Projects
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NSUF 19-2890: Alumina-stabilized coatings under irradiations: towards future generation nuclear systems
Next generation nuclear power plants are meant to outperform current ones in...
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Разглеждане на NSUF 19-2890: Alumina-stabilized coatings under irradiations: towards future generation nuclear systems -
NSUF 19-2893: Understand the Fission Products Behavior in UCO Fuel Kernels of safety tested AGR2 TRISO Fuel Particles by Using Titan Themis 200 with ChemiSTEM Capability
TRISO fuel is considered for multiple applications including high temperature...
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Разглеждане на NSUF 19-2893: Understand the Fission Products Behavior in UCO Fuel Kernels of safety tested AGR2 TRISO Fuel Particles by Using Titan Themis 200 with ChemiSTEM Capability -
NSUF 19-2895: Predict the mechanical behavior of irradiated cast stainless steels based on the microstructures and measured properties from nanoindentation
The work is planned to systemically characterize the neutron irradiated CF3...
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Разглеждане на NSUF 19-2895: Predict the mechanical behavior of irradiated cast stainless steels based on the microstructures and measured properties from nanoindentation -
NSUF 19-2899: Investigation of fission gas bubble distribution, phase transformations, and bubble growth kinetics in a FFTF-irradiated U-10Zr fuel
This project aims to investigate the fission gas bubble distribution in...
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Разглеждане на NSUF 19-2899: Investigation of fission gas bubble distribution, phase transformations, and bubble growth kinetics in a FFTF-irradiated U-10Zr fuel -
NSUF 19-2900: Sink strength dependent coherency loss of precipitates during in-situ ion irradiation of fcc-structured model binary alloys
Irradiation-induced loss of coherency of precipitates can serve as a...
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Разглеждане на NSUF 19-2900: Sink strength dependent coherency loss of precipitates during in-situ ion irradiation of fcc-structured model binary alloys -
NSUF 19-2904: Investigation of the irradiation induced porosity in concrete aggregates with x-ray computed tomography and helium pycnometry
In the present project, X-ray Computed Tomography (XCT) will be used to...
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Разглеждане на NSUF 19-2904: Investigation of the irradiation induced porosity in concrete aggregates with x-ray computed tomography and helium pycnometry -
NSUF 19-CINR-16297: Irradiation studies on electron beam welded PM-HIP pressure vessel steel
The objective of this project is to assess the structural and mechanical...
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Разглеждане на NSUF 19-CINR-16297: Irradiation studies on electron beam welded PM-HIP pressure vessel steel -
NSUF 19-CINR-16380: High Fluence Active Irradiation and Combined Effects Testing of Sapphire Optical Fiber Distributed Temperature Sensors
The project will test and characterize distributed temperature measurements...
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Разглеждане на NSUF 19-CINR-16380: High Fluence Active Irradiation and Combined Effects Testing of Sapphire Optical Fiber Distributed Temperature Sensors -
NSUF 19-CINR-16547: NuScale SMR Materials Irradiation and Testing
NuScale Power, LLC (NuScale) is evaluating first-of-a-kind use of higher...
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Разглеждане на NSUF 19-CINR-16547: NuScale SMR Materials Irradiation and Testing -
NSUF 19-CINR-16549: Thermal Conductivity Measurement of Irradiated Metallic Fuel Using TREAT
With increased interest in metallic fuels from the Advanced Fuels Campaign...
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Разглеждане на NSUF 19-CINR-16549: Thermal Conductivity Measurement of Irradiated Metallic Fuel Using TREAT -
NSUF 19-CINR-16567: Irradiation-assisted Stress Corrosion Cracking of PWR-irradiated Type 347 Stainless Steel
The objective of this project is to investigate the IASCC behavior of Type...
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Разглеждане на NSUF 19-CINR-16567: Irradiation-assisted Stress Corrosion Cracking of PWR-irradiated Type 347 Stainless Steel -
NSUF 19-CINR-16583: Neutron Radiation Effect on Diffusion between Zr (and Zircaloy) and Cr for Accurate Lifetime Prediction of ATF
One of the very promising accident-tolerant fuel (ATF) claddings consists of...
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Разглеждане на NSUF 19-CINR-16583: Neutron Radiation Effect on Diffusion between Zr (and Zircaloy) and Cr for Accurate Lifetime Prediction of ATF -
NSUF 19-CINR-16895: Irradiation of Optical Components of In-Situ Laser Spectroscopic Sensors for Advanced Nuclear Reactor Systems
The development of next-generation fission reactors relies on answering...
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Разглеждане на NSUF 19-CINR-16895: Irradiation of Optical Components of In-Situ Laser Spectroscopic Sensors for Advanced Nuclear Reactor Systems -
NSUF 19-CINR-17109: Integral Fuel Rod Real-Time Wireless Sensor & Transmitter Irradiation Test and Post Irradiation Examination
The objective of the work proposed is to continue the nuclear environmental...
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Разглеждане на NSUF 19-CINR-17109: Integral Fuel Rod Real-Time Wireless Sensor & Transmitter Irradiation Test and Post Irradiation Examination -
NSUF 19-CINR-17159: High power irradiation testing of TRISO fuel particles with UCO and UO2 kernels in miniature fuel specimen capsules in HFIR
The objective is to investigate fuel performance of TRISO particles at powers...
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Разглеждане на NSUF 19-CINR-17159: High power irradiation testing of TRISO fuel particles with UCO and UO2 kernels in miniature fuel specimen capsules in HFIR -
NSUF 19-PWRBB: Baffle-former Bolt Donation to NSUF Nuclear Fuels and Materials Library
Baffle-former bolts have become a significant aging management issue for...
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Разглеждане на NSUF 19-PWRBB: Baffle-former Bolt Donation to NSUF Nuclear Fuels and Materials Library -
NSUF 20-19076: 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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Разглеждане на NSUF 20-19076: Investigation of Degradation Mechanisms of Cr coated Zirconium alloy cladding in Reactive Initiate Accidents (RIA) -
NSUF 20-19128: 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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Разглеждане на NSUF 20-19128: Machine Learning on High-Throughput Databases of Irradiation Response and Corrosion Properties of Selected Compositionally Complex Alloys for Structural Nuclear Materials -
NSUF 2020-PB2: Library Submission - Peach Bottom Unit 2 Fuel Rod Sections and Remnants
The Peach Bottom Unit 2 Reactor is a 1000 MW BWR electric plant owned and...
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Разглеждане на NSUF 2020-PB2: Library Submission - Peach Bottom Unit 2 Fuel Rod Sections and Remnants -
NSUF 20-2909: Functional Testing of an Optical Fiber Based Gamma Thermometer in the HFIR Spent Fuel Pool
The objective of this work is to test the functionality of an Optical Fiber...
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Разглеждане на NSUF 20-2909: Functional Testing of an Optical Fiber Based Gamma Thermometer in the HFIR Spent Fuel Pool