First elevated-temperature performance testing of coated particle fuel compacts from the AGR-1 irradiation experiment

Baldwin, Charles A.; Hunn, John D.; Morris, Robert; Montgomery, Fred C.; Silva, Chinthaka M.; Demkowicz, Paul A.

doi:10.1016/j.nucengdes.2013.11.021

Cited by 58 publications

(40 citation statements)

References 1 publication

Supporting

Mentioning

Contrasting

Order By: Relevance

“…In most cases, the particles were washed and dried for examination using the computerautomated ORNL Irradiated Microsphere Gamma Analyzer (IMGA). Detailed descriptions of the ORNL equipment and procedures relevant to IMGA and deconsolidation-leach-burn-leach (DLBL) are reported elsewhere [Baldwin et al, 2014]. The IMGA was used to survey the cesium inventory in every recovered particle.…”

Section: Isolating Suspect Particles With Low Cesium Inventoriesmentioning

confidence: 99%

See 1 more Smart Citation

Detection and analysis of particles with failed SiC in AGR-1 fuel compacts

Hunn¹,

Baldwin²,

Gerczak³

et al. 2016

Nuclear Engineering and Design

Self Cite

View full text Add to dashboard Cite

Section: Isolating Suspect Particles With Low Cesium Inventoriesmentioning

confidence: 99%

“…Detailed descriptions of the coated particle x-ray tomography equipment and method can be found in [Baldwin et al, 2014]. Fig.…”

Section: Imaging Sic Failures With X-ray Tomographymentioning

confidence: 99%

Detection and analysis of particles with failed SiC in AGR-1 fuel compacts

Hunn¹,

Baldwin²,

Gerczak³

et al. 2016

Nuclear Engineering and Design

Self Cite

View full text Add to dashboard Cite

“…For the temperatures of interest to TRISO operations and accident conditions, 800-1600°C [31], elemental Ag is primarily in the liquid phase with a high vapor pressure. This is an issue for traditional diffusion couple designs as it leads to possible Ag dissolution in Ag (l) [32] and difficulty in maintaining a consistent diffusion surface.…”

Section: Introductionmentioning

confidence: 99%

Observations of Ag diffusion in ion implanted SiC

Gerczak

Leng

Sridharan

et al. 2015

Journal of Nuclear Materials

View full text Add to dashboard Cite

The nature and magnitude of Ag diffusion in SiC has been a topic of interest in connection with the performance of tristructural isotropic (TRISO) coated particle fuel for high temperature nuclear reactors. Ion implantation diffusion couples have been revisited to continue developing a more complete understanding of Ag fission product diffusion in SiC. Ion implantation diffusion couples fabricated from single crystal 4H-SiC and polycrystalline 3C-SiC substrates and exposed to 1500-1625°C, were investigated by transmission electron microscopy and secondary ion mass spectrometry (SIMS). The high dynamic range of SIMS allowed for multiple diffusion régimes to be investigated, including enhanced diffusion by implantation-induced defects and grain boundary (GB) diffusion in undamaged SiC. Estimated diffusion coefficients suggest GB diffusion in bulk SiC does not accurately reflect the release observed from TRISO fuel.

show abstract

“…After graphite‐matrix fuel compacts are irradiated, the TRISO‐coated particles can be separated from the matrix by electrolytically assisted oxidation with nitric acid. Following this compact deconsolidation, particles are often surveyed by gamma analysis to identify rare particles with poor fission product retention (Baldwin et al ., ). Postirradiation tomographic imaging of these isolated particles can then be done to study the defects responsible for fission product release (Baldwin et al ., ).…”

Section: Resultsmentioning

confidence: 99%

Application of X‐ray microcomputed tomography in the characterization of irradiated nuclear fuel and material specimens

Silva

Snead

Hunn

et al. 2015

Journal of Microscopy

View full text Add to dashboard Cite

X-ray microcomputed tomography (μCT) was applied in characterizing the internal structures of a number of irradiated materials, including carbon-carbon fibre composites, nuclear-grade graphite and tristructural isotropic-coated fuel particles. Local cracks in carbon-carbon fibre composites associated with their synthesis process were observed with μCT without any destructive sample preparation. Pore analysis of graphite samples was performed quantitatively, and qualitative analysis of pore distribution was accomplished. It was also shown that high-resolution μCT can be used to probe internal layer defects of tristructural isotropic-coated fuel particles to elucidate the resulting high release of radioisotopes. Layer defects of sizes ranging from 1 to 5 μm and up could be isolated by tomography. As an added advantage, μCT could also be used to identify regions with high densities of radioisotopes to determine the proper plane and orientation of particle mounting for further analytical characterization, such as materialographic sectioning followed by optical and electron microscopy. In fully ceramic matrix fuel forms, despite the highly absorbing matrix, characterization of tristructural isotropic-coated particles embedded in a silicon carbide matrix was accomplished using μCT and related advanced image analysis techniques.

show abstract

First elevated-temperature performance testing of coated particle fuel compacts from the AGR-1 irradiation experiment

Cited by 58 publications

References 1 publication

Detection and analysis of particles with failed SiC in AGR-1 fuel compacts

Detection and analysis of particles with failed SiC in AGR-1 fuel compacts

Observations of Ag diffusion in ion implanted SiC

Application of X‐ray microcomputed tomography in the characterization of irradiated nuclear fuel and material specimens

Contact Info

Product

Resources

About