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 | 102 | 2007 |
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 | 70 | 2013 |
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 | 67 | 2015 |
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 | 64 | 2014 |
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 | 62 | 2014 |
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 | 61 | 2015 |
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 | 61 | 2015 |
High temperature aging and corrosion study on alloy 617 and alloy 230 K Mo, G Lovicu, HM Tung, X Chen, JF Stubbins | 61 | 2011 |
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 | 58 | 2013 |
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 | 57 | 2015 |
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 | 50 | 2015 |
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 | 44 | 2017 |
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 | 41 | 2017 |
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 | 39 | 2015 |
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 | 37 | 2016 |
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 | 37 | 2013 |
Grain growth and pore coarsening in dense nanocrystalline UO2+x fuel pellets T Yao, K Mo, D Yun, S Nanda, AM Yacout, J Lian Journal of the American Ceramic Society 100 (6), 2651-2658, 2017 | 33 | 2017 |
Nano-crystallization induced by high-energy heavy ion irradiation in UO2 Y Miao, T Yao, J Lian, S Zhu, S Bhattacharya, A Oaks, AM Yacout, K Mo Scripta Materialia 155, 169-174, 2018 | 32 | 2018 |
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 | 32 | 2014 |
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 | 32 | 2010 |