Kun Mo
Title
Cited by
Cited by
Year
A dynamic neural network aggregation model for transient diagnosis in nuclear power plants
K Mo, SJ Lee, PH Seong
Progress in nuclear energy 49 (3), 262-272, 2007
722007
Synchrotron study on load partitioning between ferrite/martensite and nanoparticles of a 9Cr ODS steel
K Mo, Z Zhou, Y Miao, D Yun, HM Tung, G Zhang, W Chen, J Almer, ...
Journal of Nuclear Materials 455 (1-3), 376-381, 2014
502014
On the microstructure and strengthening mechanism in oxide dispersion-strengthened 316 steel: A coordinated electron microscopy, atom probe tomography and in situ synchrotron…
Y Miao, K Mo, Z Zhou, X Liu, KC Lan, G Zhang, MK Miller, KA Powers, ...
Materials Science and Engineering: A 639, 585-596, 2015
482015
High temperature aging and corrosion study on alloy 617 and alloy 230
K Mo, G Lovicu, HM Tung, X Chen, JF Stubbins
Journal of engineering for gas turbines and power 133 (5), 2011
472011
Effect of creep and oxidation on reduced fatigue life of Ni-based alloy 617 at 850 C
X Chen, Z Yang, MA Sokolov, DL Erdman III, K Mo, JF Stubbins
Journal of Nuclear Materials 444 (1-3), 393-403, 2014
432014
The interfacial orientation relationship of oxide nanoparticles in a hafnium-containing oxide dispersion-strengthened austenitic stainless steel
Y Miao, K Mo, B Cui, WY Chen, MK Miller, KA Powers, V McCreary, ...
Materials Characterization 101, 136-143, 2015
422015
In situ synchrotron tensile investigations on the phase responses within an oxide dispersion-strengthened (ODS) 304 steel
Y Miao, K Mo, Z Zhou, X Liu, KC Lan, G Zhang, MK Miller, KA Powers, ...
Materials Science and Engineering: A 625, 146-152, 2015
422015
Atom probe study of irradiation-enhanced α′ precipitation in neutron-irradiated Fe–Cr model alloys
WY Chen, Y Miao, Y Wu, CA Tomchik, K Mo, J Gan, MA Okuniewski, ...
Journal of Nuclear Materials 462, 242-249, 2015
412015
Mechanism of plastic deformation of a Ni-based superalloy for VHTR applications
K Mo, G Lovicu, X Chen, HM Tung, JB Hansen, JF Stubbins
Journal of nuclear materials 441 (1-3), 695-703, 2013
382013
Experimental and modeling results of creep–fatigue life of Inconel 617 and Haynes 230 at 850 C
X Chen, MA Sokolov, S Sham, DL Erdman III, JT Busby, K Mo, ...
Journal of nuclear materials 432 (1-3), 94-101, 2013
382013
Short Communication on “In-situ TEM ion irradiation investigations on U3Si2 at LWR temperatures”
Y Miao, J Harp, K Mo, S Bhattacharya, P Baldo, AM Yacout
Journal of Nuclear Materials 484, 168-173, 2017
332017
The evolution of internal stress and dislocation during tensile deformation in a 9Cr ferritic/martensitic (F/M) ODS steel investigated by high-energy X-rays
G Zhang, Z Zhou, K Mo, Y Miao, X Liu, J Almer, JF Stubbins
Journal of Nuclear Materials 467, 50-57, 2015
322015
The microstructure and mechanical properties of Al-containing 9Cr ODS ferritic alloy
G Zhang, Z Zhou, K Mo, P Wang, Y Miao, S Li, M Wang, X Liu, M Gong, ...
Journal of Alloys and Compounds 648, 223-228, 2015
312015
Lattice strain and damage evolution of 9–12% Cr ferritic/martensitic steel during in situ tensile test by X-ray diffraction and small angle scattering
X Pan, X Wu, K Mo, X Chen, J Almer, J Ilavsky, DR Haeffner, JF Stubbins
Journal of Nuclear Materials 407 (1), 10-15, 2010
302010
Bubble morphology in U3Si2 implanted by high-energy Xe ions at 300 C
Y Miao, J Harp, K Mo, S Zhu, T Yao, J Lian, AM Yacout
Journal of Nuclear Materials 495, 146-153, 2017
292017
The comparison of microstructures and mechanical properties between 14Cr-Al and 14Cr-Ti ferritic ODS alloys
G Zhang, Z Zhou, K Mo, Y Miao, S Li, X Liu, M Wang, JS Park, J Almer, ...
Materials & Design 98, 61-67, 2016
252016
Low cycle fatigue and creep-fatigue behavior of Ni-based alloy 230 at 850 C
X Chen, Z Yang, MA Sokolov, DL Erdman III, K Mo, JF Stubbins
Materials Science and Engineering: A 563, 152-162, 2013
252013
Microstructure investigations of U3Si2 implanted by high-energy Xe ions at 600 C
Y Miao, J Harp, K Mo, YS Kim, S Zhu, AM Yacout
Journal of Nuclear Materials 503, 314-322, 2018
222018
Synchrotron radiation study on Alloy 617 and Alloy 230 for VHTR application
K Mo, HM Tung, J Almer, M Li, X Chen, W Chen, JB Hansen, JF Stubbins
Journal of Pressure Vessel Technology 135 (2), 2013
222013
Biaxial thermal creep of Inconel 617 and Haynes 230 at 850 and 950 C
HM Tung, K Mo, JF Stubbins
Journal of Nuclear Materials 447 (1-3), 28-37, 2014
212014
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Articles 1–20