Projects
-
NSUF 19-1774: Effect of Irradiation on Nuclear Graphite Microstructure in Relation to Oxidation in Oxygen Environments
One primary safety concern in Very High Temperature Reactors (VHTRs) is...
0 Datasets
View NSUF 19-1774: Effect of Irradiation on Nuclear Graphite Microstructure in Relation to Oxidation in Oxygen Environments -
NSUF 19-1778: Neutron powder diffraction and transmission in graphite to assess impact of microstructure on neutron thermalization
Several advanced nuclear reactor concepts have been proposed in the past few...
0 Datasets
View NSUF 19-1778: Neutron powder diffraction and transmission in graphite to assess impact of microstructure on neutron thermalization -
NSUF 19-1779: Understand the atomic positions of the metallic fission product in UCO Fuel Kernels and Determine the exact stoichiometry of UC, UO phase of Irradiated TRISO Fuel Particles by Using Titan Themis 200 with EELS characterization Capability
TRISO fuel is considered for multiple applications including high temperature...
0 Datasets
View NSUF 19-1779: Understand the atomic positions of the metallic fission product in UCO Fuel Kernels and Determine the exact stoichiometry of UC, UO phase of Irradiated TRISO Fuel Particles by Using Titan Themis 200 with EELS characterization Capability -
NSUF 19-1782: Scanning/Transmission Electron Microscopy Characterization of Irradiated Zr-1Nb-O During Thermal Treatments
The niobium, an alloying element in zirconium alloys, improves the radiation...
0 Datasets
View NSUF 19-1782: Scanning/Transmission Electron Microscopy Characterization of Irradiated Zr-1Nb-O During Thermal Treatments -
NSUF 19-1784: Irradiation and TEM Characterization of induced Defects in a-U and d-UZr2+x Crystals
U-Zr based metallic fuel is an advanced fuel type for fast reactors. However,...
0 Datasets
View NSUF 19-1784: Irradiation and TEM Characterization of induced Defects in a-U and d-UZr2+x Crystals -
NSUF 19-1785: Microstructural characterizations of in-core molten salt irradiated TRISO particles
As a part of Integrated Research Project of fluoride salt-cooled high-...
0 Datasets
View NSUF 19-1785: Microstructural characterizations of in-core molten salt irradiated TRISO particles -
NSUF 19-1789: Radiation Stability Study on Nuclear Waste Materials
Radiation damage and decay heat are significant issues for nuclear waste and...
0 Datasets
View NSUF 19-1789: Radiation Stability Study on Nuclear Waste Materials -
NSUF 19-1793: Elevated Temperature In-situ Scanning Electron Microscopy Microcantilever Testing of U3Si2
The PI has access to several different U3Si2 samples at the Fuels Research...
0 Datasets
View NSUF 19-1793: Elevated Temperature In-situ Scanning Electron Microscopy Microcantilever Testing of U3Si2 -
NSUF 19-1796: EPMA and TEM Characterization of a UO2 fuel pellet and cladding interaction layer
During operation of a nuclear power plant, a brittle complex oxide layer...
0 Datasets
View NSUF 19-1796: EPMA and TEM Characterization of a UO2 fuel pellet and cladding interaction layer -
NSUF 19-1799: Irradiation response and mechanical properties of Cr coated Zircaloy-4
As one accident tolerant fuel (ATF) concept, Cr was used to coat fuel...
0 Datasets
View NSUF 19-1799: Irradiation response and mechanical properties of Cr coated Zircaloy-4 -
NSUF 19-1802: Microstructure characterization of neutron-irradiated Fe-Cr-C model alloys
This project aims to investigate the irradiated microstructure of...
0 Datasets
View NSUF 19-1802: Microstructure characterization of neutron-irradiated Fe-Cr-C model alloys -
NSUF 19-1806: The impact of grain orientation on the nucleation of fission gas bubbles in U-Mo fuel
It has been postulated that fission gas bubble growth and nucleation is...
0 Datasets
View NSUF 19-1806: The impact of grain orientation on the nucleation of fission gas bubbles in U-Mo fuel -
NSUF 19-1809: In-situ TEM Study of the Irradiation Response of Pre-deformed Alloy 709
The project aims to investigate the irradiation response of pre-deformed...
0 Datasets
View NSUF 19-1809: In-situ TEM Study of the Irradiation Response of Pre-deformed Alloy 709 -
NSUF 19-1810: Microstructural characterization of in-situ ion irradiated SiC layer of TRISO fuel
The objective of this work is to get deeper understanding of the Ag and He...
0 Datasets
View NSUF 19-1810: Microstructural characterization of in-situ ion irradiated SiC layer of TRISO fuel -
NSUF 19-1814: TEM Characterization of Neutron Irradiated Nd2Zr2O7 and Its Thermal Recovery Behavior
The pyrochlore ceramic Nd2Zr2O7 has been found to be radiation resistant,...
0 Datasets
View NSUF 19-1814: TEM Characterization of Neutron Irradiated Nd2Zr2O7 and Its Thermal Recovery Behavior -
NSUF 19-2822: Examining microstructural evolution of HT9 under neutron and ion irradiations from 370 °C to 570 °C
Secondary phase precipitates (SPP) play an important role of controlling...
0 Datasets
View NSUF 19-2822: Examining microstructural evolution of HT9 under neutron and ion irradiations from 370 °C to 570 °C -
NSUF 19-2828: Irradiation of Nb-93 targets for ASTM International Inter-Laboratory Study of E1297, “Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium”.
Irradiation is requested in support of an ASTM International Inter-Laboratory...
0 Datasets
View NSUF 19-2828: Irradiation of Nb-93 targets for ASTM International Inter-Laboratory Study of E1297, “Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium”. -
NSUF 19-2832: Performance and Structural Damage Analysis of Chalcogenide Glass Phase Change Temperature Sensors Under Ion Irradiation
The goal of this project is to test the performance of the novel chalcogenide...
0 Datasets
View NSUF 19-2832: Performance and Structural Damage Analysis of Chalcogenide Glass Phase Change Temperature Sensors Under Ion Irradiation -
NSUF 19-2833: The influence of proton irradiation damage on the corrosion of Hastelloy N exposed to FliNaK molten salt
A complete understanding of the evolution of Hastelloy N under adverse...
0 Datasets
View NSUF 19-2833: The influence of proton irradiation damage on the corrosion of Hastelloy N exposed to FliNaK molten salt -
NSUF 19-2840: Impact of neutron damage and microstructure changes on hydrogen retention in nuclear graphite
The proposed experiments allow for further investigation of nuclear graphite...
0 Datasets
View NSUF 19-2840: Impact of neutron damage and microstructure changes on hydrogen retention in nuclear graphite