S.J. Zinkle
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View article: Investigation of Corrosion Behavior of Carbide Phase Strengthened Nickel‐Based Alloy in Molten Fluoride Salt
Investigation of Corrosion Behavior of Carbide Phase Strengthened Nickel‐Based Alloy in Molten Fluoride Salt Open
The corrosion behavior of a high creep strength carbide‐phase strengthened Ni‐based alloy in molten FLiNaK (LiF‐NaF‐KF: 46.5‐11.5‐42 mol%) salt in the temperature range of 700°C–750°C has been investigated as a part of the development of s…
View article: Determining the low temperature Cr solubility limit and precipitation mechanisms in Fe-Cr alloys with proton irradiations and thermal aging
Determining the low temperature Cr solubility limit and precipitation mechanisms in Fe-Cr alloys with proton irradiations and thermal aging Open
View article: Microstructure evolution in ultra-high purity Fe-Cr alloys under low-PKA proton irradiation
Microstructure evolution in ultra-high purity Fe-Cr alloys under low-PKA proton irradiation Open
View article: Thin film combinatorial sputtering of TaTiHfZr refractory compositionally complex alloys for rapid materials discovery
Thin film combinatorial sputtering of TaTiHfZr refractory compositionally complex alloys for rapid materials discovery Open
View article: The Effect of Stress on Laves Phase Precipitation in Creep Ruptured Grade 92 Ferritic Martensitic Steel Determined by an Accessible Volume Fraction and Number Density Quantification Method
The Effect of Stress on Laves Phase Precipitation in Creep Ruptured Grade 92 Ferritic Martensitic Steel Determined by an Accessible Volume Fraction and Number Density Quantification Method Open
View article: Microstructure and Mechanical Behavior of a Tic Nanoprecipitate Strengthened V Alloy
Microstructure and Mechanical Behavior of a Tic Nanoprecipitate Strengthened V Alloy Open
View article: Object kinetic Monte Carlo simulations on the difference between fission neutron and heavy ion irradiation induced void evolution in Fe-Cr alloys
Object kinetic Monte Carlo simulations on the difference between fission neutron and heavy ion irradiation induced void evolution in Fe-Cr alloys Open
Experimental results show significant difference between neutrons and ions irradiation of alloys, while the underlying reasons remain unclear. Herein, we performed object kinetic Monte Carlo (OKMC) simulations on void evolution in Fe-Cr al…
View article: Microstructure, electrical resistivity, and tensile properties of neutron-irradiated Cu–Cr–Nb–Zr
Microstructure, electrical resistivity, and tensile properties of neutron-irradiated Cu–Cr–Nb–Zr Open
High strength, high conductivity copper alloys that can resist creep at high temperatures are one of the primary candidates for efficient heat exchangers in fusion reactors. Cu–Cr–Nb–Zr (CCNZ) alloys, which were designed to improve the str…
View article: Simulations of radiation damage accumulation in Fe-9Cr under pulsed irradiation conditions representative of inertial fusion energy
Simulations of radiation damage accumulation in Fe-9Cr under pulsed irradiation conditions representative of inertial fusion energy Open
Structural materials for laser-based inertial fusion energy (IFE) reactor concepts are expected to operate under pulsed irradiation conditions, with cycles consisting of microsecond-long neutron bursts followed by inter-pulse periods of up…
View article: Anisotropic dislocation loop nucleation in ion-irradiated MgAl sub 2 O sub 4
Anisotropic dislocation loop nucleation in ion-irradiated MgAl sub 2 O sub 4 Open
Polycrystalline disks of stoichiometric magnesium aluminate spinel (MgAl{sub 2}O{sub 4}) were irradiated with 2 MeV Al{sup +} ions at 650{degrees}C and subsequently analyzed in cross-section using transmission electron microscopy (TEM). In…
View article: Application of Weak-Beam Dark-Field STEM for Dislocation Loop Analysis
Application of Weak-Beam Dark-Field STEM for Dislocation Loop Analysis Open
Nanoscale dislocation loops formed by irradiation can significantly contribute to both irradiation hardening and embrittlement of materials when subjected to extreme nuclear reactor environments. This study explores the application of weak…
View article: Understanding Formation of Irradiation-Induced Defects through 4D-STEM, Electron Tomography, and WBDF-STEM
Understanding Formation of Irradiation-Induced Defects through 4D-STEM, Electron Tomography, and WBDF-STEM Open
A major challenge in advancing nuclear materials for next-generation fission and proposed fusion reactors is to comprehensively understand the formation of irradiation-induced defects. Here it is essential to correlate the evolution of irr…
