Projects
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NSUF 23-4745: In-Situ Irradiation and RF Characterization of Langasite-Based Surface Acoustic Wave Sensors for Advanced Nuclear Reactor Applications
Currently there is a significant need for harsh environment sensors, sensor...
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瀏覽 NSUF 23-4745: In-Situ Irradiation and RF Characterization of Langasite-Based Surface Acoustic Wave Sensors for Advanced Nuclear Reactor Applications -
NSUF 23-4747: Characterization of Manganese-Nickel Rich Precipitates and Their Interaction with Dislocations in Irradiated Reactor Pressure Vessel Steels
Major concerns for light water reactor life extensions involve neutron...
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瀏覽 NSUF 23-4747: Characterization of Manganese-Nickel Rich Precipitates and Their Interaction with Dislocations in Irradiated Reactor Pressure Vessel Steels -
NSUF 23-4750: Time-Resolved Neutron Damage Characterization using In Situ Positron Annihilation Spectroscopy
The main objective of this experiment is to develop a novel positron...
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瀏覽 NSUF 23-4750: Time-Resolved Neutron Damage Characterization using In Situ Positron Annihilation Spectroscopy -
NSUF 23-4751: Determining Mechanical Properties of the Phases Formed of Irradiated U-19Pu-10Zr
The objective of the proposed work is to measure the local mechanical...
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瀏覽 NSUF 23-4751: Determining Mechanical Properties of the Phases Formed of Irradiated U-19Pu-10Zr -
NSUF 23-4753: Characterization of fluff region in a EBR-II metallic fuel pin
This proposal aims at investigating axial swelling behavior in metallic fuels...
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瀏覽 NSUF 23-4753: Characterization of fluff region in a EBR-II metallic fuel pin -
NSUF 23-4754: Characterization of the Total-Dose Effect on State-of-the-Art Static Random-Access Memory
The key objective of this proposal is to evaluate the total-ionizing-dose...
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瀏覽 NSUF 23-4754: Characterization of the Total-Dose Effect on State-of-the-Art Static Random-Access Memory -
NSUF 23-4756: Understanding the role of nanostructuring in enhancing phase stability of 304 austenitic steel during irradiation via in-situ ion irradiation in transmission electron microscope
The proposed project will involve in-situ ion irradiation of coarse-grained...
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瀏覽 NSUF 23-4756: Understanding the role of nanostructuring in enhancing phase stability of 304 austenitic steel during irradiation via in-situ ion irradiation in transmission electron microscope -
NSUF 23-4764: Probing Interface Metastability as a Response to Radiation in Compositionally Complex Alloys
This project aims to understand metastability in complex alloys to tailor...
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瀏覽 NSUF 23-4764: Probing Interface Metastability as a Response to Radiation in Compositionally Complex Alloys -
NSUF 23-4765: Ion Irradiation and Post Characterization on Additively Manufactured High Entropy Alloys for Nuclear Applications
Structural materials for advanced nuclear reactor designs will be required to...
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瀏覽 NSUF 23-4765: Ion Irradiation and Post Characterization on Additively Manufactured High Entropy Alloys for Nuclear Applications -
NSUF 23-4766: Proton Irradiation of High Entropy Carbide Ceramics
The objective of this RTE project is to use proton irradiation experiments at...
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瀏覽 NSUF 23-4766: Proton Irradiation of High Entropy Carbide Ceramics -
NSUF 23-4768: Atom Probe Tomography and Transmission Electron Microscopy of Neutron-Irradiated Nanocrystalline Compositionally Complex Alloys
Despite interest in CCAs for nuclear applications, experimental data on...
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瀏覽 NSUF 23-4768: Atom Probe Tomography and Transmission Electron Microscopy of Neutron-Irradiated Nanocrystalline Compositionally Complex Alloys -
NSUF 23-4769: Probing the Chemical composition and Charge Status of Secondary Phases and Precipitates in High Burnup Metallic Fuel using Nano-SIMS and TEM-EELS
In this project, the elemental and isotopic data collected with the nano SIMS...
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瀏覽 NSUF 23-4769: Probing the Chemical composition and Charge Status of Secondary Phases and Precipitates in High Burnup Metallic Fuel using Nano-SIMS and TEM-EELS -
NSUF 23-4771: In situ irradiation of spent nuclear fuels
Nuclear fuel undergoes significant microstructural and chemical evolution...
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瀏覽 NSUF 23-4771: In situ irradiation of spent nuclear fuels -
NSUF 23-4774: Quantification of local burnup in irradiated U-10Zr metallic fuel using Atom Probe Tomography
The objective of this study is to quantify the radial distribution of local...
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瀏覽 NSUF 23-4774: Quantification of local burnup in irradiated U-10Zr metallic fuel using Atom Probe Tomography -
NSUF 23-4777: Elucidating Dislocation Loop Formation in Hot-extruded U-10Zr Alloy Under Irradiation
U-10Zr is currently being considered as fuel for several nuclear reactors...
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瀏覽 NSUF 23-4777: Elucidating Dislocation Loop Formation in Hot-extruded U-10Zr Alloy Under Irradiation -
NSUF 23-4778: Preliminary testing of additively manufactured UO2
Unlike the printing of metallic alloys, 3D printing of ceramics has proven to...
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瀏覽 NSUF 23-4778: Preliminary testing of additively manufactured UO2 -
NSUF 23-4780: Microstructural Defect Induced Thermal Conductivity Reduction in Uranium Nitride and Thorium Nitride
We propose to investigate thermal conductivity variation of uranium nitride...
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瀏覽 NSUF 23-4780: Microstructural Defect Induced Thermal Conductivity Reduction in Uranium Nitride and Thorium Nitride -
NSUF 23-KJRR: KJRR Fuel Plates
The Korean Atomic Energy Research Institute (KAERI) initiated the KJRR...
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瀏覽 NSUF 23-KJRR: KJRR Fuel Plates -
NSUF 24-4797: An evaluation of effects of ion irradiation on crystal, mechanical, and microstructural properties of Alloy 709
Advanced manufacturing of structural materials such as Alloy 709 for Gen IV...
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瀏覽 NSUF 24-4797: An evaluation of effects of ion irradiation on crystal, mechanical, and microstructural properties of Alloy 709 -
NSUF 24-4798: Reliability Assessment of Irradiated Integrated Silicon Carbide Pressure/Temperature Sensors for Lunar Fission Surface Power Reactor
NASA and DOE are developing a technology demonstration of a 40 kWe Lunar...
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瀏覽 NSUF 24-4798: Reliability Assessment of Irradiated Integrated Silicon Carbide Pressure/Temperature Sensors for Lunar Fission Surface Power Reactor