Search

Maxim N. Gussev

Deconvoluting the Effect of Chromium and Aluminum on the Radiation Response of Wrought FeCrAl Alloys After Low-Dose Neutron Irradiation
Accident tolerant fecral fuel cladding: current status towards commercialization
Influence of welding and neutron irradiation on dislocation loop formation and $\alpha$′ precipitation in a FeCrAl alloy
Performance of a ferritic/martensitic steel for nuclear reactor applications fabricated using additive manufacturing
Sub-size tensile specimen design for in-reactor irradiation and post-irradiation testing
The Analysis of the General Performance and Mechanical Behavior of Unirradiated FeCrAl Alloys Before and After Welding
The Analysis of the General Performance and Mechanical Behavior of Unirradiated FeCrAl Alloys Before and After Welding
Deformation localization and dislocation channel dynamics in neutron-irradiated 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
Deformation behavior of laser welds in high temperature oxidation resistant Fe-Cr-Al alloys for fuel cladding applications
Microstructural characterization of deformation localization at small strains in a neutron-irradiated 304 stainless steel
FY-13 FCRD Milestone M3FT-13OR0202311 Weldability of ORNL Accident Tolerant Fuel Cladding Model Alloys For Thin Walled Tubes

Published with Wowchemy — the free, open source website builder that empowers creators.