Projects
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NSUF 16-618: Nano-Indentation Investigations on Nano-grained UO2 with and without High-Energy Ion Irradiation
Grain boundary affects a series of key material properties, including...
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瀏覽 NSUF 16-618: Nano-Indentation Investigations on Nano-grained UO2 with and without High-Energy Ion Irradiation -
NSUF 16-622: Characterize Neutron Irradiated HT-UPS Stainless Steel Using Transmission Electron Microscopy and Atom Probe Tomography
To fully understand how the high-temperature ultrafine-precipitate-...
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瀏覽 NSUF 16-622: Characterize Neutron Irradiated HT-UPS Stainless Steel Using Transmission Electron Microscopy and Atom Probe Tomography -
NSUF 16-623: A comparison of mechanical properties of ion and neutron irradiated Fe-9Cr
In nuclear materials testing heavy ion irradiation is commonly used to...
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瀏覽 NSUF 16-623: A comparison of mechanical properties of ion and neutron irradiated Fe-9Cr -
NSUF 16-624: Effects of carbon addition on the solute redistribution in Fe-9Cr alloys under irradiation
Fe-9Cr alloys are leading candidates for the cladding and core components in...
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瀏覽 NSUF 16-624: Effects of carbon addition on the solute redistribution in Fe-9Cr alloys under irradiation -
NSUF 16-625: Understanding the effects of irradiation dose rate and particle type in Ferritic/Martensitic alloys
The objective of this project is to understand the microstructural effects of...
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瀏覽 NSUF 16-625: Understanding the effects of irradiation dose rate and particle type in Ferritic/Martensitic alloys -
NSUF 16-627: Microstructure characterization of U-Mo/Al fuel irradiated with Xe
The dispersion-type fuel developed to be used in research and test reactors...
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瀏覽 NSUF 16-627: Microstructure characterization of U-Mo/Al fuel irradiated with Xe -
NSUF 16-633: Microstructural Characterization of Post-Irradiation Alloys for Integrated FHR Technology Development
The Fluoride salt-cooled High-temperature Reactor (FHR) is being actively...
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瀏覽 NSUF 16-633: Microstructural Characterization of Post-Irradiation Alloys for Integrated FHR Technology Development -
NSUF 16-637: TEM Microstructural Characterization of Irradiated UO2 Fuel
INL has undertaken the effort to characterize a variety of fuel systems,...
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瀏覽 NSUF 16-637: TEM Microstructural Characterization of Irradiated UO2 Fuel -
NSUF 16-638: Influence of neutron irradiation on the microstructures and electrical properties of polymer derived ceramic sensing material
The objective of this project is to perform neutron irradiation damage test...
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瀏覽 NSUF 16-638: Influence of neutron irradiation on the microstructures and electrical properties of polymer derived ceramic sensing material -
NSUF 16-640: TEM investigation of the SiC containment layer of irradiated nuclear fuel particles
We propose to study the interaction of fission products with the barrier SiC...
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瀏覽 NSUF 16-640: TEM investigation of the SiC containment layer of irradiated nuclear fuel particles -
NSUF 16-642: APT of Irradiated UO2 Fuel
INL has undertaken the effort to characterize a variety of fuel systems,...
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瀏覽 NSUF 16-642: APT of Irradiated UO2 Fuel -
NSUF 16-643: Effect of Neutron Irradiation on Tensile Deformation of a HT-UPS Stainless Steel
It is proposed to conduct microstructural characterization on a tensile-...
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瀏覽 NSUF 16-643: Effect of Neutron Irradiation on Tensile Deformation of a HT-UPS Stainless Steel -
NSUF 16-644: In situ study of defect accumulation in Ti-6Al-4V under heavy ion irradiation: Influence of the microstructure and temperature
In previous studies, a dual dose and temperature dependence was observed in...
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瀏覽 NSUF 16-644: In situ study of defect accumulation in Ti-6Al-4V under heavy ion irradiation: Influence of the microstructure and temperature -
NSUF 16-645: B and Li grain boundary segregation in irradiated LWR steels
Boron is a trace element present either as an intentional addition or as an...
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瀏覽 NSUF 16-645: B and Li grain boundary segregation in irradiated LWR steels -
NSUF 16-649: Irradiation Effect in the Heterogeneous Hardening of Cast Austenitic Stainless Steels
The duplex cast austenitic stainless steels (CASS) possess excellent...
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瀏覽 NSUF 16-649: Irradiation Effect in the Heterogeneous Hardening of Cast Austenitic Stainless Steels -
NSUF 16-650: Microstructure Analysis of High Dose Neutron Irradiated Microstructures
The promise for developing new, advanced nuclear reactor concepts that...
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瀏覽 NSUF 16-650: Microstructure Analysis of High Dose Neutron Irradiated Microstructures -
NSUF 16-651: Determining Structure Evolution in Isomolded Nuclear Graphite Under Stress
Graphite is an important material for a number of reactor systems and...
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瀏覽 NSUF 16-651: Determining Structure Evolution in Isomolded Nuclear Graphite Under Stress -
NSUF 16-652: Wigner Energy of SiC Irradiated to High Levels of Swelling
Recently, through an FCRD sponsored research effort, single crystal alpha and...
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瀏覽 NSUF 16-652: Wigner Energy of SiC Irradiated to High Levels of Swelling -
NSUF 16-655: Evaluate the ferrite decomposition in irradiated duplex cast stainless steels
The work is aimed to complete the study on cast stainless steels irradiated...
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瀏覽 NSUF 16-655: Evaluate the ferrite decomposition in irradiated duplex cast stainless steels -
NSUF 16-656: TEM in situ microcantilever testing of irradiated F/M alloys
The objective of this project is to acquire a multiscale mechanistic...
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瀏覽 NSUF 16-656: TEM in situ microcantilever testing of irradiated F/M alloys