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Research Output 1975 2020

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2020

A transmission electron microscopy study of EBR-II neutron-irradiated austenitic stainless steel 304 and nickel-base alloy X-750

Liu, X., He, L., Yan, H., Bachhav, M. & Stubbins, J. F., Jan 2020, In : Journal of Nuclear Materials. 528, 151851.

Research output: Contribution to journalArticle

austenitic stainless steels
Austenitic stainless steel
Nickel
Precipitates
precipitates
2019

Dissolution of Intermetallic Second-Phase Particles in Zircaloy-2 in High-Temperature Steam

Zhong, W., Liu, X., Mouche, P. A., Lin, J. L., Park, D., Elbakhshwan, M. S., Gill, S. K., Ren, Y., Stubbins, J. F. & Heuser, B. J., Apr 15 2019, In : Metallurgical and Materials Transactions A: Physical Metallurgy and Materials Science. 50, 4, p. 1851-1861 11 p.

Research output: Contribution to journalArticle

Zircaloy 2 (trademark)
Steam
steam
Intermetallics
intermetallics

Interaction between Al and atomic layer deposited (ALD) ZrN under high-energy heavy ion irradiation

Bhattacharya, S., Liu, X., Miao, Y., Mo, K., Mei, Z. G., Jamison, L., Mohamed, W., Oaks, A., Xu, R., Zhu, S., Stubbins, J. F. & Yacout, A. M., Feb 1 2019, In : Acta Materialia. 164, p. 788-798 11 p.

Research output: Contribution to journalArticle

Heavy Ions
Ion bombardment
Heavy ions
Zirconium
Nitrides

The effect of thermal-aging on the microstructure and mechanical properties of 9Cr ferritic/martensitic ODS alloy

Zhang, G., Zhou, Z., Mo, K., Miao, Y., Xu, S., Jia, H., Liu, X. & Stubbins, J. F., Aug 15 2019, In : Journal of Nuclear Materials. 522, p. 212-219 8 p.

Research output: Contribution to journalArticle

Thermal aging
Aging of materials
mechanical properties
Microhardness
Mechanical properties
2018

A special coarsening mechanism for intergranular helium bubbles upon heating: A combined experimental and numerical study

Gao, J., Huang, H., Liu, X., Wang, C., Stubbins, J. F. & Li, Y., Apr 1 2018, In : Scripta Materialia. 147, p. 93-97 5 p.

Research output: Contribution to journalArticle

Helium
Surface diffusion
Coarsening
Pressure gradient
Coalescence

Biaxial creep performance of CWSR Zircaloy-4 cladding at emulated off-normal conditions of interim dry storage facility

Lan, K. C., Tung, H. M., Miao, Y. & Stubbins, J. F., Oct 24 2018, In : Materials Science and Engineering A. 736, p. 400-403 4 p.

Research output: Contribution to journalArticle

Creep
retraining
hydrides
exponents
microscopy

Radiation resistance of oxide dispersion strengthened alloys: Perspectives from in situ observations and rate theory calculations

Liu, X., Miao, Y., Li, M., Kirk, M. A., Zhang, G., Ukai, S., Maloy, S. A. & Stubbins, J. F., Apr 15 2018, In : Scripta Materialia. 148, p. 33-36 4 p.

Research output: Contribution to journalArticle

radiation tolerance
Oxides
Radiation
oxides
Defects

The challenge of acquiring a satisfactory EBSD result of CWSR Zircaloy-4 cladding tube

Lan, K. C., Zhong, W., Mouche, P. A., Tung, H. M., Lee, H., Heuser, B. J. & Stubbins, J. F., Oct 2018, In : Journal of Microscopy. 272, 1, p. 25-34 10 p.

Research output: Contribution to journalArticle

Electrons
Hydrofluoric Acid
Corrosion
Electrolytes
Research Personnel
2017

In situ high-energy X-ray diffraction study of tensile deformation of neutron-irradiated polycrystalline Fe-9%Cr alloy

Zhang, X., Li, M., Park, J. S., Kenesei, P., Almer, J., Xu, C. & Stubbins, J. F., Mar 1 2017, In : Acta Materialia. 126, p. 67-76 10 p.

Research output: Contribution to journalArticle

Neutrons
Strain hardening
X ray diffraction
Coherent scattering
Neutron irradiation

Ion-irradiation-induced microstructural modifications in ferritic/martensitic steel T91

Liu, X., Miao, Y., Li, M., Kirk, M. K., Maloy, S. A. & Stubbins, J. F., Jul 1 2017, In : Journal of Nuclear Materials. 490, p. 305-316 12 p.

