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Tyler Gerczak
Tyler Gerczak
Dirección de correo verificada de ornl.gov
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Ag diffusion in cubic silicon carbide
D Shrader, SM Khalil, T Gerczak, TR Allen, AJ Heim, I Szlufarska, ...
Journal of Nuclear Materials 408 (3), 257-271, 2011
1282011
Detection and analysis of particles with failed SiC in AGR-1 fuel compacts
JD Hunn, CA Baldwin, TJ Gerczak, FC Montgomery, RN Morris, CM Silva, ...
Nuclear Engineering and Design 306, 36-46, 2016
1202016
Hydrothermal corrosion of SiC in LWR coolant environments in the absence of irradiation
KA Terrani, Y Yang, YJ Kim, R Rebak, HM Meyer III, TJ Gerczak
Journal of Nuclear Materials 465, 488-498, 2015
1162015
AGR-1 post irradiation examination final report
PA Demkowicz
Idaho National Lab.(INL), Idaho Falls, ID (United States), 2015
962015
Restructuring in high burnup UO2 studied using modern electron microscopy
TJ Gerczak, CM Parish, PD Edmondson, CA Baldwin, KA Terrani
Journal of Nuclear Materials 509, 245-259, 2018
942018
Irradiation performance of AGR-1 high temperature reactor fuel
PA Demkowicz, JD Hunn, SA Ploger, RN Morris, CA Baldwin, JM Harp, ...
Nuclear Engineering and Design 306, 2-13, 2016
812016
Initial examination of fuel compacts and TRISO particles from the US AGR-2 irradiation test
JD Hunn, CA Baldwin, FC Montgomery, TJ Gerczak, RN Morris, ...
Nuclear Engineering and Design 329, 89-101, 2018
662018
SiC layer microstructure in AGR-1 and AGR-2 TRISO fuel particles and the influence of its variation on the effective diffusion of key fission products
TJ Gerczak, JD Hunn, RA Lowden, TR Allen
Journal of Nuclear Materials 480, 257-270, 2016
652016
Initial results from safety testing of US AGR-2 irradiation test fuel
RN Morris, JD Hunn, CA Baldwin, FC Montgomery, TJ Gerczak, ...
Nuclear Engineering and Design 329, 124-133, 2018
572018
AGR-2 TRISO fuel post-irradiation examination final report
JD Stempien, RN Morris, TJ Gerczak, PA Demkowicz
Idaho National Lab.(INL), Idaho Falls, ID (United States), 2021
482021
Observations of Ag diffusion in ion implanted SiC
TJ Gerczak, B Leng, K Sridharan, JL Hunter Jr, AJ Giordani, TR Allen
Journal of Nuclear Materials 461, 314-324, 2015
322015
AGR-1 irradiated compact 4-4-2 PIE report: evaluation of as-irradiated fuel performance with leach burn leach, IMGA, materialography, and x-ray tomography
J Hunn, R Morris, C Baldwin, F Montgomery, C Silva, T Gerczak
322013
Effect of carbon ion irradiation on Ag diffusion in SiC
B Leng, H Ko, TJ Gerczak, J Deng, AJ Giordani, JL Hunter Jr, D Morgan, ...
Journal of Nuclear Materials 471, 220-232, 2016
252016
PIE on safety-tested AGR-1 Compact 4-2-2
JD Hunn, RN Morris, CA Baldwin, FC Montgomery, TJ Gerczak
Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2015
252015
Post-irradiation examination and safety testing of US AGR-2 irradiation test compacts
JD Hunn, R Morris, F Montgomery, T Gerczak, D Skitt, C Baldwin, J Dyer, ...
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2018
242018
Electron microscopy study of Pd, Ag, and Cs in carbon areas in the locally corroded SiC layer in a neutron-irradiated TRISO fuel particle
H Wen, IJ van Rooyen, JD Hunn, TJ Gerczak
Journal of the European Ceramic Society 38 (12), 4173-4188, 2018
242018
Characterization of PyC/SiC interfaces with FIB-SEM tomography
JD Arregui-Mena, RL Seibert, TJ Gerczak
Journal of Nuclear Materials 545, 152736, 2021
232021
Analysis of fission product distribution and composition in the TRISO layers of AGR-2 fuel
TJ Gerczak, JD Hunn, RN Morris, FC Montgomery, DJ Skitt, CA Baldwin, ...
Nuclear Engineering and Design 364, 110656, 2020
222020
Characterization of the radial microstructural evolution in LWR UO2 using electron backscatter diffraction
C McKinney, R Seibert, J Werden, C Parish, T Gerczak, J Harp, N Capps
Journal of Nuclear Materials 585, 154605, 2023
172023
Role of microstructure on CO corrosion of SiC layer in UO2-TRISO fuel
TJ Gerczak, R Seibert, JD Hunn
Journal of Nuclear Materials 537, 152185, 2020
152020
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