Safety Test on Loose Particles from Irradiated Compact 4-4-2

Post-irradiation examination (PIE) is being carried out on coated particle fuel compacts from the first Advanced Gas Reactor (AGR) Fuel Development and Qualification irradiation experiment (AGR-1). The Oak Ridge National Laboratory (ORNL) Core Conduction Cooldown Test Facility (CCCTF) has been used to evaluate the effect of elevated temperature on the fuel microstructure and fission product retention by heating compacts to maximum temperatures of 1600, 1700, or 1800°C for typically 300 hours, where 1600°C is the expected maximum temperature during a high-temperature gas-cooled reactor (HTGR) depressurization conduction cooldown event, while 1700 and 1800°C explore the performance margin. After completing eleven standard safety tests, a different type of experiment was conducted [INL/PLN4650], where, rather than heating an entire as-irradiated fuel compact, loose particles were tested after deconsolidation of a compact and separation of the particles from the compact matrix.