James F Stubbins

Search results

• 2022

  A study on texture stability and the biaxial creep behavior of as-hydrided CWSR Zircaloy-4 cladding at the effective stresses from 55 MPa to 65 MPa and temperatures from 300 °C to 400 °C

  Lan, K. C., Chuang, C. P., Tung, H. M., Mo, K., Miao, Y., Liu, X., Lee, H., Park, J. S., Almer, J. & Stubbins, J. F., Jun 2022, In: Journal of Nuclear Materials. 564, 153688.

  Research output: Contribution to journal › Article › peer-review

  • Creep Behavior 100%
  • Zircaloy 91%
  • Crystalline Texture 64%
  • Hydrides 62%
  • textures 55%

• Effects of diffusion and primary creep on intergranular cavitation at high temperatures

  Sanders, J. W., Jamshidi, N., Jamshidi, N., Dadfarnia, M., Subramanian, S., Sehitoglu, H., Stubbins, J. & Sofronis, P., 2022, (Accepted/In press) In: International Journal of Fracture.

  Research output: Contribution to journal › Article › peer-review

  • Cavitation 100%
  • Creep 90%
  • Surface diffusion 49%
  • Surface Diffusion 47%
  • Temperature 28%
• 2021

  Early-stage microstructural evolution and phase stability in neutron-irradiated ferritic-martensitic steel T91

  Yan, H., Liu, X., He, L. & Stubbins, J., Dec 15 2021, In: Journal of Nuclear Materials. 557, 153207.

  Research output: Contribution to journal › Article › peer-review

  • Dislocation Loop 100%
  • Phase stability 78%
  • Microstructural evolution 67%
  • Phase Stability 66%
  • Neutrons 59%

• Phase Stability and Microstructural Evolution in Neutron-irradiated Ferritic-martensitic Steel HT9

  Yan, H., Liu, X., He, L. & Stubbins, J., Dec 15 2021, In: Journal of Nuclear Materials. 557, 153252.

  Research output: Contribution to journal › Article › peer-review

  • Phase stability 100%
  • Dislocation Loop 95%
  • Microstructural evolution 85%
  • Phase Stability 84%
  • Neutrons 76%

• Simulation of Intergranular Void Growth Under the Combined Effects of Surface Diffusion, Grain Boundary Diffusion, and Bulk Creep

  Sanders, J. W., Jamshidi, N., Jamshidi, N., Dadfarnia, M., Subramanian, S. & Stubbins, J., 2021, TMS 2021 150th Annual Meeting and Exhibition Supplemental Proceedings. Springer, p. 853-863 11 p. (Minerals, Metals and Materials Series; vol. 5).

  Research output: Chapter in Book/Report/Conference proceeding › Conference contribution

  • Grain Boundary Diffusion 100%
  • Surface diffusion 97%
  • Nuclear reactors 69%
  • Grain boundaries 63%
  • Simulation 40%

• The cultural dynamics of energy: The impact of lived experience, preference and demographics on future energy policy in the United States

  Chapman, A., Shigetomi, Y., Chandra Karmaker, S., Baran Saha, B., Huff, K., Brooks, C. & Stubbins, J., Oct 2021, In: Energy Research and Social Science. 80, 102231.

  Research output: Contribution to journal › Article › peer-review

  • Energy policy 100%
  • energy 57%
  • income 44%
  • experience 25%
  • American Indian 18%

• The role of current and emerging technologies in meeting Japan's mid- to long-term carbon reduction goals

  Chaube, A., Chapman, A., Minami, A., Stubbins, J. & Huff, K. D., Dec 15 2021, In: Applied Energy. 304, 117669.

  Research output: Contribution to journal › Article › peer-review

  • emission reduction 100%
  • Carbon capture 83%
  • Hydrogen 81%
  • hydrogen 79%
  • Carbon 77%
• 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 journal › Article › peer-review

  Open Access

  • austenitic stainless steels 100%
  • Neutrons 94%
  • Precipitates 88%
  • Transmission electron microscopy 88%
  • Neutron Irradiation 83%

• Investigating creep behavior of Ni–Cr–W alloy pressurized tube at 950 °C by using in-situ creep testing system

  Zhong, Y., Lan, K. C., Lee, H., Zhou, B., Wang, Y., Tsang, D. K. L. & Stubbins, J. F., Jul 2020, In: Nuclear Engineering and Technology. 52, 7, p. 1481-1485 5 p.

