Lizhen Tan

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Todd AllenUniversity of MichiganVerifisert e-postadresse på umich.edu
Yutai KatohMaterials Science and Technology Division, Oak Ridge National LaboratoryVerifisert e-postadresse på ornl.gov
Tianyi ChenAssistant Professor, Oregon State UniversityVerifisert e-postadresse på oregonstate.edu
D.T. HoelzerOak Ridge National LaboratoryVerifisert e-postadresse på ornl.gov
Lance SneadMassachusetts Institute of TechnologyVerifisert e-postadresse på MIT.edu
Steven ZinkleUniversity of TennesseeVerifisert e-postadresse på utk.edu
Wendy C. CroneUniversity of Wisconsin-MadisonVerifisert e-postadresse på engr.wisc.edu
Kevin FieldUniversity of MichiganVerifisert e-postadresse på umich.edu
Yukinori YamamotoOak Ridge National LaboratoryVerifisert e-postadresse på ornl.gov
Chad M. ParishSenior Research and Development Staff, Oak Ridge National LaboratoryVerifisert e-postadresse på ornl.gov
Haixuan XuDepartment of Materials Science and Engineering, University of TennesseeVerifisert e-postadresse på utk.edu
Bruce A. PintConsultant, retired Oak Ridge National LaboratoryVerifisert e-postadresse på ornl.gov
TS Byun, Thak Sang ByunOak Ridge National Laboratory, Korea Atomic Energy Research InstituteVerifisert e-postadresse på ornl.gov
Philip MaziaszOak Ridge National LaboratoryVerifisert e-postadresse på ornl.gov
Ji-Cheng Zhao (J.-C. Zhao) (JC Zhao)Dean of College of Engineering, University of Connecticut (UConn)Verifisert e-postadresse på uconn.edu
FA GarnerL.N.Gumilyov Eurasian National University, Faculty of Physics and TechnicsVerifisert e-postadresse på enu.kz
Hideo SakasegawaJapan Atomic Energy Agency

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Lizhen Tan

Oak Ridge National Laboratory

Verifisert e-postadresse på ornl.gov

Reactor Structural Materials Radiation Effects Microstructure Mechanical Properties Corrosion


Tittel Sorter etter sitater Sorter etter år Sorter etter tittel	Sitert av Sitert av	År
Corrosion and stress corrosion cracking in supercritical water GS Was, P Ampornrat, G Gupta, S Teysseyre, EA West, TR Allen, ... Journal of Nuclear Materials 371 (1-3), 176-201, 2007	547	2007
Development of next generation tempered and ODS reduced activation ferritic/martensitic steels for fusion energy applications SJ Zinkle, JL Boutard, DT Hoelzer, A Kimura, R Lindau, GR Odette, ... Nuclear Fusion 57 (9), 092005, 2017	255	2017
Corrosion and wear-corrosion behavior of NiTi modified by plasma source ion implantation L Tan, RA Dodd, WC Crone Biomaterials 24 (22), 3931-3939, 2003	251	2003
Corrosion behavior of Ni-base alloys for advanced high temperature water-cooled nuclear plants L Tan, X Ren, K Sridharan, TR Allen Corrosion science 50 (11), 3056-3062, 2008	246	2008
Recent progress of R&D activities on reduced activation ferritic/martensitic steels Q Huang, N Baluc, Y Dai, S Jitsukawa, A Kimura, J Konys, RJ Kurtz, ... Journal of Nuclear Materials 442 (1-3), S2-S8, 2013	235	2013
Bifunctional nanoprecipitates strengthen and ductilize a medium-entropy alloy Y Yang, T Chen, L Tan, JD Poplawsky, K An, Y Wang, GD Samolyuk, ... Nature 595 (7866), 245-249, 2021	225	2021
Effect of thermomechanical treatment on the corrosion of AA5083 L Tan, TR Allen Corrosion Science 52 (2), 548-554, 2010	214	2010
Effect of shot-peening on the oxidation of alloy 800H exposed to supercritical water and cyclic oxidation L Tan, X Ren, K Sridharan, TR Allen Corrosion Science 50 (7), 2040-2046, 2008	197	2008
Surface characterization of NiTi modified by plasma source ion implantation L Tan, WC Crone Acta Materialia 50 (18), 4449-4460, 2002	194	2002
Corrosion behavior of 9–12% Cr ferritic–martensitic steels in supercritical water L Tan, X Ren, TR Allen Corrosion science 52 (4), 1520-1528, 2010	184	2010
Development of new generation reduced activation ferritic-martensitic steels for advanced fusion reactors L Tan, LL Snead, Y Katoh Journal of Nuclear Materials 478, 42-49, 2016	175	2016
Materials challenges for generation IV nuclear energy systems TR Allen, K Sridharan, L Tan, WE Windes, JI Cole, DC Crawford, GS Was Nuclear Technology 162 (3), 342-357, 2008	166	2008
Microstructure tailoring for property improvements by grain boundary engineering L Tan, K Sridharan, TR Allen, RK Nanstad, DA McClintock Journal of Nuclear Materials 374 (1-2), 270-280, 2008	166	2008
The effect of grain boundary engineering on the oxidation behavior of INCOLOY alloy 800H in supercritical water L Tan, K Sridharan, TR Allen Journal of nuclear materials 348 (3), 263-271, 2006	163	2006
Corrosion of austenitic and ferritic-martensitic steels exposed to supercritical carbon dioxide L Tan, M Anderson, D Taylor, TR Allen Corrosion Science 53 (10), 3273-3280, 2011	161	2011
Oxidation behavior of iron-based alloy HCM12A exposed in supercritical water L Tan, Y Yang, TR Allen Corrosion Science 48 (10), 3123-3138, 2006	160	2006
Corrosion behavior of alloy 800H (Fe–21Cr–32Ni) in supercritical water L Tan, TR Allen, Y Yang Corrosion Science 53 (2), 703-711, 2011	155	2011
Formulating the strength factor α for improved predictability of radiation hardening L Tan, JT Busby Journal of Nuclear Materials 465, 724-730, 2015	145	2015
Grain boundary engineering for structure materials of nuclear reactors L Tan, TR Allen, JT Busby Journal of nuclear materials 441 (1-3), 661-666, 2013	129	2013
Recent status and improvement of reduced-activation ferritic-martensitic steels for high-temperature service L Tan, Y Katoh, AAF Tavassoli, J Henry, M Rieth, H Sakasegawa, ... Journal of Nuclear Materials 479, 515-523, 2016	122	2016

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