Projects
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NSUF 13-409: Electron Backscatter Diffraction and Atom Probe Tomography to Study Krypton Segregation Behavior in Uranium Dioxide
It is widely known that microstructural changes influence the thermal...
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瀏覽 NSUF 13-409: Electron Backscatter Diffraction and Atom Probe Tomography to Study Krypton Segregation Behavior in Uranium Dioxide -
NSUF 13-410: Characterization and correlation of SiC layer grain size/grain boundary orientation with strength/layer growth conditions - Lite
Silicon carbide (SiC) is a candidate material for a fuel matrix during...
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瀏覽 NSUF 13-410: Characterization and correlation of SiC layer grain size/grain boundary orientation with strength/layer growth conditions - Lite -
NSUF 13-411: Irradiation Effects inAged Cast Duplex Stainless Steels
The work is planned to systemically characterize the neutron irradiated cast...
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瀏覽 NSUF 13-411: Irradiation Effects inAged Cast Duplex Stainless Steels -
NSUF 13-412: STEM/LEAP Study of Fission Product Transportation in Neutron Irradiated TRISO Fuel Particles
The objective of the proposed project is to build a complete understanding of...
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瀏覽 NSUF 13-412: STEM/LEAP Study of Fission Product Transportation in Neutron Irradiated TRISO Fuel Particles -
NSUF 13-413: Advanced Microstructural Characterization of Spark Plasma Sintered Lanthanum-Bearing Nanostructured Ferritic Steels
Nanostructured ferritic steels (NSF) have attracted much attention as fuel...
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瀏覽 NSUF 13-413: Advanced Microstructural Characterization of Spark Plasma Sintered Lanthanum-Bearing Nanostructured Ferritic Steels -
NSUF 13-418: Irradiation-Assisted Diffusion of Uranium-Fe Diffusion Couples
The project will study the effect of radiation damage on interface compound...
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瀏覽 NSUF 13-418: Irradiation-Assisted Diffusion of Uranium-Fe Diffusion Couples -
NSUF 13-419: Toward an understanding of the effect of dose rate on the irradiation response of F-M alloys
Ferritic-martensitic (F-M) alloys are leading candidates for cladding and...
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瀏覽 NSUF 13-419: Toward an understanding of the effect of dose rate on the irradiation response of F-M alloys -
NSUF 13-425: Microstructure Analysis of HIgh Dose Neutron Irradiated Microstructures
The objective of this project is to characterize the microstructure of alloys...
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瀏覽 NSUF 13-425: Microstructure Analysis of HIgh Dose Neutron Irradiated Microstructures -
NSUF 13-427: Microstructures of Low-Dose He2+ and H+ Ion Irradiated UO2
The microstructure of nuclear fuel, UO2, is strongly modified under...
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瀏覽 NSUF 13-427: Microstructures of Low-Dose He2+ and H+ Ion Irradiated UO2 -
NSUF 13-429: Electron Backscatter Diffraction and Atom Probe Tomography to Study Grain Boundary Chemistry Variation in Off Stoichiometric Uranium Dioxide Thin Films
It is widely known that microstructural changes influence the thermal...
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瀏覽 NSUF 13-429: Electron Backscatter Diffraction and Atom Probe Tomography to Study Grain Boundary Chemistry Variation in Off Stoichiometric Uranium Dioxide Thin Films -
NSUF 13-431: Study of the Microstructure of Kr and Xe Irradiated UO2 by Advanced Microscopy Techniques
The rapid turnaround experiment is to clarify the microstructure of UO2...
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瀏覽 NSUF 13-431: Study of the Microstructure of Kr and Xe Irradiated UO2 by Advanced Microscopy Techniques -
NSUF 13-432: Radiation resistance of novel ODS alloy
A novel Oxide Dispersion Strengthened (ODS) ferritic alloy was developed at...
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瀏覽 NSUF 13-432: Radiation resistance of novel ODS alloy -
NSUF 14-439: APT (LEAP) analyisis of Cs implanted SiC
The project objectives are to determine the pathway of Cs diffusion in the...
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瀏覽 NSUF 14-439: APT (LEAP) analyisis of Cs implanted SiC -
NSUF 14-448: Synchrotron XAS and EXAFS Study of Technetium-99 Relevant to the Nuclear Fuel Cycle
The synchrotron radiation techniques of X-ray Absorption Near Edge...
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瀏覽 NSUF 14-448: Synchrotron XAS and EXAFS Study of Technetium-99 Relevant to the Nuclear Fuel Cycle -
NSUF 14-450: Post Irradiation Examination of ATR-irradiated Ultra-Fine Grained Steel
Effect of radiation exposure on nanograin structured metals is of immense...
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瀏覽 NSUF 14-450: Post Irradiation Examination of ATR-irradiated Ultra-Fine Grained Steel -
NSUF 14-451: Microstructural and mechanical characterization of self-ion irradiated 14LMT nanostructured ferritic steels
Yttria-containing nanostructured ferritic steels (NFS) are considered a...
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瀏覽 NSUF 14-451: Microstructural and mechanical characterization of self-ion irradiated 14LMT nanostructured ferritic steels -
NSUF 14-452: Microstructural and mechanical characterization of self-ion irradiated Grade 92 steel
Ferritic-martensitic steels have many interesting properties that make them...
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瀏覽 NSUF 14-452: Microstructural and mechanical characterization of self-ion irradiated Grade 92 steel -
NSUF 14-460: Development of advanced crystallographic analysis techniques for localised fission product transport in irradiated SiC.
The objective of this work is to develop and apply state-of-the-art...
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瀏覽 NSUF 14-460: Development of advanced crystallographic analysis techniques for localised fission product transport in irradiated SiC. -
NSUF 14-462: Effects of neutron irradiation on mechanical properties of nanocrystalline metals
The effect of radiation exposure on nano grain structured metals is of...
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瀏覽 NSUF 14-462: Effects of neutron irradiation on mechanical properties of nanocrystalline metals -
NSUF 14-463: Synchrotron X-Ray Characterizations of Advanced Accident-tolerant Cladding
We have initiated the plan for developing advanced ceramic coatings on Zr...
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瀏覽 NSUF 14-463: Synchrotron X-Ray Characterizations of Advanced Accident-tolerant Cladding