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Kun Mo, Ph.D. - Publications

Affiliations: 
2011 University of Illinois, Urbana-Champaign, Urbana-Champaign, IL 
Area:
Nuclear Engineering
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56 high-probability publications. We are testing a new system for linking publications to authors. You can help! If you notice any inaccuracies, please sign in and mark papers as correct or incorrect matches. If you identify any major omissions or other inaccuracies in the publication list, please let us know.

Year Citation  Score
2020 Miao Y, Mo K, Bhattacharya S, Jamison L, Oaks A, Kim YS, Yacout AM. Microstructure Evolution in U-10Zr Alloy Irradiated by Swift Xe Ions at 700∘C Journal of Nuclear Materials. 152470. DOI: 10.1016/J.Jnucmat.2020.152470  0.361
2020 Miao Y, Nimmagadda LA, Rajagopal MC, Mo K, Shi J, Ye B, Jamison L, Kim YS, Petry W, Sinha S, Yacout AM. Thermal conductivity measurement of the interaction layer between UMo and Al produced by high-energy heavy ion irradiation Journal of Nuclear Materials. 539: 152262. DOI: 10.1016/J.Jnucmat.2020.152262  0.64
2020 Kim S, Kim YS, Jeong Y, Mo K, Miao Y, Ye B, Oaks A, Bhattacharya S, Lee K, Kim K, Park J, Yacout A. Effectiveness of the metal coating on U–7Mo dispersion fuel in Al during irradiation Journal of Nuclear Materials. 529: 151945. DOI: 10.1016/J.Jnucmat.2019.151945  0.657
2020 Mo K, Miao Y, Xu R, Yao T, Lian J, Jamison LM, Yacout AM. Lattice strain mapping of cracks and indentations in UO2 using synchrotron microdiffraction Journal of Nuclear Materials. 529: 151943. DOI: 10.1016/J.Jnucmat.2019.151943  0.347
2020 Bhattacharya S, Mo K, Mei Z, Seidman D, Stepnik B, Pellin MJ, Yacout AM. Improving stability of ALD ZrN thin film coatings over U-Mo dispersion fuel Applied Surface Science. 533: 147378. DOI: 10.1016/J.Apsusc.2020.147378  0.302
2019 Miao Y, Rajagopal MC, Valavala K, Mo K, Mei Z, Bhattacharya S, Jamison L, Sinha S, Yacout AM. An exploration of measuring lower-length-scale structures in nuclear materials: Thermal conductivity of U-Mo fuel particle Journal of Nuclear Materials. 527: 151797. DOI: 10.1016/J.Jnucmat.2019.151797  0.359
2019 Zhang G, Zhou Z, Mo K, Miao Y, Xu S, Jia H, Liu X, Stubbins JF. The effect of thermal-aging on the microstructure and mechanical properties of 9Cr ferritic/martensitic ODS alloy Journal of Nuclear Materials. 522: 212-219. DOI: 10.1016/J.Jnucmat.2019.05.023  0.625
2019 Miao Y, Harp J, Mo K, Mei Z, Xu R, Zhu S, Yacout AM. Phase decomposition and bubble evolution in Xe implanted U3Si2 at 450∘C Journal of Nuclear Materials. 518: 108-116. DOI: 10.1016/J.Jnucmat.2019.02.004  0.409
2019 Bhattacharya S, Liu X, Miao Y, Mo K, Mei Z, Jamison L, Mohamed W, Oaks A, Xu R, Zhu S, Stubbins JF, Yacout AM. Interaction between Al and atomic layer deposited (ALD) ZrN under high-energy heavy ion irradiation Acta Materialia. 164: 788-798. DOI: 10.1016/J.Actamat.2018.10.031  0.642
2018 Miao Y, Yao T, Lian J, Zhu S, Bhattacharya S, Oaks A, Yacout AM, Mo K. Nano-crystallization induced by high-energy heavy ion irradiation in UO2 Scripta Materialia. 155: 169-174. DOI: 10.1016/J.Scriptamat.2018.04.006  0.44
