PIE on Safety-Tested AGR-1 Compact 5-1-1

Hunn, John D.¹  Morris, Robert Noel¹  Baldwin, Charles A.¹  Montgomery, Fred C.¹  Gerczak, Tyler J.¹ 

[1] Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

关键词: TRISO;    Coated Particle Fuel;    AGR;    PIE;   

DOI  :  10.2172/1213349
RP-ID  :  ORNL/TM--2015/317
PID  :  OSTI ID: 1213349

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来源: SciTech Connect

【 摘 要 】

Post-irradiation examination (PIE) is being performed in support of tristructural isotropic (TRISO) coated particle fuel development and qualification for High-Temperature Gas-cooled Reactors (HTGRs). AGR-1 was the first in a series of TRISO fuel irradiation experiments initiated in 2006 under the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program; this work continues to be funded by the Department of Energy's Office of Nuclear Energy as part of the Advanced Reactor Technologies (ART) initiative. AGR-1 fuel compacts were fabricated at Oak Ridge National Laboratory (ORNL) in 2006 and irradiated for three years in the Idaho National Laboratory (INL) Advanced Test Reactor (ATR) to demonstrate and evaluate fuel performance under HTGR irradiation conditions. PIE is being performed at INL and ORNL to study how the fuel behaved during irradiation, and to examine fuel performance during exposure to elevated temperatures at or above temperatures that could occur during a depressurized conduction cooldown event. This report summarizes safety testing of irradiated AGR-1 Compact 5-1-1 in the ORNL Core Conduction Cooldown Test Facility (CCCTF) and post-safety testing PIE.