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Lizhen Tan
标题
引用次数
引用次数
年份
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
5202007
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
2432003
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
2352008
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
2272017
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
2212013
Effect of thermomechanical treatment on the corrosion of AA5083
L Tan, TR Allen
Corrosion Science 52 (2), 548-554, 2010
2012010
Surface characterization of NiTi modified by plasma source ion implantation
L Tan, WC Crone
Acta Materialia 50 (18), 4449-4460, 2002
1882002
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
1872021
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
1822008
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
1762010
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
1572016
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
1562008
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
1562006
Oxidation behavior of iron-based alloy HCM12A exposed in supercritical water
L Tan, Y Yang, TR Allen
Corrosion Science 48 (10), 3123-3138, 2006
1552006
Corrosion behavior of alloy 800H (Fe–21Cr–32Ni) in supercritical water
L Tan, TR Allen, Y Yang
Corrosion Science 53 (2), 703-711, 2011
1472011
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
1472008
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
1462011
Formulating the strength factor α for improved predictability of radiation hardening
L Tan, JT Busby
Journal of Nuclear Materials 465, 724-730, 2015
1292015
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
1212013
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
1082016
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