Research output: Contribution to journalArticle

Martensitic steel
Ferritic steel
Ion bombardment
ion irradiation
Irradiation

On the fracture of high temperature alloys by creep cavitation under uniaxial or biaxial stress states

Sanders, J. W., Dadfarnia, M., Stubbins, J. F. & Sofronis, P., Jan 1 2017, In : Journal of the Mechanics and Physics of Solids. 98, p. 49-62 14 p.

Research output: Contribution to journalArticle

heat resistant alloys
cavitation flow
Superalloys
Cavitation
Creep

Stability of nanoclusters in an oxide dispersion strengthened alloy under neutron irradiation

Liu, X., Miao, Y., Wu, Y., Maloy, S. A. & Stubbins, J. F., Sep 2017, In : Scripta Materialia. 138, p. 57-61 5 p.

Research output: Contribution to journalArticle

Neutron irradiation
Nanoclusters
neutron irradiation
nanoclusters
Oxides
2016

Biaxial Thermal Creep of Alloy 617 and Alloy 230 for VHTR Applications

Mo, K., Lv, W., Tung, H. M., Yun, D., Miao, Y., Lan, K. C. & Stubbins, J. F., Jul 1 2016, In : Journal of Engineering Materials and Technology, Transactions of the ASME. 138, 3, 031015.

Research output: Contribution to journalArticle

High temperature gas reactors
Creep
reactors
Inconel (trademark)
carbides

Greenhouse Gas Emissions, Energy Efficiency, and Cost of Synthetic Fuel Production Using Electrochemical CO2 Conversion and the Fischer-Tropsch Process

Li, X., Anderson, P., Jhong, H. R. M., Paster, M., Stubbins, J. F. & Kenis, P. J. A., Jul 21 2016, In : Energy and Fuels. 30, 7, p. 5980-5989 10 p.

Research output: Contribution to journalArticle

Synthetic fuels
Gas emissions
Greenhouse gases
Energy efficiency
Diesel fuels

High energy X-ray diffraction study of the relationship between the macroscopic mechanical properties and microstructure of irradiated HT-9 steel

Tomchik, C., Almer, J., Anderoglu, O., Balogh, L., Brown, D. W., Clausen, B., Maloy, S. A., Sisneros, T. A. & Stubbins, J. F., Jul 1 2016, In : Journal of Nuclear Materials. 475, p. 46-56 11 p.

Research output: Contribution to journalArticle

Steel
steels
mechanical properties
X ray diffraction
Mechanical properties

In situ synchrotron tensile investigations on 14YWT, MA957, and 9-Cr ODS alloys

Lin, J. L., Mo, K., Yun, D., Miao, Y., Liu, X., Zhao, H., Hoelzer, D. T., Park, J. S., Almer, J., Zhang, G., Zhou, Z., Stubbins, J. F. & Yacout, A. M., Apr 1 2016, In : Journal of Nuclear Materials. 471, p. 289-298 10 p.

Research output: Contribution to journalArticle

Nanoclusters
nanoclusters
Synchrotrons
synchrotrons
steels

Investigation of high-energy ion-irradiated MA957 using synchrotron radiation under in-situ tension

Mo, K., Yun, D., Miao, Y., Liu, X., Pellin, M., Almer, J., Park, J. S., Stubbins, J. F., Zhu, S. & Yacout, A. M., Jan 1 2016, In : Materials. 9, 1, 15.

Research output: Contribution to journalArticle

Synchrotron radiation
Ions
Radiation hardening
Radiation
X ray diffraction

Investigation of thermal aging effects on the tensile properties of Alloy 617 by in-situ synchrotron wide-angle X-ray scattering

Liu, X., Mo, K., Miao, Y., Lan, K. C., Zhang, G., Chen, W. Y., Tomchik, C., Seibert, R., Terry, J. & Stubbins, J. F., Jan 10 2016, In : Materials Science and Engineering A. 651, p. 55-62 8 p.

Research output: Contribution to journalArticle

Thermal aging
tensile properties
X ray scattering
Synchrotrons
Tensile properties

Load-partitioning in an oxide dispersion-strengthened 310 steel at elevated temperatures

Miao, Y., Mo, K., Zhou, Z., Liu, X., Lan, K. C., Zhang, G., Park, J. S., Almer, J. & Stubbins, J. F., Dec 5 2016, In : Materials and Design. 111, p. 622-630 9 p.

