Projects
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NSUF 23-4593: Serial Sectioning to Quantify Fission Induced Microstructural Evolution in U-Zr Alloys
This work will use scanning electron microscopy (SEM) and electron dispersive...
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NSUF 23-4593: Serial Sectioning to Quantify Fission Induced Microstructural Evolution in U-Zr Alloys ansehen -
NSUF 23-4597: Electron tomography study of dislocation loops and precipitates in ion irradiated Fe-Cr alloys
This proposal aims to examine the 3D configuration of petal-shaped...
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NSUF 23-4597: Electron tomography study of dislocation loops and precipitates in ion irradiated Fe-Cr alloys ansehen -
NSUF 23-4600: Microstructural characterization of neutron irradiated C-C composites
In recent years the nuclear industry has considered C-C composites a...
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NSUF 23-4600: Microstructural characterization of neutron irradiated C-C composites ansehen -
NSUF 23-4603: Neutron Irradiation of Updated In-Pile Steady State, Extreme Temperature Experiment (INSET)
Material and sensor characterization at temperatures up to and exceeding...
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NSUF 23-4603: Neutron Irradiation of Updated In-Pile Steady State, Extreme Temperature Experiment (INSET) ansehen -
NSUF 23-4606: Neutron Irradiation of a radiation resistant digitizer at PULSTAR
The goal of this work is to elucidate critical points of failure of the...
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NSUF 23-4606: Neutron Irradiation of a radiation resistant digitizer at PULSTAR ansehen -
NSUF 23-4629: Atom probe characterization of HT-9 as a function of neutron irradiation temperature
Ferritic-martensitic (F-M) steels are being considered as candidate in-core...
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NSUF 23-4629: Atom probe characterization of HT-9 as a function of neutron irradiation temperature ansehen -
NSUF 23-4634: Correlative Atom Probe Tomography of the Buffer-IPyC Interlayer Region of TRISO-coated Particles
Research is being conducted (DOE NEUP 17251 “Thermomechanical Properties of...
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NSUF 23-4634: Correlative Atom Probe Tomography of the Buffer-IPyC Interlayer Region of TRISO-coated Particles ansehen -
NSUF 23-4636: Stability of VN, TaN, and TaC MX-type Precipitates in Ferritic Steels under Neutron Radiation
A leading strategy for designing radiation resistant nuclear structural...
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NSUF 23-4636: Stability of VN, TaN, and TaC MX-type Precipitates in Ferritic Steels under Neutron Radiation ansehen -
NSUF 23-4641: Critical database development of high dose microstructure evolution in irradiated advanced steels
The promise for developing new, advanced nuclear reactor concepts, and the...
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NSUF 23-4641: Critical database development of high dose microstructure evolution in irradiated advanced steels ansehen -
NSUF 23-4648: Hydrogen quantification in neutron irradiated monolithic metal hydrides compacts
Metal hydrides are an essential component for designing and building advanced...
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NSUF 23-4648: Hydrogen quantification in neutron irradiated monolithic metal hydrides compacts ansehen -
NSUF 23-4651: Investigating nitrogen effects on the mechanical properties and microstructure evolution in neutron irradiated HT-9 steel
Ferritic/martensitic (F/M) steels are being considered as potential...
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NSUF 23-4651: Investigating nitrogen effects on the mechanical properties and microstructure evolution in neutron irradiated HT-9 steel ansehen -
NSUF 23-4652: Irradiating a novel thin-film scintillator for neutron radiography
Dr. Zhibin Yu at Florida State University is developing a novel thin-film...
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NSUF 23-4652: Irradiating a novel thin-film scintillator for neutron radiography ansehen -
NSUF 23-4654: Quantifying the effect of simultaneous vs. sequential irradiation on creep performance of additively manufactured austenitic stainless steel
Alloy 316H SS is one of only six structural materials qualified for use in...
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NSUF 23-4654: Quantifying the effect of simultaneous vs. sequential irradiation on creep performance of additively manufactured austenitic stainless steel ansehen -
NSUF 23-4662: Post Incubation Void Swelling in Tempered Martensitic Steels
The potential for void swelling in 9-12 Cr tempered martensitic steels (TMS)...
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NSUF 23-4662: Post Incubation Void Swelling in Tempered Martensitic Steels ansehen -
NSUF 23-4668: In situ Synchrotron radiation diffraction study of the Effect of Radiation Damage on the Precipitation and Dissolution of Hydrides in Zircaloy
Hydrogen absorption and hydride particle precipitation in nuclear fuel...
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NSUF 23-4668: In situ Synchrotron radiation diffraction study of the Effect of Radiation Damage on the Precipitation and Dissolution of Hydrides in Zircaloy ansehen -
NSUF 23-4673: In-situ high temperature micro-tensile testing of reactor irradiated HT9 cladding
HT9 cladding used in sodium fast reactors can experience dramatical...
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NSUF 23-4673: In-situ high temperature micro-tensile testing of reactor irradiated HT9 cladding ansehen -
NSUF 23-4674: Assessing Deformation Mechanisms in Irradiated Superalloy 718 using Ultra-Miniature Specimens
Ni-based superalloys are a primary candidate alloy class for current and...
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NSUF 23-4674: Assessing Deformation Mechanisms in Irradiated Superalloy 718 using Ultra-Miniature Specimens ansehen -
NSUF 23-4676: Increasing the Sensitivity of Passive SiC Thermometry Through Nanocalorimetry Experiments
Determination of the sample temperature during irradiation experiments is...
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NSUF 23-4676: Increasing the Sensitivity of Passive SiC Thermometry Through Nanocalorimetry Experiments ansehen -
NSUF 23-4679: Correlating microstructure to the thermal conductivity of irradiated U-20Pu-10Zr fuels
The objective of the proposed work is to measure the local thermal...
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NSUF 23-4679: Correlating microstructure to the thermal conductivity of irradiated U-20Pu-10Zr fuels ansehen -
NSUF 23-4680: Investigation of Void Swelling and Chemical Segregation in Heavy Ion Irradiated Compositionally Complex Alloys
The proposed study will investigate the formation of extended defects after...
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NSUF 23-4680: Investigation of Void Swelling and Chemical Segregation in Heavy Ion Irradiated Compositionally Complex Alloys ansehen