Advanced Electron Microscopy and Micro Analytical Technique Development and Application for Irradiated TRISO Coated Particles from the AGR-1 Experiment
A series of up to seven irradiation experiments are planned for the Advanced Gas Reactor (AGR) Fuel Development and Quantification Program, with irradiation completed at the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL) for the first experiment (i.e., AGR-1) in November 2009 for an effective 620 full power days. The objective of the AGR-1 experiment was primarily to provide lessons learned on the multi-capsule test train design and to provide early data on fuel performance for use in fuel fabrication process development and post-irradiation safety testing data at high temperatures. This report describes the advanced microscopy and micro-analysis results on selected AGR-1 coated particles.
I. J. Van Rooyen et al., "Advanced Electron Microscopy and Micro Analytical Technique Development and Application for Irradiated TRISO Coated Particles from the AGR-1 Experiment,", pp. 1 - 390 Cambridge University Press, Jan 2017.
The definitive version is available at https://doi.org/10.2172/1364087
Materials Science and Engineering
USDOE Office of Nuclear Energy
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01 Jan 2017