U.S. Department of EnergyOffice of Scientific and Technical Information
Radial Deconsolidation and Leach-Burn-Leach of AGR-3/4 Compact 1-4 and 10-4
Abstract
The Advanced Gas Reactor (AGR) Fuel Development and Qualification Program third and fourth irradiation experiments (AGR-3/4), originally planned as separate tests, were combined in one test train for irradiation in the Advanced Test Reactor at Idaho National Laboratory (INL). The irradiation test began on December 14, 2011 and ended on April 12, 2014 (Collin 2016). The originally planned AGR-3 and AGR-4 irradiation experiments were both focused on obtaining data on fission product transport to support the improvement of modeling. The AGR-3 experimental plan was focused on gaseous and metallic fission product release from the kernels and diffusion in the coatings during irradiation and postirradiation safety testing. The AGR-4 experimental plan was focused on diffusivities and sorptivities in the compact matrix and reactor graphite (Petti et al. 2005). These two goals were combined in the AGR-3/4 irradiation, which consisted of twelve independently monitored capsules that each contained four AGR-3/4 compacts in a single stack surrounded by an inner ring of matrix or graphite and an outer ring of graphite. There were two capsule types: a standard capsule and a “fuel body”, in which the outer graphite ring included a floor and cap that fully enclosed the fuel (Stempien et al. 2018a).more »
- Publication Date:
- Research Org.:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org.:
- USDOE Office of Nuclear Energy (NE)
- OSTI Identifier:
- 1709104
- Report Number(s):
- ORNL/TM-2020/1707
TRN: US2204990
- DOE Contract Number:
- AC05-00OR22725
- Resource Type:
- Technical Report
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
Citation Formats
Hunn, John D., Montgomery, Fred C., Skitt, Darren, and Helmreich, Grant. Radial Deconsolidation and Leach-Burn-Leach of AGR-3/4 Compact 1-4 and 10-4. United States: N. p., 2020.
Web. doi:10.2172/1709104.
Hunn, John D., Montgomery, Fred C., Skitt, Darren, & Helmreich, Grant. Radial Deconsolidation and Leach-Burn-Leach of AGR-3/4 Compact 1-4 and 10-4. United States. https://doi.org/10.2172/1709104
Hunn, John D., Montgomery, Fred C., Skitt, Darren, and Helmreich, Grant. 2020.
"Radial Deconsolidation and Leach-Burn-Leach of AGR-3/4 Compact 1-4 and 10-4". United States. https://doi.org/10.2172/1709104. https://www.osti.gov/servlets/purl/1709104.
@article{osti_1709104,
title = {Radial Deconsolidation and Leach-Burn-Leach of AGR-3/4 Compact 1-4 and 10-4},
author = {Hunn, John D. and Montgomery, Fred C. and Skitt, Darren and Helmreich, Grant},
abstractNote = {The Advanced Gas Reactor (AGR) Fuel Development and Qualification Program third and fourth irradiation experiments (AGR-3/4), originally planned as separate tests, were combined in one test train for irradiation in the Advanced Test Reactor at Idaho National Laboratory (INL). The irradiation test began on December 14, 2011 and ended on April 12, 2014 (Collin 2016). The originally planned AGR-3 and AGR-4 irradiation experiments were both focused on obtaining data on fission product transport to support the improvement of modeling. The AGR-3 experimental plan was focused on gaseous and metallic fission product release from the kernels and diffusion in the coatings during irradiation and postirradiation safety testing. The AGR-4 experimental plan was focused on diffusivities and sorptivities in the compact matrix and reactor graphite (Petti et al. 2005). These two goals were combined in the AGR-3/4 irradiation, which consisted of twelve independently monitored capsules that each contained four AGR-3/4 compacts in a single stack surrounded by an inner ring of matrix or graphite and an outer ring of graphite. There were two capsule types: a standard capsule and a “fuel body”, in which the outer graphite ring included a floor and cap that fully enclosed the fuel (Stempien et al. 2018a). The fuel body design supported post-irradiation safety testing of the intact fuel and ring assembly to provide data on fission product transport and release from matrix and graphite at accident temperatures (Demkowicz 2017).},
doi = {10.2172/1709104},
url = {https://www.osti.gov/biblio/1709104},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2020},
month = {9}
}