Nedim N Cinbiz Nuclear Materials R&D Staff Contact CINBIZMN@ORNL.GOV All Publications The state of the art for neutron irradiation experiments from the perspective of the High Flux Isotope Reactor (HFIR) Damage progression and failure of SiC/SiC composite tubes under hard-contact radial expansion A Standardized Analysis Process Using Digital Image Correlation to Calculate In Situ Cladding Strain from Modified Burst Test... Mechanical property assessment of unirradiated cladding after exposure to time at temperature Rapid Solidification Effects in Additively Manufactured Si and SiGe Compositions Superionic-like diffusion in yttrium dihydride Phase stability and microstructure of neutron-irradiated substoichiometric yttrium dihydrides Hydrogen permeation in iron-chromium-aluminum (FeCrAl) alloys and the effects of microstructure and surface oxide Effect of impurities on hydrogen defect stability and migration barrier in yttrium dihydride crystal Challenges in developing materials for microreactors: A case-study of yttrium dihydride in extreme conditions Rupture Properties of Hydrided Fuel Cladding During Simulated LOCA Conditions Irradiation and Mechanical Testing of Chromium-Coated M5Framatome Cladding Tubes MECHANICAL BEHAVIOR OF FRESH, HYDRIDED, AND Cr-COATED CLADDING TUBES AND SUB-SIZED FLAT SPECIMENS Community Data Contribution to M.E.T.A. with ATF-relevant Hydrided Zr cladding (Coated and Uncoated) Hydrogen Effects on Cladding Performance during Simulated Loss of Coolant Accident Testing... Report on RIA Relevant Modified Burst Testing of ATF Cladding Materials Hydrogen motion in near stoichiometric yttrium dihydride at elevated temperatures Impact of nano-scale cavities on hydrogen storage and retention in yttrium hydride... Mechanical failure of fresh nuclear grade iron–chromium–aluminum (FeCrAl) cladding under simulated hot zero power reactivity initiated accident conditions Biaxial Creep Behavior of Nb-Modified Zircaloys Length Dependence of Severe Accident Test Station Integral Testing Hydrogen in zirconium alloys: A review Progress Report on Modified Burst Testing and Alternative Test Methodologies An advanced experimental design for modified burst testing of nuclear fuel cladding materials during transient loading Failure behavior of SiC/SiC composite tubes under strain rates similar to the pellet-cladding mechanical interaction phase of reactivity-initiated accidents Pagination Current page 1 Page 2 Next page ›› Last page Last » Key Links ORCID Organizations Physical Sciences Directorate Materials Science and Technology Division Materials in Extremes Section Radiation Effects and Microstructural Analysis Group