Research output: Contribution to journalArticle

Steel
Oxides
Synchrotrons
Temperature
Oxygen

Mechanical properties of UO2 thin films under heavy ion irradiation using nanoindentation and finite element modeling

Elbakhshwan, M. S., Miao, Y., Stubbins, J. F. & Heuser, B. J., Oct 1 2016, In : Journal of Nuclear Materials. 479, p. 548-558 11 p.

Research output: Contribution to journalArticle

Heavy Ions
Nanoindentation
Ion bombardment
nanoindentation
ion irradiation

Neutron irradiation effects in Fe and Fe-Cr at 300 °c

Chen, W. Y., Miao, Y., Gan, J., Okuniewski, M. A., Maloy, S. A. & Stubbins, J. F., Jun 1 2016, In : Acta Materialia. 111, p. 407-416 10 p.

Research output: Contribution to journalArticle

Neutron irradiation
Hardening
Irradiation
Microstructure
Dislocations (crystals)

Size-dependent characteristics of ultra-fine oxygen-enriched nanoparticles in austenitic steels

Miao, Y., Mo, K., Zhou, Z., Liu, X., Lan, K. C., Zhang, G., Miller, M. K., Powers, K. A. & Stubbins, J. F., Nov 1 2016, In : Journal of Nuclear Materials. 480, p. 195-201 7 p.

Research output: Contribution to journalArticle

Austenitic steel
steels
Oxygen
Nanoparticles
Steel

The comparison of microstructures and mechanical properties between 14Cr-Al and 14Cr-Ti ferritic ODS alloys

Zhang, G., Zhou, Z., Mo, K., Miao, Y., Li, S., Liu, X., Wang, M., Park, J. S., Almer, J. & Stubbins, J. F., May 15 2016, In : Materials and Design. 98, p. 61-67 7 p.

Research output: Contribution to journalArticle

Mechanical properties
Microstructure
X ray diffraction
Synchrotrons
Plastic deformation
2015

Atom probe study of irradiation-enhanced α precipitation in neutron-irradiated Fe-Cr model alloys

Chen, W. Y., Miao, Y., Wu, Y., Tomchik, C. A., Mo, K., Gan, J., Okuniewski, M. A., Maloy, S. A. & Stubbins, J. F., Jul 1 2015, In : Journal of Nuclear Materials. 462, p. 242-249 8 p.

Research output: Contribution to journalArticle

Precipitates
precipitates
Neutrons
Irradiation
neutrons

Defect structures induced by high-energy displacement cascades in γ uranium

Miao, Y., Beeler, B., Deo, C., Baskes, M. I., Okuniewski, M. A. & Stubbins, J. F., Jan 2015, In : Journal of Nuclear Materials. 456, p. 1-6 6 p.

Research output: Contribution to journalArticle

Uranium
Defect structures
uranium
cascades
embedded atom method

In situ synchrotron tensile investigations on the phase responses within an oxide dispersion-strengthened (ODS) 304 steel

Miao, Y., Mo, K., Zhou, Z., Liu, X., Lan, K. C., Zhang, G., Miller, M. K., Powers, K. A., Almer, J. & Stubbins, J. F., Feb 1 2015, In : Materials Science and Engineering A. 625, p. 146-152 7 p.

Research output: Contribution to journalArticle

phase response
Steel
Stainless Steel
Synchrotrons
Oxides

Load partitioning between ferrite/martensite and dispersed nanoparticles of a 9Cr ferritic/martensitic (F/M) ODS steel at high temperatures

Zhang, G., Mo, K., Miao, Y., Liu, X., Almer, J., Zhou, Z. & Stubbins, J. F., Jun 8 2015, In : Materials Science and Engineering A. 637, p. 75-81 7 p.

Research output: Contribution to journalArticle

Martensitic steel
Ferritic steel
martensite
Martensite
residual stress

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

Miao, Y., Mo, K., Zhou, Z., Liu, X., Lan, K. C., Zhang, G., Miller, M. K., Powers, K. A., Mei, Z. G., Park, J. S., Almer, J. & Stubbins, J. F., Jan 1 2015, In : Materials Science and Engineering A. 639, p. 585-596 12 p.

