Projects
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NSUF 23-1854: Ion Irradiation tolerance of Gadolinium titanates / zirconates as candidates for waste form matrices
NSUF RTE Argonne National Labs IVEM – Tandem facility. October 2022...
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Разглеждане на NSUF 23-1854: Ion Irradiation tolerance of Gadolinium titanates / zirconates as candidates for waste form matrices -
NSUF 23-1855: Irradiation of Radiation-hard GaN Transistors for Mixed Gamma and Neutron Field Under High Temperature
By developing radiation-hardened electronics that can operate reliably within...
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Разглеждане на NSUF 23-1855: Irradiation of Radiation-hard GaN Transistors for Mixed Gamma and Neutron Field Under High Temperature -
NSUF 23-1856: Mesoscale irradiation of HT-9
This proposal aims to bridge the gab between neutrons and ion beam...
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Разглеждане на NSUF 23-1856: Mesoscale irradiation of HT-9 -
NSUF 23-1857: Compositional and Defect Analysis of the FCCI in high burnup UO2
The main objective of the proposed research is to conduct an examination of...
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Разглеждане на NSUF 23-1857: Compositional and Defect Analysis of the FCCI in high burnup UO2 -
NSUF 23-1862: Deconvoluting Void and Bubble Effects on Deformation-Induced Martensitic Transformations in Austenitic Stainless Steel Using 4D STEM Strain Mapping
The objective of this project is to deconvolute the effects of voids from...
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Разглеждане на NSUF 23-1862: Deconvoluting Void and Bubble Effects on Deformation-Induced Martensitic Transformations in Austenitic Stainless Steel Using 4D STEM Strain Mapping -
NSUF 23-1868: Elucidating the Effect of Radiation-Induced Defect Accumulation on Swelling in UN using in-situ TEM Irradiation
Uranium mononitride (UN) is under consideration as an advanced nuclear fuel...
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Разглеждане на NSUF 23-1868: Elucidating the Effect of Radiation-Induced Defect Accumulation on Swelling in UN using in-situ TEM Irradiation -
NSUF 23-1870: Microstructural Origin of Irradiation Hardening and Embrittlement in Irradiated Second Generation FeCrAl Alloys
FeCrAl alloys are promising candidate materials for the accident tolerant...
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Разглеждане на NSUF 23-1870: Microstructural Origin of Irradiation Hardening and Embrittlement in Irradiated Second Generation FeCrAl Alloys -
NSUF 23-1877: Investigation of Simultaneous Irradiation and Creep Behavior of Cr Thin Films
In this proposal, we aim to investigate the simultaneous irradiation and...
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Разглеждане на NSUF 23-1877: Investigation of Simultaneous Irradiation and Creep Behavior of Cr Thin Films -
NSUF 23-1878: The effect of irradiation on the densities of chloride-bearing molten salts
The project will investigate the effect of neutron irradiation in chloride-...
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Разглеждане на NSUF 23-1878: The effect of irradiation on the densities of chloride-bearing molten salts -
NSUF 23-1879: Dual Ion Beam Irradiation and Post-Irradiation-Examinations of Alumina Coating on Stainless Steel
Development of high-performance nuclear components is a crucial objective to...
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Разглеждане на NSUF 23-1879: Dual Ion Beam Irradiation and Post-Irradiation-Examinations of Alumina Coating on Stainless Steel -
NSUF 23-1884: Effect of neutron radiation on density and mechanical properties of white cement paste
The radiation induced volumetric expansion of minerals present in aggregates...
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Разглеждане на NSUF 23-1884: Effect of neutron radiation on density and mechanical properties of white cement paste -
NSUF 23-1891: In Situ Mechanical Testing of Irradiated Zr Single Crystals
Our effort is currently focused on the use of zirconium to due to its hcp...
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Разглеждане на NSUF 23-1891: In Situ Mechanical Testing of Irradiated Zr Single Crystals -
NSUF 23-1893: Isotope density mapping using Energy Resolved Neutron Resonance Imaging of a High Burnup UO2 Fuel Fragment
This project will characterize high burnup UO2 fuel from a light water...
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Разглеждане на NSUF 23-1893: Isotope density mapping using Energy Resolved Neutron Resonance Imaging of a High Burnup UO2 Fuel Fragment -
NSUF 23-1896: Spatially resolved thermal conductivity measurement of medium burnup MOX fuel
This project aims to measure the thermal conductivity profile of Sodium Fast...
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Разглеждане на NSUF 23-1896: Spatially resolved thermal conductivity measurement of medium burnup MOX fuel -
NSUF 23-1898: Assessment of Local Thermal Conductivity and Microstructure of Irradiated U-20 wt% Pu-10 wt% Zr alloy
The objective of this work is to correlate, for the first time,...
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Разглеждане на NSUF 23-1898: Assessment of Local Thermal Conductivity and Microstructure of Irradiated U-20 wt% Pu-10 wt% Zr alloy -
NSUF 23-1901: Serial Sectioning to Quantify Fission Induced Microstructural Evolution in U-Zr Alloys
This work will use scanning electron microscopy (SEM) and electron dispersive...
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Разглеждане на NSUF 23-1901: Serial Sectioning to Quantify Fission Induced Microstructural Evolution in U-Zr Alloys -
NSUF 23-1905: Electron tomography study of dislocation loops and precipitates in ion irradiated Fe-Cr alloys
This proposal aims to examine the 3D configuration of petal-shaped...
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Разглеждане на NSUF 23-1905: Electron tomography study of dislocation loops and precipitates in ion irradiated Fe-Cr alloys -
NSUF 23-1908: Microstructural characterization of neutron irradiated C-C composites
In recent years the nuclear industry has considered C-C composites a...
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Разглеждане на NSUF 23-1908: Microstructural characterization of neutron irradiated C-C composites -
NSUF 23-1910: Neutron Irradiation of Updated In-Pile Steady State, Extreme Temperature Experiment (INSET)
Material and sensor characterization at temperatures up to and exceeding...
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Разглеждане на NSUF 23-1910: Neutron Irradiation of Updated In-Pile Steady State, Extreme Temperature Experiment (INSET) -
NSUF 23-1913: Neutron Irradiation of a radiation resistant digitizer at PULSTAR
The goal of this work is to elucidate critical points of failure of the...
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Разглеждане на NSUF 23-1913: Neutron Irradiation of a radiation resistant digitizer at PULSTAR