Projects
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NSUF 17-1042: Microstructural characterization of 13% burn-up MOX fuel
Attaining fundamental understanding of fuel performance requires detailed...
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NSUF 17-1042: Microstructural characterization of 13% burn-up MOX fuel ansehen -
NSUF 17-1043: Microstructural characterization of 21% burn-up MOX fuel
Attaining fundamental understanding of fuel performance requires detailed...
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NSUF 17-1043: Microstructural characterization of 21% burn-up MOX fuel ansehen -
NSUF 17-1047: Examining microstructural differences in irradiated HT9, correlated with differences in processing prior to irradiation
The goal of this project is to do an examination of the irradiated...
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NSUF 17-1047: Examining microstructural differences in irradiated HT9, correlated with differences in processing prior to irradiation ansehen -
NSUF 17-1052: Study of the factors affecting the radiation tolerance of MAX phases for innovative fuel cladding concepts
This project aims at understanding the factors affecting the radiation...
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NSUF 17-1052: Study of the factors affecting the radiation tolerance of MAX phases for innovative fuel cladding concepts ansehen -
NSUF 17-1055: Post-irradiation observation following high-rate self-ion irradiation of previously neutron-irradiated 304 stainless steel
The project aims to combine two types of irradiation to forecast the behavior...
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NSUF 17-1055: Post-irradiation observation following high-rate self-ion irradiation of previously neutron-irradiated 304 stainless steel ansehen -
NSUF 17-1065: Fundamental Study of Alloying Complexity Effects on the Irradiation Process in High Entropy Alloys
High entropy alloys (HEAs) have attracted wide attention for its potential...
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NSUF 17-1065: Fundamental Study of Alloying Complexity Effects on the Irradiation Process in High Entropy Alloys ansehen -
NSUF 17-1066: Changes on viscoelastic behavior, morphology and chemical structure of gamma irradiated calcium silicate hydrates to 1.94 MGy with respect to non-irradiated samples
The proposed project objectives are to study the changes in viscoelastic...
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NSUF 17-1066: Changes on viscoelastic behavior, morphology and chemical structure of gamma irradiated calcium silicate hydrates to 1.94 MGy with respect to non-irradiated samples ansehen -
NSUF 17-1069: Atomic Probe Tomography Studies of Irradiated Cold Spray Coatings for Accident Tolerant Cladding
The goal of the proposed RTE research, led by the University of Wisconsin,...
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NSUF 17-1069: Atomic Probe Tomography Studies of Irradiated Cold Spray Coatings for Accident Tolerant Cladding ansehen -
NSUF 17-1073: Ion irradiation response of nanostructured alloys: In-situ TEM observations vs. ex-situ characterization
In-situ transmission electron microscopy (TEM) combined with ion irradiation...
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NSUF 17-1073: Ion irradiation response of nanostructured alloys: In-situ TEM observations vs. ex-situ characterization ansehen -
NSUF 17-1076: Characterization of Grain Boundary Damage in Highly Irradiated Specimens Exposed to Irradiation Assisted Stress Corrosion Cracking.
The objective of this work is to quantify, at the microscopic scale, the...
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NSUF 17-1076: Characterization of Grain Boundary Damage in Highly Irradiated Specimens Exposed to Irradiation Assisted Stress Corrosion Cracking. ansehen -
NSUF 17-1080: Post-irradiation analysis of hybrid metallic coatings on SiC after neutron irradiation 290-330°C
The objective of the project is to examine and understand the post-...
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NSUF 17-1080: Post-irradiation analysis of hybrid metallic coatings on SiC after neutron irradiation 290-330°C ansehen -
NSUF 17-1081: Microstructure and microchemical characterization of neutron and proton irradiated Alloy D9 using APT and TEM
The objective of this study is to understand the effect of irradiation on the...
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NSUF 17-1081: Microstructure and microchemical characterization of neutron and proton irradiated Alloy D9 using APT and TEM ansehen -
NSUF 17-1090: In situ amorphization studies of forsterite, diopside and quartz under ion irradiation
The proposed project objectives are to redefine the critical ion doses for...
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NSUF 17-1090: In situ amorphization studies of forsterite, diopside and quartz under ion irradiation ansehen -
NSUF 17-1091: Characterize the Irradiated Microstructure and Understand the Fission Product Behavior in an Irradiated and Safety Tested AGR-1 TRISO Fuel Particle New Proposal
TRISO-coated particle fuel is a center piece in developing the high...
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NSUF 17-1091: Characterize the Irradiated Microstructure and Understand the Fission Product Behavior in an Irradiated and Safety Tested AGR-1 TRISO Fuel Particle New Proposal ansehen -
NSUF 17-1092: Effect of Phosphorous (P) on precipitation and segregation behavior in neutron irradiated Reactor Pressure Vessel steels in the Advanced Test Reactor (ATR-2): An Atom Probe study.
The objective of this study is to understand the effect of Phosphorous (P) on...
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NSUF 17-1092: Effect of Phosphorous (P) on precipitation and segregation behavior in neutron irradiated Reactor Pressure Vessel steels in the Advanced Test Reactor (ATR-2): An Atom Probe study. ansehen -
NSUF 17-1093: AsTeROID (follow-on AsTeR (Advanced Test Reactor) project to Optimize hydrogen-assisted Irradiation growth and Dimensional stability)
The scientific objective of this project is to develop a better understanding...
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NSUF 17-1093: AsTeROID (follow-on AsTeR (Advanced Test Reactor) project to Optimize hydrogen-assisted Irradiation growth and Dimensional stability) ansehen -
NSUF 17-1098: An in-situ TEM characterization of tensile testing of ion irradiated HT-UPS steel at RT and 400°C
The objective of this research is to develop an understanding of the...
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NSUF 17-1098: An in-situ TEM characterization of tensile testing of ion irradiated HT-UPS steel at RT and 400°C ansehen -
NSUF 17-1099: In Situ Transmission Electron Microscopy Study of Radiation Damage Effects on the d-Hydride Microstructure in Irradiated Zircaloy-4
Hydride formation is one of the major embrittling mechanisms for zirconium-...
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NSUF 17-1099: In Situ Transmission Electron Microscopy Study of Radiation Damage Effects on the d-Hydride Microstructure in Irradiated Zircaloy-4 ansehen -
NSUF 17-1104: Radiation tolerance of Mn+1AXn phase nuclear fuel cladding materials
In this project, 1 MeV Kr ions will be used to irradiate Ti2AlC, Cr2AlC,...
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NSUF 17-1104: Radiation tolerance of Mn+1AXn phase nuclear fuel cladding materials ansehen -
NSUF 17-1105: The effectiveness of coherent and incoherent twin boundaries in alleviating radiation damage in heavy-ion-irradiated 316L austenitic stainless steels
The proposed experiment will consist in carrying out TEM in-situ ion...
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NSUF 17-1105: The effectiveness of coherent and incoherent twin boundaries in alleviating radiation damage in heavy-ion-irradiated 316L austenitic stainless steels ansehen