Research output: Contribution to journalArticle

Steel
Synchrotrons
Oxides
Electron microscopy
Tomography

The electrical AC impedance response of oxide scales on 9Cr-1Mo steel immersed in molten lead-bismuth eutectic alloy at 200°C

Bolind, A. M., Lillard, R. S. & Stubbins, J. F., Mar 1 2015, In : Corrosion Science. 92, p. 48-57 10 p.

Research output: Contribution to journalArticle

Steel
Bismuth
Oxides
Eutectics
Molten materials

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

Zhang, G., Zhou, Z., Mo, K., Miao, Y., Liu, X., Almer, J. & Stubbins, J. F., Dec 1 2015, In : Journal of Nuclear Materials. 467, p. 50-57 8 p., 49323.

Research output: Contribution to journalArticle

tensile deformation
Martensitic steel
Ferritic steel
residual stress
Residual stresses

The interfacial orientation relationship of oxide nanoparticles in a hafnium-containing oxide dispersion-strengthened austenitic stainless steel

Miao, Y., Mo, K., Cui, B., Chen, W. Y., Miller, M. K., Powers, K. A., McCreary, V., Gross, D., Almer, J., Robertson, I. M. & Stubbins, J. F., Apr 2015, In : Materials Characterization. 101, p. 136-143 8 p.

Research output: Contribution to journalArticle

Hafnium
hafnium oxides
austenitic stainless steels
Austenitic stainless steel
Oxides

The microstructure and mechanical properties of Al-containing 9Cr ODS ferritic alloy

Zhang, G., Zhou, Z., Mo, K., Wang, P., Miao, Y., Li, S., Wang, M., Liu, X., Gong, M., Almer, J. & Stubbins, J. F., Jul 9 2015, In : Journal of Alloys and Compounds. 648, p. 223-228 6 p.

Research output: Contribution to journalArticle

Oxides
Mechanical properties
Microstructure
Tensile strength
Mechanical alloying
2014

Biaxial thermal creep-fatigue of inconel 617 at 950°C

Lan, K. C., Mo, K. & Stubbins, J. F., 2014, In : Transactions of the American Nuclear Society. 110, p. 857-858 2 p.

Research output: Contribution to journalArticle

Creep
Fatigue of materials
Hot Temperature

Biaxial thermal creep of Inconel 617 and Haynes 230 at 850 and 950°C

Tung, H. M., Mo, K. & Stubbins, J. F., Apr 1 2014, In : Journal of Nuclear Materials. 447, 1-3, p. 28-37 10 p.

Research output: Contribution to journalArticle

Inconel (trademark)
Creep
tensile creep
creep tests
creep strength

Effect of creep and oxidation on reduced fatigue life of Ni-based alloy 617 at 850 °c

Chen, X., Yang, Z., Sokolov, M. A., Erdman, D. L., Mo, K. & Stubbins, J. F., Jan 1 2014, In : Journal of Nuclear Materials. 444, 1-3, p. 393-403 11 p.

Research output: Contribution to journalArticle

fatigue life
Creep
Fatigue of materials
Oxidation
oxidation

Response of oxide particles to externally applied stress in austenitic ods alloys

Miao, Y., Mo, K., Liu, X., Zhou, Z., Aimer, J. & Stubbins, J. F., Jan 1 2014, In : Transactions of the American Nuclear Society. 110, p. 853-854 2 p.

Research output: Contribution to journalArticle

Oxides

Synchrotron study on load partitioning between ferrite/martensite and nanoparticles of a 9Cr ODS steel

Mo, K., Zhou, Z., Miao, Y., Yun, D., Tung, H. M., Zhang, G., Chen, W., Almer, J. & Stubbins, J. F., Dec 2014, In : Journal of Nuclear Materials. 455, 1-3, p. 376-381 6 p.

Research output: Contribution to journalArticle

Steel
martensite
Synchrotrons
Martensite
Oxides

The evolution mechanism of the dislocation loops in irradiated lanthanum doped cerium oxide

Miao, Y., Aidhy, D., Chen, W. Y., Mo, K., Oaks, A., Wolf, D. & Stubbins, J. F., Feb 1 2014, In : Journal of Nuclear Materials. 445, 1-3, p. 209-217 9 p.

Research output: Contribution to journalArticle

Lanthanum
cerium oxides
Cerium
lanthanum
dioxides

The incorporation and migration of a single xenon atom in ceria

Miao, Y., Chen, W. Y., Oaks, A., Mo, K. & Stubbins, J. F., Jun 2014, In : Journal of Nuclear Materials. 449, 1-3, p. 242-247 6 p.

