Yukinori Yamamoto

Latest

Deconvoluting the Effect of Chromium and Aluminum on the Radiation Response of Wrought FeCrAl Alloys After Low-Dose Neutron Irradiation
Hydrothermal corrosion of 2nd generation FeCrAl alloys for accident tolerant fuel cladding
Accident tolerant fecral fuel cladding: current status towards commercialization
Designing for radiation tolerance in fecral alloys
Handbook on the Material Properties of FeCrAl Alloys for Nuclear Power Production Applications (FY18 Version: Revision 1.1) Prepared for U.S. Department of Energy Nuclear Technology R\&D Advanced Fuels Campaign FY18 version author(s): Kevin G. Field 1 FY17 version author(s)
A combined APT and SANS investigation of $\alpha$′ phase precipitation in neutron-irradiated model FeCrAl alloys
Dislocation loop formation in model FeCrAl alloys after neutron irradiation below 1 dpa
Heterogeneous dislocation loop formation near grain boundaries in a neutron-irradiated commercial FeCrAl alloy
Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys
ORNL/TM-2017/186 Rev.1 Handbook of FeCrAl Alloys for Nuclear Power Production Applications
ORNL/TM-2017/186 Rev.1 Handbook of FeCrAl Alloys for Nuclear Power Production Applications
Complementary Techniques for Quantification of $\alpha$' Phase Precipitation in Neutron-Irradiated Fe-Cr-Al Model Alloys
Complementary Techniques for Quantification of $\alpha$' Phase Precipitation in Neutron-Irradiated Fe-Cr-Al Model Alloys
Database on Performance of Neutron Irradiated FeCrAl Alloys
Dependencies of $\alpha$' embrittlement in neutron-irradiated model Fe-Cr-Al alloys
Effect of Alloying Additions on Wrought FeCrAl Alloys for Accident-Tolerant Fuel Cladding
Overview of the multifaceted activities towards development and deployment of nuclear-grade FeCrAl alloys
Status of Post Irradiation Examination of FCAB and FCAT Irradiation Capsules
Submission of FeCrAl Feedstock for Support of AFC ATR- 2 Irradiations
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
Current status of FeCrAl alloys as an accident tolerant cladding alloy class for commercial light water reactors
Evaluation of the Effect of Composition on Radiation Hardening and Embrittlement in Model FeCrAl Alloys, ORNL/TM-2015/518 M2FT-15OR02302243
Preliminary Results on FeCrAl Alloys in the As-received and Welded State Designed to Have Enhanced Weldability and Radiation Tolerance
Preliminary Results on FeCrAl Alloys in the As-received and Welded State Designed to Have Enhanced Weldability and Radiation Tolerance
Deformation behavior of laser welds in high temperature oxidation resistant Fe-Cr-Al alloys for fuel cladding applications
FY-13 FCRD Milestone M3FT-13OR0202311 Weldability of ORNL Accident Tolerant Fuel Cladding Model Alloys For Thin Walled Tubes