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Jeremy T. Busby
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Roles of vacancy/interstitial diffusion and segregation in the microchemistry at grain boundaries of irradiated Fe-Cr-Ni alloys
Defect sink characteristics of specific grain boundary types in 304 stainless steels under high dose neutron environments
Deformation localization and dislocation channel dynamics in neutron-irradiated austenitic stainless steels
Development of a robust modeling tool for radiation-induced segregation in austenitic stainless steels
LAMDA: A facility for advanced characterization of irradiated materials at Oak Ridge national laboratory
Role of scale factor during tensile testing of small specimens
Microstructural characterization of deformation localization at small strains in a neutron-irradiated 304 stainless steel
Concrete aging and degradation in NPPs: LWRS program R\&D progress report
Dependence on grain boundary structure of radiation induced segregation in a 9 wt.\% Cr model ferritic/martensitic steel
Dependence on grain boundary structure of radiation induced segregation in a 9 wt.\% Cr model ferritic/martensitic steel
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