  Research output: Contribution to journal › Article › peer-review

  Open Access

  • Thermal fatigue 24%
  • Argon 11%
  • Fatigue of materials 6%
  • Finite element method 6%
  • Gases 5%

• On the biaxial thermal creep-fatigue behavior of Ni-base Alloy 617 at 950 °C

  Zhong, Y., Liu, X., Lan, K. C., Lee, H., Tsang, D. K. L. & Stubbins, J. F., Oct 2020, In: International Journal of Fatigue. 139, 105787.

  Research output: Contribution to journal › Article › peer-review

  • Fatigue 95%
  • Creep 88%
  • Alloy 49%
  • Fatigue of materials 48%
  • Hot Temperature 34%

• On the stress field ahead of a stationary crack tip during the transition from primary to secondary creep

  Sanders, J. W., Dadfarnia, M., Sehitoglu, H., Stubbins, J. & Sofronis, P., Jun 1 2020, In: International Journal of Solids and Structures. 193-194, p. 455-473 19 p.

  Research output: Contribution to journal › Article › peer-review

  Open Access

  • Creep 96%
  • Stress Field 90%
  • crack tips 82%
  • stress distribution 71%
  • Flow Stress 22%

• Radiation response of a Fe–20Cr–25Ni austenitic stainless steel under Fe²⁺ irradiation at 500 °C

  Liu, X., Gigax, J. G., Poplawsky, J. D., Guo, W., Kim, H., Shao, L., Garner, F. A. & Stubbins, J. F., Mar 2020, In: Materialia. 9, 100542.

  Research output: Contribution to journal › Article › peer-review

  • Irradiation 100%
  • Austenitic stainless steel 92%
  • Dislocation Loop 89%
  • Radiation 77%
  • Dose 75%

• The role of hydrogen in achieving long term Japanese energy system goals

  Chaube, A., Chapman, A., Shigetomi, Y., Huff, K. & Stubbins, J., Sep 2020, In: Energies. 13, 17, 4539.

  Research output: Contribution to journal › Article › peer-review

  Open Access

  • Hydrogen 100%
  • Hydrogen economy 83%
  • Energy 50%
  • Term 40%
  • Power generation 32%
• 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 journal › Article › peer-review

  • Zircaloy 2 (trademark) 100%
  • Zircaloy 92%
  • steam 71%
  • Dissolution 70%
  • Intermetallics 70%

• 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 journal › Article › peer-review

  • Ion bombardment 100%
  • Heavy ions 88%
  • Nitrides 75%
  • Nitride 60%
  • Molybdenum 31%

• 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 journal › Article › peer-review

  • Thermal Aging 100%
  • Thermal aging 94%
  • Microhardness 60%
  • Alloy 52%
  • Microstructure 50%
• 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 journal › Article › peer-review

  • Coarsening 100%
  • Helium 92%
  • helium 64%
  • bubbles 63%
  • Surface diffusion 63%

• 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 journal › Article › peer-review

  • Creep Behavior 100%
  • Zircaloy 91%
  • hydrides 33%
  • retraining 32%
  • Optical Microscopy 29%

• In-situ synchrotron x-ray scattering study on the tensile properties of neutron irradiated ferritic/martensitic alloys

  Lee, H., Liu, X., Lan, K. C., Yan, H., Li, M., Zhang, X., Xu, C., Park, J. S., Almer, J. & Stubbins, J. F., 2018, In: Transactions of the American Nuclear Society. 118, p. 1651-1653 3 p.

  Research output: Contribution to journal › Conference article › peer-review

• Radiation-induced microstructural evolution and hardening of austenitic alloy 709

  Liu, X., Gigax, J., Shao, L., Garner, F. A. & Stubbins, J. F., 2018, AISTech 2018 Proceedings - Iron and Steel Technology Conference and Exposition. Association for Iron and Steel Technology, AISTECH, p. 1480-1482 3 p. (AISTech - Iron and Steel Technology Conference Proceedings; vol. 2018-May).

