Projects
-
NSUF 23-1837: 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...
0 Datasets
View NSUF 23-1837: Evolution of Dispersoid in Austenitic Fe-Cr-Ni Oxide Dispersion Strengthened Alloy in Ion Irradiation -
NSUF 23-1840: Measurement of 254-eV Nuclear Recoils in Germanium
Nuclear recoils within a high-purity germanium detector (HPGe) will be...
0 Datasets
View NSUF 23-1840: Measurement of 254-eV Nuclear Recoils in Germanium -
NSUF 23-1845: 4D-STEM strain mapping of radiation induced defects
To characterize irradiation-induced defects, TEM is often the go-to...
0 Datasets
View NSUF 23-1845: 4D-STEM strain mapping of radiation induced defects -
NSUF 23-1847: 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...
0 Datasets
View NSUF 23-1847: High-Resolution Characterization of Neutron-Irradiated Cr-Fe-Mn-Ni-(Al,Ti) High-Entropy Alloys -
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...
0 Datasets
View 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...
0 Datasets
View 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...
0 Datasets
View 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...
0 Datasets
View 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...
0 Datasets
View 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...
0 Datasets
View 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...
0 Datasets
View 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...
0 Datasets
View 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-...
0 Datasets
View 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...
0 Datasets
View 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...
0 Datasets
View 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...
0 Datasets
View 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...
0 Datasets
View 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...
0 Datasets
View 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,...
0 Datasets
View 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...
0 Datasets
View NSUF 23-1901: Serial Sectioning to Quantify Fission Induced Microstructural Evolution in U-Zr Alloys