|About this Abstract
||2016 TMS Annual Meeting & Exhibition
||Materials and Fuels for the Current and Advanced Nuclear Reactors V
||AA-8: A Study on the Diffusion of Volatile Fission Products in the Graphite Matrix of HTGR
||Je-Kyun Baek, Qusai Mistarihi, Sunghwan Yeo, Young-Woo Lee, Hojin Ryu
|On-Site Speaker (Planned)
An understanding of the diffusion of cesium (Cs) is essential for the operational safety of High Temperature Gas-cooled Reactors (HTGR). Cesium is one the volatile fission products and they can release out to the external environment by penetrating the coating layers and the graphite matrix of fuel pellets. The transport kinetics of Cs in the graphite matrix with varying microstructural parameters depending on the fabrication process was evaluated. The microstructures of the graphite matrix of fuel pellets were characterized as a function of fabrication process parameters. Cs has been absorbed in the graphite matrix by decomposition of CsNO3 and long-term annealing at an elevated temperature. In order to measure the diffusivity of Cs in the graphite matrix, the concentration profiles of Cs/graphite diffusion couples were measured. In addition, the concentration changes after annealing the Cs-absorbed pellets were measured with time to confirm the measured diffusivities by diffusion couple methods.
||Planned: A print-only volume