Projects
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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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NSUF 16-657: In Situ Observation of Lunar Crater Features in Xe Irradiated UO2 at High Dose
To simulate fission fragments damage and fission gas evolution in UO2, 300...
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NSUF 16-661: Investigation of the interface strength for matrix-fiber interface of irradiated SiC composite materials
The objective of this proposal is to investigate the interface strength for...
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NSUF 16-682: Destructive Examination of Metallic Fuel Elements Subjected to Transient Irradiation
A unique transient irradiation experiment was conducted during one of the...
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NSUF 16-683: A TEM study of proton, heavy-ion and neutron irradiated FeCr
in nuclear materials research, it is essential to be able to replicate the...
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NSUF 16-687: Parametric study of factors affecting precipitation in model FeCrAl alloys
The objective of this project is to investigate the factors affecting alpha’...
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NSUF 16-694: Nanoindentation investigations of neutron-irradiated Fe-Cr-C ternary model alloys
The objective of this research program is to investigate the neutron...
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NSUF 16-696: Neutron Irradiation Effects on Tensile Properties and Deformation Behavior of 14YWT
The objective of this research is to investigate the effects of neutron...
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NSUF 16-700: Analysis of differential damage in binary carbide hybrids undergoing radiation damage
Through the novel use of high resolution post irradiation analysis, coupled...
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NSUF 16-705: Atom Probe Characterization of Two Different Precipitation Regimes in a U-6wt.%Nb alloy
U-Nb alloys are of current interest in defense applications and could...
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NSUF 16-710: Modeling nanocluster evolution in irradiated ferritic ODS and ferritic/martensitic alloys
The objective of this project is to provide validation data for a...
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NSUF 16-713: Improving understanding of defect evolution in neutron-irradiated MAX phases
The objective of this project is to investigate the defect type responsible...
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NSUF 16-737: Microstructural recovery in irradiated nanostructured ferritic alloys
I have samples of 14YWT nanostructured ferritic alloy that have been ion-...
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NSUF 16-766: Fission Gas Bubble Characterizations of High-Energy Xe Implanted U3Si2
Gaseous fission products such as Xe and Kr form bubbles within nuclear fuel...
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NSUF 16-767: Xe Bubble Evolution in U3Si2: an in situ TEM Investigation
Gaseous fission products such as Xe and Kr form bubbles within nuclear fuel...
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NSUF 16-771: Investigation of the Thermal Stability of Mn-Ni-Si Precipitates in Ion Irradiated RPV Steels
Accurately predicting embrittlement of reactor pressure vessel (RPV) steels...
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NSUF 16-782: Micro-structural and -chemical Investigations of the Short-Term Annealing of Irradiation-Induced Late Blooming Phase Precipitates in a High-Ni Reactor Pressure Vessel Steel Weld
Embrittlement of reactor pressure vessel (RPV) steels by irradiation is a...
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NSUF 16-788: Study of deformation mechanisms of zirconium alloys under irradiation
In Pressurized Water Reactors, cladding tubes, made of zirconium alloys, are...
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NSUF 16-790: Microstructural evolution of dual-phase cast stainless steels under irradiation
The embrittlement of cast austenitic stainless steels and stainless steel...
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NSUF 16-797: In situ studies of radiation damage in nanostructured austenitic stainless steels
Technical Abstract The main objective of this RTE proposal is to use in situ...
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