2018 Miao Y, Harp J, Mo K, Kim YS, Zhu S, Yacout AM. Microstructure investigations of U3Si2 implanted by high-energy Xe ions at 600 °C Journal of Nuclear Materials. 503: 314-322. DOI: 10.1016/J.Jnucmat.2018.02.031  0.397
2017 Yao T, Mo K, Yun D, Nanda S, Yacout AM, Lian J. Grain growth and pore coarsening in dense nano‐crystalline UO2+xfuel pellets Journal of the American Ceramic Society. 100: 2651-2658. DOI: 10.1111/Jace.14780  0.663
2017 Miao Y, Yao T, Lian J, Park J, Almer J, Bhattacharya S, Yacout AM, Mo K. In situ synchrotron investigation of grain growth behavior of nano-grained UO 2 Scripta Materialia. 131: 29-32. DOI: 10.1016/J.Scriptamat.2016.12.025  0.372
2017 Gan Y, Mo K, Yun D, Hoelzer DT, Miao Y, Liu X, Lan K, Park J, Almer J, Chen T, Zhao H. Temperature effect of elastic anisotropy and internal strain development in advanced nanostructured alloys: An in-situ synchrotron X-ray investigation Materials Science and Engineering: A. 692: 53-61. DOI: 10.1016/J.Msea.2017.03.068  0.724
2017 Miao Y, Harp J, Mo K, Zhu S, Yao T, Lian J, Yacout AM. Bubble morphology in U3Si2 implanted by high-energy Xe ions at 300 °C Journal of Nuclear Materials. 495: 146-153. DOI: 10.1016/J.Jnucmat.2017.07.066  0.399
2017 Zang H, Yun D, Mo K, Wang K, Mohamed W, Kirk MA, Velázquez D, Seibert R, Logan K, Terry J, Baldo P, Yacout AM, Liu W, Zhang B, Gao Y, et al. TEM and XAS investigation of fission gas behaviors in U-Mo alloy fuels through ion beam irradiation Journal of Nuclear Materials. 494: 165-171. DOI: 10.1016/J.Jnucmat.2017.07.033  0.703
2017 Mo K, Miao Y, Kontogeorgakos DC, Connaway HM, Wright AE, Yacout AM. Effect of reactor radiation on the thermal conductivity of TREAT fuel Journal of Nuclear Materials. 487: 453-460. DOI: 10.1016/J.Jnucmat.2017.02.003  0.338
2017 Miao Y, Harp J, Mo K, Bhattacharya S, Baldo P, Yacout AM. Short Communication on “In-situ TEM ion irradiation investigations on U3Si2 at LWR temperatures” Journal of Nuclear Materials. 484: 168-173. DOI: 10.1016/J.Jnucmat.2016.11.020  0.412
2016 Mo K, Yun D, Miao Y, Liu X, Pellin M, Almer J, Park JS, Stubbins JF, Zhu S, Yacout AM. Investigation of High-Energy Ion-Irradiated MA957 Using Synchrotron Radiation under In-Situ Tension. Materials (Basel, Switzerland). 9. PMID 28787819 DOI: 10.3390/Ma9010015  0.767
2016 Mo K, Yun D, Miao Y, Liu X, Pellin M, Almer J, Park JS, Stubbins JF, Zhu S, Yacout AM. Investigation of high-energy ion-irradiated MA957 using synchrotron radiation under in-situ tension Materials. 9. DOI: 10.3390/ma9010015  0.717
2016 Mo K, Lv W, Tung HM, Yun D, Miao Y, Lan KC, Stubbins JF. Biaxial Thermal Creep of Alloy 617 and Alloy 230 for VHTR Applications Journal of Engineering Materials and Technology, Transactions of the Asme. 138. DOI: 10.1115/1.4033322  0.764
2016 Miao Y, Mo K, Ye B, Jamison L, Mei ZG, Gan J, Miller B, Madden J, Park JS, Almer J, Bhattacharya S, Kim YS, Hofman GL, Yacout AM. High-energy synchrotron study of in-pile-irradiated U-Mo fuels Scripta Materialia. 114: 146-150. DOI: 10.1016/J.Scriptamat.2015.12.019  0.676