  Research output: Chapter in Book/Report/Conference proceeding › Conference contribution

• Radiation-induced microstructural evolution and hardening of austenitic alloy 709

  Liu, X., Gigax, J., Shao, L., Garner, F. A. & Stubbins, J. F., 2018, In: Transactions of the American Nuclear Society. 118, p. 1480-1482 3 p.

  Research output: Contribution to journal › Conference article › peer-review

• 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 journal › Article › peer-review

  • radiation tolerance 100%
  • Oxides 72%
  • Radiation 66%
  • Alloy 59%
  • Resistance 53%

• 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 journal › Article › peer-review

  • Cold-Shock Response 100%
  • Electrons 59%
  • Zirconium 31%
  • Hydrofluoric Acid 10%
  • Corrosion 8%
• 2017

  Biaxial thermal creep of alloy 617 and alloy 230 for vhtr applications

  Mo, K., Yun, D., Lv, W., Miao, Y., Tung, H. M. & Stubbins, J. F., Jan 1 2017, ASME 2014 Symposium on Elevated Temperature Application of Materials for Fossil, Nuclear, and Petrochemical Industries, ETAM 2014. American Society of Mechanical Engineers, (ASME 2014 Symposium on Elevated Temperature Application of Materials for Fossil, Nuclear, and Petrochemical Industries, ETAM 2014).

  Research output: Chapter in Book/Report/Conference proceeding › Conference contribution

  • Hot Temperature 50%
  • Coarsening 10%
  • effective stress 9%
  • Nucleation 9%
  • Grain boundaries 8%

• 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 journal › Article › peer-review

  Open Access

  • Dislocation Loop 100%
  • Strain Hardening 75%
  • Neutrons 59%
  • Polycrystalline Solid 48%
  • Neutron Irradiation 39%

• 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 journal › Article › peer-review

  • Ion bombardment 100%
  • ion irradiation 65%
  • Irradiation 64%
  • steels 45%
  • Ions 34%

• Neutron and ion irradiation studies on advanced steels using the nuclear science user facilities

  Liu, X., Miao, Y., Chen, W. Y., Wu, Y., Li, M. & Stubbins, J. F., 2017, In: Transactions of the American Nuclear Society. 116, p. 369-370 2 p.

  Research output: Contribution to journal › Conference article › peer-review

• 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 journal › Article › peer-review

  • Cavitation 100%
  • Superalloys 97%
  • heat resistant alloys 95%
  • cavitation flow 88%
  • voids 39%

• 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 journal › Article › peer-review

  • Neutron irradiation 84%
  • Neutron Irradiation 83%
  • nanoclusters 63%
  • neutron irradiation 63%
  • Oxides 49%
• 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 journal › Article › peer-review

  • reactors 58%
  • Alloy 53%
  • Hot Temperature 36%
  • Application 24%
  • Inconel (trademark) 19%

• 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 journal › Article › peer-review

  • Synthetic fuels 100%
  • Fischer-Tropsch Reaction 98%
  • Diesel Fuel 83%
  • Gas emissions 72%
  • Greenhouse gases 71%

• 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 journal › Article › peer-review

  Open Access

  • steels 59%
  • Irradiation 54%
  • Microstructure 54%
  • mechanical properties 53%
  • Mechanical properties 52%

• 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 journal › Article › peer-review

  Open Access

  • Synchrotrons 76%
  • nanoclusters 63%
  • synchrotrons 49%
  • Alloy 40%
  • Nanoparticles 38%

• 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., 2016, In: Materials. 9, 1, 15.

