U.S. Department of EnergyOffice of Scientific and Technical Information
Advanced Microscopy Report on UCO Fuel Kernels from Selected AGR-1 and AGR-2 Experiments
Abstract
A variety of neutron irradiation experiments were completed at Idaho National Laboratory (INL) on tristructural isotropic (TRISO) coated particles contained in a graphitic matrix as part of the Advanced Gas Reactor (AGR) fuel development and qualification program. Although the initial advanced microscopy and microanalysis studies on AGR-1 particles focused predominantly on the SiC layer?s role as the main fission-product containment, studies were further expanded to evaluate UCO kernels of selected AGR-1 and AGR-2 coated particles. Fuel kernels tested in the AGR-1 and AGR-2 experiments is composed of a mixture of UO2 and UC, with a nominal as-fabricated stoichiometry of UO1.37 C0.35 and UO1.43 C0.39, respectively. These as-fabricated kernel-stoichiometry values are determined at the completion of kernel fabrication and do not account for any changes that will occur during the subsequent coating and compacting processes.
- Publication Date:
- Research Org.:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Sponsoring Org.:
- USDOE Office of Nuclear Energy (NE)
- OSTI Identifier:
- 1778921
- Report Number(s):
- INL/EXT-21-62124-Rev000
- DOE Contract Number:
- DE-AC07-05ID14517
- Resource Type:
- Program Document
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 11 - NUCLEAR FUEL CYCLE AND FUEL MATERIALS; Tristructural Isotropic; Advanced Gas Reactor; Post-irradiation examination
Citation Formats
Van Rooyen, Isabella J, Yang, Yong, Fu, Zhenyu, Kombaiah, Boopathy, and Wright, Karen E. Advanced Microscopy Report on UCO Fuel Kernels from Selected AGR-1 and AGR-2 Experiments. United States: N. p., 2021.
Web.
Van Rooyen, Isabella J, Yang, Yong, Fu, Zhenyu, Kombaiah, Boopathy, & Wright, Karen E. Advanced Microscopy Report on UCO Fuel Kernels from Selected AGR-1 and AGR-2 Experiments. United States.
Van Rooyen, Isabella J, Yang, Yong, Fu, Zhenyu, Kombaiah, Boopathy, and Wright, Karen E. 2021.
"Advanced Microscopy Report on UCO Fuel Kernels from Selected AGR-1 and AGR-2 Experiments". United States. https://www.osti.gov/servlets/purl/1778921.
@article{osti_1778921,
title = {Advanced Microscopy Report on UCO Fuel Kernels from Selected AGR-1 and AGR-2 Experiments},
author = {Van Rooyen, Isabella J and Yang, Yong and Fu, Zhenyu and Kombaiah, Boopathy and Wright, Karen E},
abstractNote = {A variety of neutron irradiation experiments were completed at Idaho National Laboratory (INL) on tristructural isotropic (TRISO) coated particles contained in a graphitic matrix as part of the Advanced Gas Reactor (AGR) fuel development and qualification program. Although the initial advanced microscopy and microanalysis studies on AGR-1 particles focused predominantly on the SiC layer?s role as the main fission-product containment, studies were further expanded to evaluate UCO kernels of selected AGR-1 and AGR-2 coated particles. Fuel kernels tested in the AGR-1 and AGR-2 experiments is composed of a mixture of UO2 and UC, with a nominal as-fabricated stoichiometry of UO1.37 C0.35 and UO1.43 C0.39, respectively. These as-fabricated kernel-stoichiometry values are determined at the completion of kernel fabrication and do not account for any changes that will occur during the subsequent coating and compacting processes.},
doi = {},
url = {https://www.osti.gov/biblio/1778921},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2021},
month = {3}
}