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Jing Hu
Jing Hu
Dirección de correo verificada de anl.gov
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Identifying suboxide grains at the metal–oxide interface of a corroded Zr–1.0% Nb alloy using (S) TEM, transmission-EBSD and EELS
J Hu, A Garner, N Ni, A Gholinia, RJ Nicholls, S Lozano-Perez, P Frankel, ...
Micron 69, 35-42, 2015
892015
The effect of Sn concentration on oxide texture and microstructure formation in zirconium alloys
A Garner, J Hu, A Harte, P Frankel, C Grovenor, S Lozano-Perez, ...
Acta Materialia 99, 259-272, 2015
762015
In situ microstructural evolution in face-centered and body-centered cubic complex concentrated solid-solution alloys under heavy ion irradiation
C Parkin, M Moorehead, M Elbakhshwan, J Hu, WY Chen, M Li, L He, ...
Acta Materialia 198, 85-99, 2020
462020
Hydrogen pickup during oxidation in aqueous environments: The role of nano-pores and nano-pipes in zirconium oxide films
J Hu, J Liu, S Lozano-Perez, CRM Grovenor, M Christensen, W Wolf, ...
Acta Materialia 180, 105-115, 2019
462019
Comprehensive investigation of the role of Nb on the oxidation kinetics of Zr-Nb alloys
M Moorehead, Z Yu, L Borrel, J Hu, Z Cai, A Couet
Corrosion Science 155, 173-181, 2019
462019
Evolution of cellular dislocation structures and defects in additively manufactured austenitic stainless steel under ion irradiation
S Li, J Hu, WY Chen, J Yu, M Li, Y Wang
Scripta Materialia 178, 245-250, 2020
412020
Mechanism of the α-Zr to hexagonal-ZrO transformation and its impact on the corrosion performance of nuclear Zr alloys
J Liu, H Yu, P Karamched, J Hu, G He, D Goran, GM Hughes, ...
Acta Materialia 179, 328-341, 2019
402019
In situ TEM investigation of irradiation-induced defect formation in cold spray Cr coatings for accident tolerant fuel applications
BR Maier, H Yeom, G Johnson, T Dabney, J Hu, P Baldo, M Li, ...
Journal of Nuclear Materials 512, 320-323, 2018
382018
Effect of neutron and ion irradiation on the metal matrix and oxide corrosion layer on Zr-1.0 Nb cladding alloys
J Hu, A Garner, P Frankel, M Li, MA Kirk, S Lozano-Perez, M Preuss, ...
Acta Materialia 173, 313-326, 2019
372019
Investigating the stability of second phase particles in Zr-Nb alloys under irradiation
G He, J Liu, K Li, J Hu, AH Mir, S Lozano-Perez, C Grovenor
Journal of Nuclear Materials 526, 151738, 2019
362019
Understanding Corrosion and Hydrogen Pickup of Zirconium Fuel Cladding Alloys: The Role of Oxide Microstructure
J Hu, B Setiadinata, T Aarholt, A Garner, A Vilalta-Clemente, J Partezana, ...
Porosity, Suboxides, and Second-Phase Particles, Zirconium in the Nuclear …, 2018
302018
A multi-technique study of “barrier layer” nano-porosity in Zr oxides during corrosion and hydrogen pickup using (S) TEM, TKD, APT and NanoSIMS
J Hu, T Aarholt, B Setiadinata, K Li, A Garner, S Lozano-Perez, M Moody, ...
Corrosion Science 158, 108109, 2019
242019
An integrated modeling and experimental approach to study hydrogen pickup mechanism in zirconium alloys
A Couet, L Borrel, J Liu, J Hu, C Grovenor
Corrosion Science 159, 108134, 2019
212019
High-resolution charaterization of corrosion and hydrogen pickup of Zr cladding alloys
J Hu, B Setiadinata, T Aarholt, P Bagot, M Moody, S Lozano-Perez, ...
TopFuel, 2015
192015
Irradiation-induced amorphization in the zirconium suboxide on Zr-0.5 Nb alloys
J Liu, G He, J Hu, Z Shen, M Kirk, M Li, E Ryan, P Baldo, S Lozano-Perez, ...
Journal of Nuclear Materials 513, 226-231, 2019
152019
Fundamental understanding of Nb effect on corrosion mechanisms of irradiated Zr-Nb alloys
Z Yu, A Couet, M Moorehead, L Borrel, J Hu, M Bachhav
19th International Symposium on Zirconium in the Nuclear Industry, 669-695, 2021
52021
Progressing zirconium-alloy corrosion models using synchrotron XANES
M Moorehead, A Couet, J Hu, Z Cai
Proceedings of the 18th International Conference on Environmental …, 2019
52019
Radiation tolerance of multilayer (TiN, TiAlN) ceramic ATF coatings
J Hu, D Wolfe, A Motta, J Wang, M Li, M Kirk
Transactions of the American Nuclear Society 117, 507-508, 2017
12017
The importance of international collaboration and parallel licensing for advanced nuclear reactors
S Clement, J Hu, J Kendrick, K Yates
Journal of Science Policy & Governance, 2017
2017
Understanding corrosion and hydrogen pickup of zirconium fuel cladding alloys: The role of oxide microstructure, porosity, sub-oxides, and second-phase particles-2016-0071
J Hu, B Setiadinata, T Aarholt, A Garner, A Vilalta-Clemente, ...
ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken …, 2016
2016
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