Projects
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NSUF 23-4508: Evolution of Dispersoid in Austenitic Fe-Cr-Ni Oxide Dispersion Strengthened Alloy in Ion Irradiation
This project is proposed by a collaborative team established by Boise State...
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Разглеждане на NSUF 23-4508: Evolution of Dispersoid in Austenitic Fe-Cr-Ni Oxide Dispersion Strengthened Alloy in Ion Irradiation -
NSUF 23-4513: Measurement of 254-eV Nuclear Recoils in Germanium
Nuclear recoils within a high-purity germanium detector (HPGe) will be...
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Разглеждане на NSUF 23-4513: Measurement of 254-eV Nuclear Recoils in Germanium -
NSUF 23-4519: 4D-STEM strain mapping of radiation induced defects
To characterize irradiation-induced defects, TEM is often the go-to...
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Разглеждане на NSUF 23-4519: 4D-STEM strain mapping of radiation induced defects -
NSUF 23-4521: High-Resolution Characterization of Neutron-Irradiated Cr-Fe-Mn-Ni-(Al,Ti) High-Entropy Alloys
Many advanced reactor concepts demand pushing in-core materials to higher...
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Разглеждане на NSUF 23-4521: High-Resolution Characterization of Neutron-Irradiated Cr-Fe-Mn-Ni-(Al,Ti) High-Entropy Alloys -
NSUF 23-4529: 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 23-4529: Ion Irradiation tolerance of Gadolinium titanates / zirconates as candidates for waste form matrices -
NSUF 23-4530: 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 23-4530: Irradiation of Radiation-hard GaN Transistors for Mixed Gamma and Neutron Field Under High Temperature -
NSUF 23-4534: Mesoscale irradiation of HT-9
This proposal aims to bridge the gab between neutrons and ion beam...
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Разглеждане на NSUF 23-4534: Mesoscale irradiation of HT-9 -
NSUF 23-4537: 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 23-4537: Compositional and Defect Analysis of the FCCI in high burnup UO2 -
NSUF 23-4546: 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 23-4546: Deconvoluting Void and Bubble Effects on Deformation-Induced Martensitic Transformations in Austenitic Stainless Steel Using 4D STEM Strain Mapping -
NSUF 23-4552: 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 23-4552: Elucidating the Effect of Radiation-Induced Defect Accumulation on Swelling in UN using in-situ TEM Irradiation -
NSUF 23-4554: 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 23-4554: Microstructural Origin of Irradiation Hardening and Embrittlement in Irradiated Second Generation FeCrAl Alloys -
NSUF 23-4565: 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 23-4565: Investigation of Simultaneous Irradiation and Creep Behavior of Cr Thin Films -
NSUF 23-4566: 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 23-4566: The effect of irradiation on the densities of chloride-bearing molten salts -
NSUF 23-4567: 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 23-4567: Dual Ion Beam Irradiation and Post-Irradiation-Examinations of Alumina Coating on Stainless Steel -
NSUF 23-4571: Investigating the effect of solute segregation on defect recovery kinetics in reactor-irradiated Ti
The degradation of material properties with irradiation depends intimately on...
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Разглеждане на NSUF 23-4571: Investigating the effect of solute segregation on defect recovery kinetics in reactor-irradiated Ti -
NSUF 23-4573: 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 23-4573: Effect of neutron radiation on density and mechanical properties of white cement paste -
NSUF 23-4581: 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 23-4581: In Situ Mechanical Testing of Irradiated Zr Single Crystals -
NSUF 23-4584: 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 23-4584: Isotope density mapping using Energy Resolved Neutron Resonance Imaging of a High Burnup UO2 Fuel Fragment -
NSUF 23-4587: 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 23-4587: Spatially resolved thermal conductivity measurement of medium burnup MOX fuel -
NSUF 23-4590: 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 23-4590: Assessment of Local Thermal Conductivity and Microstructure of Irradiated U-20 wt% Pu-10 wt% Zr alloy