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Fingerprint Fingerprint is based on mining the text of the expert's scholarly documents to create an index of weighted terms, which defines the key subjects of each individual researcher.

Irradiation Engineering & Materials Science
Temperature Engineering & Materials Science
irradiation Physics & Astronomy
Copper alloys Engineering & Materials Science
Creep Engineering & Materials Science
Fatigue of materials Engineering & Materials Science
Neutrons Engineering & Materials Science
Oxides Chemical Compounds

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Research Output 1975 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

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 journalArticle

Austenitic stainless steel

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)

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

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
Mechanical properties