Projects
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NSUF 16-802: Microstructural Characterization of Archival Surveillance Steels from the Advanced Test Reactor (ATR-2) Neutron Irradiation Experiment
This proposal covers characterization of a number of different RPV...
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NSUF 16-804: Investigation of Deformation Mechanisms of an Intermetallic-strengthened Alloy with and without Heavy Ion Irradiation
A series of Zr-containing ferritic alloys were recently developed with the...
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NSUF 16-812: Microstructural characterization of 23% burn-up MOX fuel
Attaining fundamental understanding of fuel performance requires detailed...
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NSUF 16-813: Characterization of ferritic steels Fe-9Cr and 9Cr2WYT ODS alloys irradiated in ATR
Development of advanced fuel claddings and structural materials that can...
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NSUF 16-821: Changes on viscoelastic behavior, morphology and chemical structure of gamma irradiated calcium silicate hydrates with respect to non-irradiated samples
The proposed project objectives are to study the changes in viscoelastic...
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NSUF 16-832: Ion beam radiation damage assessment in advanced Ferritic/Martensitic (F/M) alloys
In-situ transmission electron microscopy (TEM) combined with ion irradiation...
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NSUF 16-835: Radiation Response and Microstructure of Accident Tolerant U3Si2 Fuels by Ion Beam Irradiation
U3Si2 fuel is the leading candidate of the accident tolerant fuels (ATFs),...
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NSUF 16-837: Localized mechanical property assessment of neutron irradiated SiC/SiC composites at elevated temperature
In this proposal we investigate the effects of irradiation on the individual...
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NSUF 16-838: TEM Investigation of Irradiated Austenitic Stainless Steel Alloys
The proposed post-irradiation examination (PIE) activity will examine the...
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NSUF 16-840: Hydride Microstructure at the Metal-Oxide Interface of Zircaloy-4 from H.B. Robinson Nuclear Reactor
During nuclear reactor operation, some of the hydrogen that is produced by...
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NSUF 16-846: The window of gas-bubble superlattice formation in bcc metals
Gas-bubble superlattice (GBS) have been observed for decades, they can form...
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NSUF 16-849: Micromechanical testing of Sintered UO2 fuel pellets with Controlled Microstructure
Due to extreme working environment of nuclear reactors, such as high...
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NSUF 16-853: Cavity Shrinkage in Fe21Cr32Ni under in situ Ion Irradiation
In-situ ion irradiations will be performed at the Intermediate Voltage...
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NSUF 16-859: In-situ Observation of Defect Clustering in High Entropy Alloys
The emerging applications of high-entropy alloys (HEAs) have received great...
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NSUF 16-863: Irradiation of the vanadium carbide coating on HT-9 steel using protons
A vanadium based coating layer on the inner surface of HT-9 fuel cladding...
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NSUF 16-864: Low temperature Fe-ion irradiation of 15-15Ti steel in different thermo-mechanical states
This work proposes self-ion irradiation at 300 and 450°C on cold worked and...
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NSUF 16-865: Ion irradiation of advanced materials – nanostructured steels and high entropy alloysNew Proposal
Efforts are undergoing to extend the life of current reactors and develop...
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NSUF 16-870: In situ ion irradiation and high resolution microstructure and microchemistry analysis of accident tolerant fuels
Project objectives: Because of its use as the preferred nuclear fuel cladding...
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NSUF 16-CINR-10181: Effects of High Dose on Laser Welded, Irradiated AISI 304SS
The objective of this project is to assess the mechanical integrity of laser...
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NSUF 16-CINR-10200: Feasibility of Combined Ion-Neutron Irradiation for Accessing High Dose Levels
Recently, there have been significant discussions and conference...
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