Research output: Contribution to journalArticle

Xenon
Cerium compounds
xenon
Atoms
atoms
2013

Characterization of dislocation loops in CeO2 irradiated with high energy Krypton and Xenon

Chen, W. Y., Wen, J., Kirk, M. A., Miao, Y., Ye, B., Kleinfeldt, B. R., Oaks, A. J. & Stubbins, J. F., Dec 1 2013, In : Philosophical Magazine. 93, 36, p. 4569-4581 13 p.

Research output: Contribution to journalArticle

krypton
xenon
transmission electron microscopy
energy
ions
Nanoindentation
Ion bombardment
Heavy ions
Thin films
Mechanical properties

Effect of orientation on plastic deformations of Alloy 617 for VHTR applications

Mo, K., Lovicu, G., Tung, H. M., Chen, X., Miao, Y., Hansen, J. B. & Stubbins, J. F., Sep 3 2013, In : Journal of Nuclear Materials. 443, 1-3, p. 366-377 12 p.

Research output: Contribution to journalArticle

High temperature gas reactors
plastic deformation
Plastic deformation
reactors
yield strength

Experimental and modeling results of creep-fatigue life of Inconel 617 and Haynes 230 at 850 °c

Chen, X., Sokolov, M. A., Sham, S., Erdman, D. L., Busby, J. T., Mo, K. & Stubbins, J. F., Jan 1 2013, In : Journal of Nuclear Materials. 432, 1-3, p. 94-101 8 p.

Research output: Contribution to journalArticle

Inconel (trademark)
fatigue life
Creep
Fatigue of materials
fatigue tests

Irradiation effects in UO2 and CeO2

Ye, B., Oaks, A., Kirk, M., Yun, D., Chen, W. Y., Holtzman, B. & Stubbins, J. F., Jan 1 2013, In : Journal of Nuclear Materials. 441, 1-3, p. 525-529 5 p.

Research output: Contribution to journalArticle

Irradiation
dosage
irradiation
Ions
Xenon

KMC clustering model comparison in BCC iron

Oaks, A. & Stubbins, J. F., Apr 19 2013, In : Journal of Nuclear Materials. 442, 1-3 SUPPL.1

Research output: Contribution to journalArticle

Iron
iron
Kinetics
Steel
radii

Low cycle fatigue and creep-fatigue behavior of Ni-based alloy 230 at 850°C

Chen, X., Yang, Z., Sokolov, M. A., Erdman, D. L., Mo, K. & Stubbins, J. F., Feb 15 2013, In : Materials Science and Engineering A. 563, p. 152-162 11 p.

Research output: Contribution to journalArticle

fatigue life
Creep
Fatigue of materials
cycles
grain boundaries

Mechanism of plastic deformation of a Ni-based superalloy for VHTR applications

Mo, K., Lovicu, G., Chen, X., Tung, H. M., Hansen, J. B. & Stubbins, J. F., Jan 1 2013, In : Journal of Nuclear Materials. 441, 1-3, p. 695-703 9 p.

Research output: Contribution to journalArticle

heat resistant alloys
Superalloys
plastic deformation
Plastic deformation
cracks

Strain-rate sensitivity analysis for Ni alloys to be used in Very High Temperature Reactors

Mo, K., Tung, H. M., Chen, X., Zhao, Y., Hansen, J. & Stubbins, J. F., Sep 2013, In : Nuclear Technology. 183, 3, p. 455-463 9 p.

Research output: Contribution to journalArticle

High temperature gas reactors
sensitivity analysis
Sensitivity analysis
strain rate
Strain rate

Synchrotron radiation study on alloy 617 and alloy 230 for VHTR application

Mo, K., Tung, H. M., Almer, J., Li, M., Chen, X., Chen, W., Hansen, J. B. & Stubbins, J. F., Dec 4 2013, In : Journal of Pressure Vessel Technology, Transactions of the ASME. 135, 2, 021502.

Research output: Contribution to journalArticle

Synchrotron radiation
Carbides
Synchrotrons
X rays
Residual stresses
2012

Fission gas transport and its interactions with irradiation-induced defects in lanthanum doped ceria

Yun, D., Ye, B., Oaks, A. J., Chen, W., Kirk, M. A., Rest, J., Yacout, A. M. & Stubbins, J. F., Feb 1 2012, In : Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms. 272, p. 239-243 5 p.

Research output: Contribution to journalArticle

gas transport
Cerium compounds
Lanthanum
lanthanum
fission