2016 Liu X, Mo K, Miao Y, Lan KC, Zhang G, Chen WY, Tomchik C, Seibert R, Terry J, Stubbins JF. Investigation of thermal aging effects on the tensile properties of Alloy 617 by in-situ synchrotron wide-angle X-ray scattering Materials Science and Engineering A. 651: 55-62. DOI: 10.1016/J.Msea.2015.10.098  0.639
2016 Miao Y, Mo K, Zhou Z, Liu X, Lan KC, Zhang G, Park JS, Almer J, Stubbins JF. Load-partitioning in an oxide dispersion-strengthened 310 steel at elevated temperatures Materials and Design. 111: 622-630. DOI: 10.1016/J.Matdes.2016.09.015  0.657
2016 Zhang G, Zhou Z, Mo K, Miao Y, Li S, Liu X, Wang M, Park JS, Almer J, Stubbins JF. The comparison of microstructures and mechanical properties between 14Cr-Al and 14Cr-Ti ferritic ODS alloys Materials and Design. 98: 61-67. DOI: 10.1016/J.Matdes.2016.02.117  0.646
2016 Miao Y, Mo K, Zhou Z, Liu X, Lan KC, Zhang G, Miller MK, Powers KA, Stubbins JF. Size-dependent characteristics of ultra-fine oxygen-enriched nanoparticles in austenitic steels Journal of Nuclear Materials. 480: 195-201. DOI: 10.1016/J.Jnucmat.2016.08.014  0.575
2016 Pellin MJ, Yacout AM, Mo K, Almer J, Bhattacharya S, Mohamed W, Seidman D, Ye B, Yun D, Xu R, Zhu S. MeV per nucleon ion irradiation of nuclear materials with high energy synchrotron X-ray characterization Journal of Nuclear Materials. 471: 266-271. DOI: 10.1016/J.Jnucmat.2016.01.004  0.773
2016 Lin JL, Mo K, Yun D, Miao Y, Liu X, Zhao H, Hoelzer DT, Park JS, Almer J, Zhang G, Zhou Z, Stubbins JF, Yacout AM. In situ synchrotron tensile investigations on 14YWT, MA957, and 9-Cr ODS alloys Journal of Nuclear Materials. 471: 289-298. DOI: 10.1016/J.Jnucmat.2015.10.049  0.783
2015 Mo K, Tung HM, Chen X, Yun D, Miao Y, Chen W, Aimer J, Novak A, Stubbins JF. In-situ synchrotron X-ray study of the elevated temperature deformation response of SS 316L pressurized creep tubes Astm Special Technical Publication. 244-255. DOI: 10.1520/STP157620140014  0.743
2015 Mo K, Yun D, Yacout AM, Wright AE. Heat transfer simulations of the UO2 particle-graphite system in TREAT fuel Nuclear Engineering and Design. 293: 313-322. DOI: 10.1016/J.Nucengdes.2015.08.009  0.642
2015 Miao Y, Mo K, Zhou Z, Liu X, Lan KC, Zhang G, Miller MK, Powers KA, Mei ZG, Park JS, Almer J, Stubbins JF. On the microstructure and strengthening mechanism in oxide dispersion-strengthened 316 steel: A coordinated electron microscopy, atom probe tomography and in situ synchrotron tensile investigation Materials Science and Engineering A. 639: 585-596. DOI: 10.1016/J.Msea.2015.05.064  0.661
2015 Zhang G, Mo K, Miao Y, Liu X, Almer J, Zhou Z, Stubbins JF. Load partitioning between ferrite/martensite and dispersed nanoparticles of a 9Cr ferritic/martensitic (F/M) ODS steel at high temperatures Materials Science and Engineering a-Structural Materials Properties Microstructure and Processing. 637: 75-81. DOI: 10.1016/J.Msea.2015.04.037  0.646
