Projects
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NSUF 21-4331: Imaging of Irradiation Effects in Tantalum Alloys for Fast-Spectrum Self-Powered Neutron Detectors
Four samples of ASTAR-811C tantalum alloy and three samples of T-111 tantalum...
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瀏覽 NSUF 21-4331: Imaging of Irradiation Effects in Tantalum Alloys for Fast-Spectrum Self-Powered Neutron Detectors -
NSUF 21-4345: A first Investigation in Lanthanide-induced Grain Boundary Embrittlement in HT9 Cladding via In-situ Micro-tensile Testing
Fuel cladding chemical interaction (FCCI) between HT9 cladding and UZr based...
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瀏覽 NSUF 21-4345: A first Investigation in Lanthanide-induced Grain Boundary Embrittlement in HT9 Cladding via In-situ Micro-tensile Testing -
NSUF 21-4346: Mechanistic Insight Through TEM Characterization of Intergranular Irradiation-Assisted Stress Corrosion Crack Tips in As-Irradiated vs. Post-Irradiation Annealed Specimens
Light water reactor neutron irradiation causes radiation-induced defects...
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瀏覽 NSUF 21-4346: Mechanistic Insight Through TEM Characterization of Intergranular Irradiation-Assisted Stress Corrosion Crack Tips in As-Irradiated vs. Post-Irradiation Annealed Specimens -
NSUF 21-4350: Correlative TEM and APT approach to elucidate hydride morphology and behavior in ex-service pressure tube material
Through this RTE, we propose to examine ex-service hydrides in Zr-2.5Nb...
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瀏覽 NSUF 21-4350: Correlative TEM and APT approach to elucidate hydride morphology and behavior in ex-service pressure tube material -
NSUF 21-4351: Effect of neutron radiation on density and mechanical properties of concrete aggregates
The radiation induced volumetric expansion of minerals present in aggregates...
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瀏覽 NSUF 21-4351: Effect of neutron radiation on density and mechanical properties of concrete aggregates -
NSUF 21-4352: Ion Irradiation and examination of 304 Stainless Steel and 304 ODS Steel Additively Manufactured via Selective Laser Melting
Oxide dispersion strengthened (ODS) alloys are promising candidates for...
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瀏覽 NSUF 21-4352: Ion Irradiation and examination of 304 Stainless Steel and 304 ODS Steel Additively Manufactured via Selective Laser Melting -
NSUF 21-4357: Investigation of Degradation Mechanisms of Cr coated Zirconium alloy cladding in Reactive Initiate Accidents (RIA)
Researchers will investigate the thermal, mechanical, and irradiation...
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瀏覽 NSUF 21-4357: Investigation of Degradation Mechanisms of Cr coated Zirconium alloy cladding in Reactive Initiate Accidents (RIA) -
NSUF 21-4358: Machine Learning on High-Throughput Databases of Irradiation Response and Corrosion Properties of Selected Compositionally Complex Alloys for Structural Nuclear Materials
Researchers will integrate high-throughput synthesis, irradiation, and...
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瀏覽 NSUF 21-4358: Machine Learning on High-Throughput Databases of Irradiation Response and Corrosion Properties of Selected Compositionally Complex Alloys for Structural Nuclear Materials -
NSUF 21-4359: Improving Lifetime Prediction of Electrical Cables in Containment
Cable degradation accelerates late in the cable's lifetime curve but this...
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瀏覽 NSUF 21-4359: Improving Lifetime Prediction of Electrical Cables in Containment -
NSUF 21-4360: Effect of neutron irradiation on microstructure and mechanical properties of nanocrystalline nickel
Researchers will conduct post irradiation examination (PIE) of...
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瀏覽 NSUF 21-4360: Effect of neutron irradiation on microstructure and mechanical properties of nanocrystalline nickel -
NSUF 21-4361: X-ray diffraction tomography analysis of SiC composite tubes neutron-irradiated with a radial high heat flux
Researchers will conduct x-ray diffraction computed tomography analysis at...
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瀏覽 NSUF 21-4361: X-ray diffraction tomography analysis of SiC composite tubes neutron-irradiated with a radial high heat flux -
NSUF 21-4362: Synergy of radiation damage with corrosion processes through a separate effect investigation approach
Researchers will investigate the synergy of radiation damage with corrosion...
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瀏覽 NSUF 21-4362: Synergy of radiation damage with corrosion processes through a separate effect investigation approach -
NSUF 21-4363: Demonstration of Self Powered Neutron Detectors Performance and Reliability
Researchers will demonstrate operation of domestically produced self-powered...
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瀏覽 NSUF 21-4363: Demonstration of Self Powered Neutron Detectors Performance and Reliability -
NSUF 21-4364: Irradiation of Sensors and Adhesive Couplants for Application in LWR Primary Loop Piping and Components
Researchers plan to attach ultrasonic transducers to substrates using various...
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瀏覽 NSUF 21-4364: Irradiation of Sensors and Adhesive Couplants for Application in LWR Primary Loop Piping and Components -
NSUF 21-4366: Assessment of Irradiated Microstructure and Mechanical Properties of FeCrAl Alloy Fabrication Routes
The objective of this proposal is to determine how the FeCrAl alloy...
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瀏覽 NSUF 21-4366: Assessment of Irradiated Microstructure and Mechanical Properties of FeCrAl Alloy Fabrication Routes -
NSUF 21-4367: Deployment and In-Reactor Test of an Instrument for Real-Time Monitoring Thermal Conductivity Evolution of Nuclear Fuels
The objective of this proposed project is to deploy a recently developed...
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瀏覽 NSUF 21-4367: Deployment and In-Reactor Test of an Instrument for Real-Time Monitoring Thermal Conductivity Evolution of Nuclear Fuels -
NSUF 21-4368: Understanding irradiation behaviors of ultrawide bandgap Ga2O3 high temperature sensor materials for advanced nuclear reactor systems
The project will focus on a systematic study of irradiation effects on...
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瀏覽 NSUF 21-4368: Understanding irradiation behaviors of ultrawide bandgap Ga2O3 high temperature sensor materials for advanced nuclear reactor systems -
NSUF 21-BOR60: High Fidelity Ion Beam Simulation of High Dose Neutron Irradiation
The objective of this proposal is to demonstrate the capability to predict...
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瀏覽 NSUF 21-BOR60: High Fidelity Ion Beam Simulation of High Dose Neutron Irradiation -
NSUF 21-CINR-24327: Effect of neutron irradiation on friction stir welded Ni-based ODS MA754 alloy
Researchers will study the effect of neutron irradiation and friction stir...
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瀏覽 NSUF 21-CINR-24327: Effect of neutron irradiation on friction stir welded Ni-based ODS MA754 alloy -
NSUF 21-TRISO: Unirradiated TRISO Fuel
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瀏覽 NSUF 21-TRISO: Unirradiated TRISO Fuel