Projects
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NSUF 19-1722: In situ observation of helium out-gassing mechanism in percolating 1D/2D nanodispersoids for advanced reactor structural material and fuel cladding
The objective of this project is to reveal the underlying mechanism and...
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NSUF 19-1722: In situ observation of helium out-gassing mechanism in percolating 1D/2D nanodispersoids for advanced reactor structural material and fuel cladding ansehen -
NSUF 19-1723: Influence of Grain Boundary RIS on Dislocation Mobility in Irradiated Steels
The objective of this project is to determine the influence of grain boundary...
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NSUF 19-1723: Influence of Grain Boundary RIS on Dislocation Mobility in Irradiated Steels ansehen -
NSUF 19-1730: The microstructure characterization of 21Cr32Ni model austenitic alloy irradiated at BOR60 reactor
Understanding the irradiation behavior of the materials at high dose is...
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NSUF 19-1730: The microstructure characterization of 21Cr32Ni model austenitic alloy irradiated at BOR60 reactor ansehen -
NSUF 19-1731: Atom Probe Tomography (APT) Investigation of Radiation Stability of Oxide Nanoclusters in Oxide Dispersion Strengthened (ODS) Steel Manufactured by the Cold Spray Process
The goal of the proposed rapid turnaround experiment (RTE) led by the...
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NSUF 19-1731: Atom Probe Tomography (APT) Investigation of Radiation Stability of Oxide Nanoclusters in Oxide Dispersion Strengthened (ODS) Steel Manufactured by the Cold Spray Process ansehen -
NSUF 19-1732: Radiation Tolerance of Nanoporous Gadolinium Titanate
The method that will be employed to study the radiation tolerance of the...
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NSUF 19-1732: Radiation Tolerance of Nanoporous Gadolinium Titanate ansehen -
NSUF 19-1734: Atom Probe Tomography Investigation on the Precipitation of Neutron-Irradiated Alloy 800H/800H-TMP
The goal of the project is to investigate the chemical composition of γ’...
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NSUF 19-1734: Atom Probe Tomography Investigation on the Precipitation of Neutron-Irradiated Alloy 800H/800H-TMP ansehen -
NSUF 19-1741: APT Study of Zr-(Mo, Nb, Ta) Diffusion for Designing the Diffusion Barrier Interlayer of Cr Coated Zircaloy Accident-Tolerant Fuels
One of the promising accident-tolerant fuel (ATF) claddings consists of...
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NSUF 19-1741: APT Study of Zr-(Mo, Nb, Ta) Diffusion for Designing the Diffusion Barrier Interlayer of Cr Coated Zircaloy Accident-Tolerant Fuels ansehen -
NSUF 19-1742: Investigation of the mechanism behind irradiation-decelerated corrosion of Ni-20Cr in molten fluoride salt
Motivation: The degradation of materials in molten salt reactors (MSRs) must...
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NSUF 19-1742: Investigation of the mechanism behind irradiation-decelerated corrosion of Ni-20Cr in molten fluoride salt ansehen -
NSUF 19-1743: High-burnup U-Mo pore morphology analysis as a function of fission density and rate
Fission product swelling of the nuclear fuel causing closure of the coolant...
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NSUF 19-1743: High-burnup U-Mo pore morphology analysis as a function of fission density and rate ansehen -
NSUF 19-1744: Correlation of In-situ TEM Characterization and Ex-situ Microchemistry Analysis of Radiation Damage in Metal/Oxide Multilayers
Cross-sectional TEM specimens of Fe/Fe2O3 and (Fe-18%Ni)/Fe2O3 multilayers...
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NSUF 19-1744: Correlation of In-situ TEM Characterization and Ex-situ Microchemistry Analysis of Radiation Damage in Metal/Oxide Multilayers ansehen -
NSUF 19-1747: Nano-precipitate Stability and a'-Precipitation in ODS and Wrought FeCrAl Alloys
The primary objectives of this project are (1) to track the stability of ODS...
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NSUF 19-1747: Nano-precipitate Stability and a'-Precipitation in ODS and Wrought FeCrAl Alloys ansehen -
NSUF 19-1749: In situ TEM observation of microstructural evolution of sodium-ion battery materials under ion irradiation
Methods: This proposal is to use the Intermediate Voltage Electron Microscopy...
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NSUF 19-1749: In situ TEM observation of microstructural evolution of sodium-ion battery materials under ion irradiation ansehen -
NSUF 19-1750: In-situ investigation of irradiation damage on non-volatile memory
The objective of the proposed project is to evaluate the effectiveness of...
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NSUF 19-1750: In-situ investigation of irradiation damage on non-volatile memory ansehen -
NSUF 19-1752: A study using stoichiometry to control structural disorder and subsequent radiation tolerance of rare-earth based zirconates and titanates
NSUF RTE Argonne National Labs IVEM – Tandem facility. March 2019...
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NSUF 19-1752: A study using stoichiometry to control structural disorder and subsequent radiation tolerance of rare-earth based zirconates and titanates ansehen -
NSUF 19-1757: Role of Irradiation Damage Cascade Descriptors on ODS and Model ODS Nanocluster Evolution
The objective of this study is to understand the role of irradiation damage...
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NSUF 19-1757: Role of Irradiation Damage Cascade Descriptors on ODS and Model ODS Nanocluster Evolution ansehen -
NSUF 19-1761: Alleviating irradiation-induced precipitation in a Fe-21Cr-5Al alloy via nanostructuring.
Due to their high strength and corrosion resistance in high temperature steam...
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NSUF 19-1761: Alleviating irradiation-induced precipitation in a Fe-21Cr-5Al alloy via nanostructuring. ansehen -
NSUF 19-1765: Temperature shift evaluation for G-phase nanocluster evolution in ferritic/martensitic alloys
The objective of this project is to validate the temperature shift...
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NSUF 19-1765: Temperature shift evaluation for G-phase nanocluster evolution in ferritic/martensitic alloys ansehen -
NSUF 19-1767: Density Functional Theory Study of Defects, Solubility of Fission Products and Pu, and Phase Separation in U3Si2 Nuclear Fuel
In recent year, there has been considerable interest in the possibility of...
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NSUF 19-1767: Density Functional Theory Study of Defects, Solubility of Fission Products and Pu, and Phase Separation in U3Si2 Nuclear Fuel ansehen -
NSUF 19-1770: In-situ nanomechanical characterization of neutron-irradiated HT-9 steel
Structural materials for the Generation IV (Gen IV) reactors will be exposed...
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NSUF 19-1770: In-situ nanomechanical characterization of neutron-irradiated HT-9 steel ansehen -
NSUF 19-1773: BET and TEM characterization of nuclear graphite irradiated at temperatures below 230°C
Graphite is the moderator material of some Generation IV reactors concepts...
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NSUF 19-1773: BET and TEM characterization of nuclear graphite irradiated at temperatures below 230°C ansehen