  Research output: Contribution to journal › Article › peer-review

  Open Access

  • Synchrotron radiation 100%
  • Synchrotron Radiation 74%
  • Tension 67%
  • Ions 64%
  • synchrotron radiation 62%

• 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 journal › Article › peer-review

  Open Access

  • Thermal Aging 85%
  • Synchrotrons 84%
  • Thermal aging 79%
  • Yield Point 73%
  • tensile properties 71%

• Investigation on thermal treatments of high-resistance austenitic stainless steels employed as structural materials in generation IV reactors

  Mazzei, G. B., Lo Frano, R. & Stubbins, J. F., 2016, Student Paper Competition. American Society of Mechanical Engineers (ASME), V005T15A052. (International Conference on Nuclear Engineering, Proceedings, ICONE; vol. 5).

  Research output: Chapter in Book/Report/Conference proceeding › Conference contribution

  • Austenitic stainless steel 100%
  • Heat treatment 91%
  • Neutron irradiation 30%
  • Microstructural evolution 26%
  • Swelling 23%

• 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 journal › Article › peer-review

  Open Access

  • Oxides 100%
  • Strain 81%
  • Steel 67%
  • Oxide 62%
  • Synchrotrons 61%

• 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 journal › Article › peer-review

  • Ion bombardment 100%
  • Heavy ions 88%
  • ion irradiation 65%
  • Irradiation 64%
  • nanoindentation 63%

• 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 journal › Article › peer-review

  Open Access

  • Dislocation Loop 100%
  • Neutron irradiation 79%
  • Neutron Irradiation 79%
  • Irradiation 55%
  • Hardening 50%

• 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 journal › Article › peer-review

  Open Access

  • Nanoparticles 100%
  • Austenitic stainless steel 95%
  • steels 74%
  • nanoparticles 68%
  • oxygen 60%

• 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 journal › Article › peer-review

  Open Access

  • Alloy 100%
  • Microstructure 96%
  • Mechanical properties 92%
  • Synchrotrons 27%
  • Transmission electron microscopy 20%
• 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 journal › Article › peer-review

  • Neutrons 100%
  • Atoms 94%
  • Precipitates 94%
  • Irradiation 93%
  • Phase Diagrams 83%

• 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 journal › Article › peer-review

  • Defect structures 100%
  • Crystal Defect 74%
  • Uranium 73%
  • Atoms 65%
  • uranium 64%

• 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 journal › Article › peer-review

  • Synchrotrons 100%
  • phase response 97%
  • Precipitates 78%
  • Austenitic stainless steel 71%
  • synchrotrons 65%

• In-situ synchrotron X-ray study of the elevated temperature deformation response of SS 316L pressurized creep tubes

  Mo, K., Tung, H. M., Chen, X., Yun, D., Miao, Y., Chen, W., Aimer, J., Novak, A. & Stubbins, J. F., 2015, Small Specimen Test Techniques: 6th Volume. Lucon, E. & Sokolov, M. A. (eds.). ASTM International, p. 244-255 12 p. (ASTM Special Technical Publication; vol. STP 1576).

  Research output: Chapter in Book/Report/Conference proceeding › Conference contribution

  • Synchrotrons 100%
  • X rays 68%
  • X-Ray 45%
  • Temperature 30%
  • Diffraction 27%

• 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 journal › Article › peer-review

  • Nanoparticles 81%
  • martensite 80%
  • Ferrite 80%
  • residual stress 75%
  • Residual stresses 71%

• 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., 2015, In: Materials Science and Engineering A. 639, p. 585-596 12 p.

  Research output: Contribution to journal › Article › peer-review

  • Synchrotrons 100%
  • Electron microscopy 97%
  • Atoms 78%
  • Precipitates 78%
  • Transmission electron microscopy 77%

• The dynamics of electricity grid operation with increasing renewables and the path toward maximum renewable deployment

  Li, X., Paster, M. & Stubbins, J., Aug 1 2015, In: Renewable and Sustainable Energy Reviews. 47, p. 1007-1015 9 p.

  Research output: Contribution to journal › Review article › peer-review

  • Electricity 100%

• 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 journal › Article › peer-review

  • Bismuth 100%
  • Eutectics 76%
  • Molten materials 73%
  • Lead 69%
  • Oxides 64%

• 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 journal › Article › peer-review

  • tensile deformation 100%
  • residual stress 74%
  • X rays 73%
  • Residual stresses 70%
  • steels 59%