Structural materials for fission & fusion energy von Zinkle, Steven J., Busby, Jeremy T.

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Radiation-induced degradation of stainless steel light water reactor internals von Kenik, Edward A., Busby, Jeremy T.

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Thermodynamic modeling and experimental study of the Fe–Cr–Zr system von Yang, Ying, Tan, Lizhen, Bei, Hongbin, Busby, Jeremy T.

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The relationship between hardness and yield stress in irradiated austenitic and ferritic steels von Busby, Jeremy T., Hash, Mark C., Was, Gary S.

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Thermophysical and mechanical properties of near-stoichiometric fiber CVI SiC/SiC composites after neutron irradiation at elevated temperatures von Katoh, Yutai, Snead, Lance L., Nozawa, Takashi, Kondo, Sosuke, Busby, Jeremy T.

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Thermal Stability of Intermetallic Phases in Fe-rich Fe-Cr-Ni-Mo Alloys von Yang, Ying, Tan, Lizhen, Busby, Jeremy T.

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Influence of thermal and radiation effects on microstructural and mechanical properties of Nb–1Zr von Leonard, Keith J., Busby, Jeremy T., Zinkle, Steven J.

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Defect sink characteristics of specific grain boundary types in 304 stainless steels under high dose neutron environments von Field, Kevin G., Yang, Ying, Allen, Todd R., Busby, Jeremy T.

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Dependence on grain boundary structure of radiation induced segregation in a 9 wt.% Cr model ferritic/martensitic steel von FIELD, Kevin G, BARNARD, Leland M, PARISH, Chad M, BUSBY, Jeremy T, MORGAN, Dane, ALLEN, Todd R

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Radiation-induced segregation and phase stability in ferritic–martensitic alloy T 91 von Wharry, Janelle P., Jiao, Zhijie, Shankar, Vani, Busby, Jeremy T., Was, Gary S.

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Microstructural characterization of deformation localization at small strains in a neutron-irradiated 304 stainless steel von Field, Kevin G., Gussev, Maxim N., Busby, Jeremy T.

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Zirconium alloys for supercritical water reactor applications: Challenges and possibilities von Motta, Arthur T., Yilmazbayhan, Aylin, da Silva, Marcelo J. Gomes, Comstock, Robert J., Was, Gary S., Busby, Jeremy T., Gartner, Eric, Peng, Qunjia, Jeong, Yong Hwan, Park, Jeong Yong

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Experimental and modeling results of creep–fatigue life of Inconel 617 and Haynes 230 at 850°C von Chen, Xiang, Sokolov, Mikhail A., Sham, Sam, Erdman III, Donald L., Busby, Jeremy T., Mo, Kun, Stubbins, James F.

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Aging effects on microstructural and mechanical properties of select refractory metal alloys for space-reactor applications von Leonard, Keith J., Busby, Jeremy T., Zinkle, Steven J.

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Dependence on grain boundary structure of radiation induced segregation in a 9wt.% Cr model ferritic/martensitic steel von Field, Kevin G., Barnard, Leland M., Parish, Chad M., Busby, Jeremy T., Morgan, Dane, Allen, Todd R.

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Formulating the strength factor α for improved predictability of radiation hardening von Tan, L., Busby, J.T.

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Microstructural and mechanical property changes with aging of Mo–41Re and Mo–47.5Re alloys von Leonard, Keith J., Busby, Jeremy T., Zinkle, Steven J.

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Deformation localization and dislocation channel dynamics in neutron-irradiated austenitic stainless steels von Gussev, Maxim N., Field, Kevin G., Busby, Jeremy T.

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Nb-Base FS-85 Alloy as a Candidate Structural Material for Space Reactor Applications: Effects of Thermal Aging von Leonard, Keith J., Busby, Jeremy T., Hoelzer, David T., Zinkle, Steven J.

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Integrated modeling of second phase precipitation in cold-worked 316 stainless steels under irradiation von Mamivand, Mahmood, Yang, Ying, Busby, Jeremy, Morgan, Dane

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