2015 Miao Y, Mo K, Zhou Z, Liu X, Lan KC, Zhang G, Miller MK, Powers KA, Almer J, Stubbins JF. In situ synchrotron tensile investigations on the phase responses within an oxide dispersion-strengthened (ODS) 304 steel Materials Science and Engineering A. 625: 146-152. DOI: 10.1016/J.Msea.2014.12.017  0.658
2015 Yun D, Mo K, Mohamed W, Ye B, Kirk MA, Baldo P, Xu R, Yacout AM. In situ TEM and synchrotron characterization of U-10Mo thin specimen annealed at the fast reactor temperature regime Materials Characterization. 110: 208-214. DOI: 10.1016/J.Matchar.2015.10.031  0.782
2015 Miao Y, Mo K, Cui B, Chen WY, Miller MK, Powers KA, McCreary V, Gross D, Almer J, Robertson IM, Stubbins JF. The interfacial orientation relationship of oxide nanoparticles in a hafnium-containing oxide dispersion-strengthened austenitic stainless steel Materials Characterization. 101: 136-143. DOI: 10.1016/J.Matchar.2015.01.015  0.604
2015 Yun D, Miao Y, Xu R, Mei Z, Mo K, Mohamed W, Ye B, Pellin MJ, Yacout AM. Characterization of high energy Xe ion irradiation effects in single crystal molybdenum with depth-resolved synchrotron microbeam diffraction Journal of Nuclear Materials. DOI: 10.1016/J.Jnucmat.2015.12.007  0.778
2015 Zhang G, Zhou Z, Mo K, Miao Y, Liu X, Almer J, Stubbins JF. 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 Journal of Nuclear Materials. 467: 50-57. DOI: 10.1016/J.Jnucmat.2015.09.014  0.662
2015 Chen W, Miao Y, Wu Y, Tomchik CA, Mo K, Gan J, Okuniewski MA, Maloy SA, Stubbins JF. Corrigendum to “Atom probe study of irradiation-enhanced α′ precipitation in neutron-irradiated Fe–Cr model alloys” [J. Nucl. Mater. 462 (2015) 242–249] Journal of Nuclear Materials. 467: 392. DOI: 10.1016/J.Jnucmat.2015.08.005  0.745
2015 Ye B, Bhattacharya S, Mo K, Yun D, Mohamed W, Pellin M, Fortner J, Kim YS, Hofman GL, Yacout AM, Wiencek T, Van Den Berghe S, Leenaers A. Irradiation behavior study of U-Mo/Al dispersion fuel with high energy Xe Journal of Nuclear Materials. 464: 236-244. DOI: 10.1016/J.Jnucmat.2015.04.051  0.777
2015 Chen WY, Miao Y, Wu Y, Tomchik CA, Mo K, Gan J, Okuniewski MA, Maloy SA, Stubbins JF. Atom probe study of irradiation-enhanced α precipitation in neutron-irradiated Fe-Cr model alloys Journal of Nuclear Materials. 462: 242-249. DOI: 10.1016/J.Jnucmat.2015.04.005  0.77
2015 Zhang G, Zhou Z, Mo K, Wang P, Miao Y, Li S, Wang M, Liu X, Gong M, Almer J, Stubbins JF. The microstructure and mechanical properties of Al-containing 9Cr ODS ferritic alloy Journal of Alloys and Compounds. 648: 223-228. DOI: 10.1016/J.Jallcom.2015.06.214  0.64
2014 Mohamed W, Yun D, Mo K, Pellin MJ, Billone MC, Almer J, Yacout AM. Depth profile of oxide volume fractions of Zircaloy-2 in high-temperature steam: An in-situ synchrotron radiation study Journal of Nuclear Materials. 454: 192-199. DOI: 10.1016/J.Jnucmat.2014.07.018  0.656
2014 Mo K, Zhou Z, Miao Y, Yun D, Tung H, Zhang G, Chen W, Almer J, Stubbins JF. Synchrotron study on load partitioning between ferrite/martensite and nanoparticles of a 9Cr ODS steel Journal of Nuclear Materials. 455: 376-381. DOI: 10.1016/J.Jnucmat.2014.06.060  0.75
