Projects
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NSUF 24-4815: Dislocation-precipitate interaction under irradiation – in situ TEM nanomechanical testing during heavy ion irradiation
The Fukushima incident highlighted the urgent need for advanced cladding...
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瀏覽 NSUF 24-4815: Dislocation-precipitate interaction under irradiation – in situ TEM nanomechanical testing during heavy ion irradiation -
NSUF 24-4817: Investigating the evolution of M23C6 and MX-type precipitates in additively manufactured Grade 91 steel under high temperature simultaneous and sequential stress and irradiation
We propose conducting tests on an additively manufactured (AM) Grade 91 steel...
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瀏覽 NSUF 24-4817: Investigating the evolution of M23C6 and MX-type precipitates in additively manufactured Grade 91 steel under high temperature simultaneous and sequential stress and irradiation -
NSUF 24-4819: Phase Characterization of Neutron Irradiated Surveillance Reactor Pressure Vessel Welds
A nuclear power plant's reactor pressure vessel (RPV) is an essential...
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瀏覽 NSUF 24-4819: Phase Characterization of Neutron Irradiated Surveillance Reactor Pressure Vessel Welds -
NSUF 24-4820: In-Situ TEM Characterization of Ion-Irradiated U-10Mo Alloys at Sub-Eutectoid Temperatures
U-Mo alloys have been of interest to the nuclear energy community as an...
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瀏覽 NSUF 24-4820: In-Situ TEM Characterization of Ion-Irradiated U-10Mo Alloys at Sub-Eutectoid Temperatures -
NSUF 24-4829: High Resolution Studies of Uranium Mononitride/Zirconium Carbide Composites for Advanced Fuels Applications
This project is an investigation of ultra-high temperature intergranular...
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瀏覽 NSUF 24-4829: High Resolution Studies of Uranium Mononitride/Zirconium Carbide Composites for Advanced Fuels Applications -
NSUF 24-4838: The Role of Dislocation Cell Walls on Cavity Nucleation in Additively Manufactured 316H Steel
Operational conditions of Gen. IV concept nuclear reactors will place...
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瀏覽 NSUF 24-4838: The Role of Dislocation Cell Walls on Cavity Nucleation in Additively Manufactured 316H Steel -
NSUF 24-4841: Co-Location of Solute Clusters and Dislocations in Additively Manufactured 316L Stainless Steels
Additive manufacturing offers the possibility of geometries unrealizable...
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瀏覽 NSUF 24-4841: Co-Location of Solute Clusters and Dislocations in Additively Manufactured 316L Stainless Steels -
NSUF 24-4846: Irradiation performance of defective Uranium Mononitride: The role of impurities in the defect accumulation using in-situ TEM ion irradiation
UN is under consideration as an advanced nuclear fuel alternative to UO2....
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瀏覽 NSUF 24-4846: Irradiation performance of defective Uranium Mononitride: The role of impurities in the defect accumulation using in-situ TEM ion irradiation -
NSUF 24-4847: Post-Irradiation Analysis of U-Pu-Zr Fuel Incorporating Am and Np Actinides: Fuel-Cladding Interactions in EBR-II and Advanced Microscopic Examination
In pursuit of understanding the integration of minor actinides in metallic...
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瀏覽 NSUF 24-4847: Post-Irradiation Analysis of U-Pu-Zr Fuel Incorporating Am and Np Actinides: Fuel-Cladding Interactions in EBR-II and Advanced Microscopic Examination -
NSUF 24-4848: Advanced characterization of irradiated FAST rodlets using Transmission Electron Microscopy and Atom Probe Tomography
The Advanced Fuels Campaign (AFC) has recently completed the first phase of...
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瀏覽 NSUF 24-4848: Advanced characterization of irradiated FAST rodlets using Transmission Electron Microscopy and Atom Probe Tomography -
NSUF 24-4849: Radiation Tolerance of MX-Type Precipitates Revealed Through In-Situ Ion Irradiations
Nanoprecipitates play a key role in preventing material degradation during...
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瀏覽 NSUF 24-4849: Radiation Tolerance of MX-Type Precipitates Revealed Through In-Situ Ion Irradiations -
NSUF 24-4855: Fuel – Cladding Chemical Interaction of U10Zr Fuel and HT-9 Cladding Using in situ Heated TEM
The goal of this work is to use in situ heating to observe microstructure and...
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瀏覽 NSUF 24-4855: Fuel – Cladding Chemical Interaction of U10Zr Fuel and HT-9 Cladding Using in situ Heated TEM -
NSUF 24-4856: Development of an Experimental-Simulation Benchmarking Database for Irradiation-Enhanced Long Range Ordering in Ni-Cr-Mo alloys
Advanced nuclear reactor concepts require materials that can withstand...
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瀏覽 NSUF 24-4856: Development of an Experimental-Simulation Benchmarking Database for Irradiation-Enhanced Long Range Ordering in Ni-Cr-Mo alloys -
NSUF 24-4862: Evolution of Heterogeneous 316LSS Microstructures Under Neutron Irradiation
This project aims to quantify the impact of as-printed heterogeneity in laser...
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瀏覽 NSUF 24-4862: Evolution of Heterogeneous 316LSS Microstructures Under Neutron Irradiation -
NSUF 24-4867: Advanced characterization to identify phases formed of irradiated annular U-4Pd-13Zr fuel
The objective of the proposed work is to identify the local phases of...
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瀏覽 NSUF 24-4867: Advanced characterization to identify phases formed of irradiated annular U-4Pd-13Zr fuel -
NSUF 24-4874: Radiation behavior of grain boundary-decorated nanocrystalline high-entropy alloy
This work investigates the potential technological benefits of stabilized...
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瀏覽 NSUF 24-4874: Radiation behavior of grain boundary-decorated nanocrystalline high-entropy alloy -
NSUF 24-4875: Innovations in Austenitic Manganese Steels for Nuclear Applications: Insights from In-Situ TEM Irradiation Experiments at the IVEM Facility
Austenitic stainless steels, enriched with Nickel, are prevalent in the...
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瀏覽 NSUF 24-4875: Innovations in Austenitic Manganese Steels for Nuclear Applications: Insights from In-Situ TEM Irradiation Experiments at the IVEM Facility -
NSUF 24-4876: Understanding the effects of proton irradiation and air oxidation in Cr alloyed UB2 at high temperatures by synchrotron X‐ray scattering
The severe nuclear accident in Fukushima-Daichi in 2011 motivated the US...
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瀏覽 NSUF 24-4876: Understanding the effects of proton irradiation and air oxidation in Cr alloyed UB2 at high temperatures by synchrotron X‐ray scattering -
NSUF 24-4880: The effect of radiation temperature on H/He core-shell structures in nuclear structural materials
The objective of this project is to investigate (1) the ability of nuclear...
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瀏覽 NSUF 24-4880: The effect of radiation temperature on H/He core-shell structures in nuclear structural materials -
NSUF 24-4881: Irradiation of GaN HEMTs and SiC JFETs for Near Core Rad-hard Electronics
Developing radiation-hardened (rad-hard) electronics that can operate...
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瀏覽 NSUF 24-4881: Irradiation of GaN HEMTs and SiC JFETs for Near Core Rad-hard Electronics