Lizhen Tan

Citované v

	Všetky	Od 2020
Citácie	6880	3132
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Verejný prístup

všetky položky

73 článkov

3 články

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nedostupné

Na základe mandátov na financovanie

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

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Lizhen Tan

Oak Ridge National Laboratory

Overená e-mailová adresa na: ornl.gov

Reactor Structural Materials Radiation Effects Microstructure Mechanical Properties Corrosion


Názov Zoradiť podľa citácií Zoradiť podľa roka Zoradiť podľa názvu	Citované v Citované v	Rok
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	226	2021
Effect of thermomechanical treatment on the corrosion of AA5083 L Tan, TR Allen Corrosion Science 52 (2), 548-554, 2010	215	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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