2014 Tung H, Mo K, Stubbins JF. Biaxial thermal creep of Inconel 617 and Haynes 230 at 850 and 950°C Journal of Nuclear Materials. 447: 28-37. DOI: 10.1016/J.Jnucmat.2013.12.016  0.639
2014 Miao Y, Aidhy D, Chen WY, Mo K, Oaks A, Wolf D, Stubbins JF. The evolution mechanism of the dislocation loops in irradiated lanthanum doped cerium oxide Journal of Nuclear Materials. 445: 209-217. DOI: 10.1016/J.Jnucmat.2013.11.015  0.576
2014 Chen X, Yang Z, Sokolov MA, Erdman DL, Mo K, Stubbins JF. Effect of creep and oxidation on reduced fatigue life of Ni-based alloy 617 at 850 °C Journal of Nuclear Materials. 444: 393-403. DOI: 10.1016/J.Jnucmat.2013.09.030  0.624
2014 Miao Y, Chen WY, Oaks A, Mo K, Stubbins JF. The incorporation and migration of a single xenon atom in ceria Journal of Nuclear Materials. 449: 242-247. DOI: 10.1016/J.Jnucmat.2013.06.028  0.546
2013 Mo K, Tung H, Chen X, Zhao Y, Hansen J, Stubbins JF. Strain-Rate Sensitivity Analysis for Ni Alloys to Be Used in Very High Temperature Reactors Nuclear Technology. 183: 455-463. DOI: 10.13182/Nt13-A19433  0.636
2013 Mo K, Tung H, Almer J, Li M, Chen X, Chen W, Hansen JB, Stubbins JF. Synchrotron Radiation Study on Alloy 617 and Alloy 230 for VHTR Application Journal of Pressure Vessel Technology. 135. DOI: 10.1115/1.4007041  0.765
2013 Chen X, Yang Z, Sokolov MA, Erdman DL, Mo K, Stubbins JF. Low cycle fatigue and creep-fatigue behavior of Ni-based alloy 230 at 850°C Materials Science and Engineering a-Structural Materials Properties Microstructure and Processing. 563: 152-162. DOI: 10.1016/J.Msea.2012.11.063  0.629
2013 Mo K, Lovicu G, Tung H, Chen X, Miao Y, Hansen JB, Stubbins JF. Effect of orientation on plastic deformations of Alloy 617 for VHTR applications Journal of Nuclear Materials. 443: 366-377. DOI: 10.1016/J.Jnucmat.2013.07.061  0.655
2013 Mo K, Lovicu G, Chen X, Tung H, Hansen JB, Stubbins JF. Mechanism of plastic deformation of a Ni-based superalloy for VHTR applications Journal of Nuclear Materials. 441: 695-703. DOI: 10.1016/J.Jnucmat.2013.03.083  0.653
2013 Chen X, Sokolov MA, Sham S, Erdman DL, Busby JT, Mo K, Stubbins JF. Experimental and modeling results of creep fatigue life of Inconel 617 and Haynes 230 at 850 C Journal of Nuclear Materials. 432: 94-101. DOI: 10.1016/J.Jnucmat.2012.08.040  0.573
2010 Mo K, Lovicu G, Tung H, Chen X, Stubbins JF. High Temperature Aging and Corrosion Study on Alloy 617 and Alloy 230 Journal of Engineering For Gas Turbines and Power. 133. DOI: 10.1115/1.4002819  0.649
2010 Pan X, Wu X, Mo K, Chen X, Almer J, Ilavsky J, Haeffner DR, Stubbins JF. 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 Journal of Nuclear Materials. 407: 10-15. DOI: 10.1016/J.Jnucmat.2010.07.003  0.776
2010 Pan X, Wu X, Chen X, Mo K, Almer J, Haeffner DR, Stubbins JF. Temperature and particle size effects on flow localization of 9–12%Cr ferritic/martensitic steel by in situ X-ray diffraction and small angle scattering Journal of Nuclear Materials. 398: 220-226. DOI: 10.1016/J.Jnucmat.2009.10.035  0.78
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