results from characterization of microstructures in the coating layers of selected irradiated fuel particles with burnup of 11.3% and 19.3% FIMA will be given. The main objectives of the characterization were to study irradiation effects, fuel kernel porosity, layer debonding, layer degradation or corrosion, fission-product precipitation, grain sizes, and transport of fission products from the kernels across the TRISO layers. Characterization techniques such as scanning electron microscopy, transmission electron microscopy, energy dispersive spectroscopy, and wavelength dispersive spectroscopy were used. A new approach to microscopic quantification of fission-product precipitates is also briefly demonstrated. Microstructural characterization focused on fission-product precipitates in the SiC-IPyC interface, the SiC layer and the fuel-buffer interlayer. The results provide significant new insights into mechanisms of fission-product transport. Although Pd-rich precipitates were identified at the SiC-IPyC interlayer, no significant SiC-layer thinning was observed for the particles investigated. Characterization of these precipitates highlighted the difficulty of measuring low concentrations of Ag in precipitates with significantly higher concentrations of Pd and U. Different approaches to resolving this problem are discussed. An initial hypothesis is provided to explain fission-product precipitate compositions and locations. No SiC phase transformations were observed and no debonding of the SiC-IPyC interlayer as a result of irradiation was observed for the samples investigated. Lessons learned from the post-irradiation examination are described and future actions are recommended.

Original languageEnglish (US)
Pages (from-to)114-122
Number of pages9
JournalNuclear Engineering and Design
Volume271
DOIs
StatePublished - Jan 1 2014
Externally publishedYes

Fingerprint

fission products
Fission products
Precipitates
precipitates
electron
Electrons
evaluation
irradiation
products
Irradiation
interlayers
electrons
experiment
Experiments
Debonding
examination
Coated fuel particles
spectroscopy
Wavelength dispersive spectroscopy
lessons learned

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Materials Science(all)
  • Nuclear Energy and Engineering
  • Safety, Risk, Reliability and Quality
  • Waste Management and Disposal
  • Mechanical Engineering

Cite this

Electron microscopic evaluation and fission product identification of irradiated TRISO coated particles from the AGR-1 experiment : A preliminary review. / Van Rooyen, I. J.; Janney, D. E.; Miller, B. D.; Demkowicz, P. A.; McQuiston, Jessica.

In: Nuclear Engineering and Design, Vol. 271, 01.01.2014, p. 114-122.

Research output: Contribution to journalArticle

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