Safety testing of AGR-2 UO2 compacts 3-3-2 and 3-4-2

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

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

关键词: URANIUM DIOXIDE;    NUCLEAR FUELS;    SAFETY;    TESTING;    COATED FUEL PARTICLES;    POST-IRRADIATION EXAMINATION;    DESIGN;    IRRADIATION;    AGR TYPE REACTORS TRISO;    Coated Particle Fuel;    AGR;    PIE;   

DOI  :  10.2172/1222564
RP-ID  :  ORNL/TM--2015/388
PID  :  OSTI ID: 1222564
Others  :  TRN: US1500427

学科分类：核能源与工程

美国|英语

来源: SciTech Connect

【 摘 要 】

Post-irradiation examination (PIE) is in progress on tristructural-isotropic (TRISO) coated-particle fuel compacts from the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program second irradiation experiment (AGR-2) [Collin 2014]. The AGR-2 PIE will build upon new information and understanding acquired throughout the recently-concluded six-year AGR-1 PIE campaign [Demkowicz et al. 2015] and establish a database for the different AGR-2 fuel designs.