U.S. Department of EnergyOffice of Scientific and Technical Information
Safety Testing and Destructive Examination of AGR-2 UO2 Compact 3-1-1
Abstract
Post-irradiation examination and elevated-temperature safety testing are being performed on compacts from the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program’s second irradiation experiment (AGR-2). The compacts in the AGR-2 irradiation experiment held either tristructural isotropic (TRISO)-coated particles containing uranium oxide fuel kernels (UO2) or TRISO-coated particles containing fuel kernels with both uranium carbide and uranium oxide phases (UCO). In UO2 TRISO particles, oxygen released by uranium fission can react with the surrounding carbon in the buffer layer to form carbon monoxide (CO). Excess CO can lead to various irradiation performance issues under certain operating conditions, such as pressure-induced fracture, kernel migration, and silicon carbide (SiC) corrosion. In UCO TRISO particles, CO formation is reduced because the chemical potential for oxidation of uranium carbide is lower than for oxidation of carbon.
- Publication Date:
- Research Org.:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org.:
- USDOE Office of Nuclear Energy (NE)
- OSTI Identifier:
- 1606690
- Report Number(s):
- ORNL/TM-2020/1451
TRN: US2103938
- DOE Contract Number:
- AC05-00OR22725
- Resource Type:
- Technical Report
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
Citation Formats
Hunn, John D., Morris, Robert Noel, Montgomery, Fred C., Skitt, Darren J., and Burns, Zachary M.. Safety Testing and Destructive Examination of AGR-2 UO2 Compact 3-1-1. United States: N. p., 2020.
Web. doi:10.2172/1606690.
Hunn, John D., Morris, Robert Noel, Montgomery, Fred C., Skitt, Darren J., & Burns, Zachary M.. Safety Testing and Destructive Examination of AGR-2 UO2 Compact 3-1-1. United States. https://doi.org/10.2172/1606690
Hunn, John D., Morris, Robert Noel, Montgomery, Fred C., Skitt, Darren J., and Burns, Zachary M.. 2020.
"Safety Testing and Destructive Examination of AGR-2 UO2 Compact 3-1-1". United States. https://doi.org/10.2172/1606690. https://www.osti.gov/servlets/purl/1606690.
@article{osti_1606690,
title = {Safety Testing and Destructive Examination of AGR-2 UO2 Compact 3-1-1},
author = {Hunn, John D. and Morris, Robert Noel and Montgomery, Fred C. and Skitt, Darren J. and Burns, Zachary M.},
abstractNote = {Post-irradiation examination and elevated-temperature safety testing are being performed on compacts from the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program’s second irradiation experiment (AGR-2). The compacts in the AGR-2 irradiation experiment held either tristructural isotropic (TRISO)-coated particles containing uranium oxide fuel kernels (UO2) or TRISO-coated particles containing fuel kernels with both uranium carbide and uranium oxide phases (UCO). In UO2 TRISO particles, oxygen released by uranium fission can react with the surrounding carbon in the buffer layer to form carbon monoxide (CO). Excess CO can lead to various irradiation performance issues under certain operating conditions, such as pressure-induced fracture, kernel migration, and silicon carbide (SiC) corrosion. In UCO TRISO particles, CO formation is reduced because the chemical potential for oxidation of uranium carbide is lower than for oxidation of carbon.},
doi = {10.2172/1606690},
url = {https://www.osti.gov/biblio/1606690},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2020},
month = {2}
}