View article: Comparison of hardening and microstructures of ferritic/martensitic steels irradiated with fast neutrons and dual ions
Comparison of hardening and microstructures of ferritic/martensitic steels irradiated with fast neutrons and dual ions Open
View article: The role of stacking fault tetrahedra on void swelling in irradiated copper
The role of stacking fault tetrahedra on void swelling in irradiated copper Open
A long-standing and critical issue in the field of irradiated structural materials is that void swelling is significantly higher in face-centered cubic-structured (fcc) materials (1% dpa −1 ) as compared to that of body-centered cubic-stru…
View article: Microstructure and thermal stability of a structurally graded tungsten and reduced activation ferritic/martensitic steel joint
Microstructure and thermal stability of a structurally graded tungsten and reduced activation ferritic/martensitic steel joint Open
View article: Synchrotron based investigation of anisotropy and microstructure of wire arc additive manufactured Grade 91 steel
Synchrotron based investigation of anisotropy and microstructure of wire arc additive manufactured Grade 91 steel Open
View article: Ion Beam Roadmap and the Use of Ion Irradiation as a Surrogate for Neutron Irradiation
Ion Beam Roadmap and the Use of Ion Irradiation as a Surrogate for Neutron Irradiation Open
We will present a discussion of the use of Ion beam irradiation as a surrogate for neutron irradiation and the FY17 NSUF Ion Beam Roadmap.
View article: Post-irradiation examination of commercial tantalum alloys following neutron irradiation
Post-irradiation examination of commercial tantalum alloys following neutron irradiation Open
View article: Microstructure Evolution in Ultra-High Purity Fe-Cr Alloys Under Low-PKA Proton Irradiation
Microstructure Evolution in Ultra-High Purity Fe-Cr Alloys Under Low-PKA Proton Irradiation Open
View article: Evaluation of the Corrosion Kinetics of SiC with and without Mitigation Coatings in LWR Chemistries
Evaluation of the Corrosion Kinetics of SiC with and without Mitigation Coatings in LWR Chemistries Open
View article: Temperature and Dose Effects on Dislocation Loops in Self-Ion Irradiated High-Purity Iron
Temperature and Dose Effects on Dislocation Loops in Self-Ion Irradiated High-Purity Iron Open
View article: Simulations of Radiation Damage Accumulation in Fe-9cr Under Pulsed Irradiation Conditions Representative of Inertial Fusion Energy
Simulations of Radiation Damage Accumulation in Fe-9cr Under Pulsed Irradiation Conditions Representative of Inertial Fusion Energy Open
View article: Hot Hydrogen Testing of Mo30w Matrix Surrogate Cermets
Hot Hydrogen Testing of Mo30w Matrix Surrogate Cermets Open
View article: Defect-specific strength factors and superposition model for predicting strengthening of ion irradiated Fe18Cr alloy
Defect-specific strength factors and superposition model for predicting strengthening of ion irradiated Fe18Cr alloy Open
View article: Predicting displacement damage for ion irradiation: Origin of the overestimation of vacancy production in SRIM full-cascade calculations
Predicting displacement damage for ion irradiation: Origin of the overestimation of vacancy production in SRIM full-cascade calculations Open
View article: Evaluation of Tungsten—Steel Solid-State Bonding: Options and the Role of CALPHAD to Screen Diffusion Bonding Interlayers
Evaluation of Tungsten—Steel Solid-State Bonding: Options and the Role of CALPHAD to Screen Diffusion Bonding Interlayers Open
Critical aspects of innovative design in engineering disciplines like infrastructure, transportation, and medical applications require the joining of dissimilar materials. This study investigates the literature on solid-state bonding techn…
View article: Flash electropolishing of BCC Fe and Fe-based alloys
Flash electropolishing of BCC Fe and Fe-based alloys Open
View article: Application of a deep learning semantic segmentation model to helium bubbles and voids in nuclear materials
Application of a deep learning semantic segmentation model to helium bubbles and voids in nuclear materials Open
View article: Review of Recent Progress in Plasma-Facing Material Joints and Composites in the FRONTIER U.S.-Japan Collaboration
Review of Recent Progress in Plasma-Facing Material Joints and Composites in the FRONTIER U.S.-Japan Collaboration Open
The plasma-facing components (PFCs) of future fusion reactors will have intricate structures and require multiple materials because no one material can simultaneously satisfy all the requirements of the component. The dissimilar material j…
View article: A deep learning model for automatic analysis of cavities in irradiated materials
A deep learning model for automatic analysis of cavities in irradiated materials Open