Projects
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NSUF 21-4242: Computational Thermochemistry of Pathways Toward Synthesis of Uranium Nitride
The proposed work seeks to leverage INL’s high performance computing...
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NSUF 21-4242: Computational Thermochemistry of Pathways Toward Synthesis of Uranium Nitride ansehen -
NSUF 21-4245: Comparison of Solute Cluster Formation and Evolution in Neutron-Irradiated ATR-2 to Thermally-Aged Low-Alloy Steels
This proposal focuses on the investigation of neutron-irradiated RPV steels...
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NSUF 21-4245: Comparison of Solute Cluster Formation and Evolution in Neutron-Irradiated ATR-2 to Thermally-Aged Low-Alloy Steels ansehen -
NSUF 21-4247: Coupling CFD and ML to transform the coated nuclear fuels fabrication process
Current Tristructural Isotropic (TRISO) fuel particle development is...
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NSUF 21-4247: Coupling CFD and ML to transform the coated nuclear fuels fabrication process ansehen -
NSUF 21-4248: Microstructural Evolution in Model & Real RPV steel due to Thermal Aging and Low-Dose Irradiation using Atom Probe Tomography
Motivation: Embrittlement due to solute-rich (Cu,Mn) precipitates in reactor...
Keine Datensätze
NSUF 21-4248: Microstructural Evolution in Model & Real RPV steel due to Thermal Aging and Low-Dose Irradiation using Atom Probe Tomography ansehen -
NSUF 21-4255: Radiation-induced Crystallization in Alumina Coatings: Temperature and Yttria Doping Effect. A Completion Kinetic Study to Model Radiation Resistant Coatings for the Future Nuclear System.
Different fission reactor concepts have been proposed as Generation IV...
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NSUF 21-4255: Radiation-induced Crystallization in Alumina Coatings: Temperature and Yttria Doping Effect. A Completion Kinetic Study to Model Radiation Resistant Coatings for the Future Nuclear System. ansehen -
NSUF 21-4257: The sink strength and radiation parameter effects on microchemical evolution in dual-ion irradiated additively manufactured and wrought HT9
The objective of this project to investigate the Cr-rich α′ and Ni-rich...
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NSUF 21-4257: The sink strength and radiation parameter effects on microchemical evolution in dual-ion irradiated additively manufactured and wrought HT9 ansehen -
NSUF 21-4259: Microstructural characterization of neutron irradiated NF616 (Grade 92) as a function of doses and temperatures
NF616 (Grade 92) is being considered as a candidate structural material for...
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NSUF 21-4259: Microstructural characterization of neutron irradiated NF616 (Grade 92) as a function of doses and temperatures ansehen -
NSUF 21-4263: Local thermal properties of fast reactor MOX fuels
This work will be the first application of the thermal conductivity...
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NSUF 21-4263: Local thermal properties of fast reactor MOX fuels ansehen -
NSUF 21-4265: Study of minor actinides redistribution and fission products in high burnup MOX using Electron Probe Micro Analysis (EPMA)
Transmutation of minor actinides (MA) remains one of the key goals towards a...
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NSUF 21-4265: Study of minor actinides redistribution and fission products in high burnup MOX using Electron Probe Micro Analysis (EPMA) ansehen -
NSUF 21-4269: Pre-oxidation effect on ATF cladding performance by characterization of irradiated FeCrAl-UO2 capsules
FeCrAl alloys are selected as candidate nuclear fuel cladding materials for...
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NSUF 21-4269: Pre-oxidation effect on ATF cladding performance by characterization of irradiated FeCrAl-UO2 capsules ansehen -
NSUF 21-4272: The Role of Precipitate Coherency on Helium Trapping in Additively Manufactured Alloy 718
The challenges for structural materials for high temperature advanced...
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NSUF 21-4272: The Role of Precipitate Coherency on Helium Trapping in Additively Manufactured Alloy 718 ansehen -
NSUF 21-4275: Defect generation and phase stability in single crystal mixed uranium-thorium actinide oxides
Presently, new nuclear fuel designs are limited by a lack of a basic...
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NSUF 21-4275: Defect generation and phase stability in single crystal mixed uranium-thorium actinide oxides ansehen -
NSUF 21-4276: Changes in mechanical and chemical-structural properties of gamma irradiated calcium silicate hydrates to an absorbed dose of 189 MGy with respect to pristine samples subjected to the same temperature history ProposalNew
The proposed project objectives are to study the changes in viscoelastic...
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NSUF 21-4276: Changes in mechanical and chemical-structural properties of gamma irradiated calcium silicate hydrates to an absorbed dose of 189 MGy with respect to pristine samples subjected to the same temperature history ProposalNew ansehen -
NSUF 21-4280: Microstructural Examination of Irradiation Effects on Metal Matrix Composite Neutron Absorber
This project proposes to conduct post-irradiation examination of HfAl3 Al...
1 Datensatz
NSUF 21-4280: Microstructural Examination of Irradiation Effects on Metal Matrix Composite Neutron Absorber ansehen -
NSUF 21-4282: Heavy Ion Irradiation and Characterization of Light-Refractory, BCC High-Entropy Alloys
Methods to be Employed: To explore the irradiation response of a new family...
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NSUF 21-4282: Heavy Ion Irradiation and Characterization of Light-Refractory, BCC High-Entropy Alloys ansehen -
NSUF 21-4296: Irradiation of stainless steel claddings produced by additive manufacturing for in-core applications
We are assessing the impact of irradiation on corrosion resistance of samples...
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NSUF 21-4296: Irradiation of stainless steel claddings produced by additive manufacturing for in-core applications ansehen -
NSUF 21-4304: Assessing the Radial Thermal Conductivity Change in FBR MOX Fuel
Radial variations in temperature and burnup result in nonuniform...
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NSUF 21-4304: Assessing the Radial Thermal Conductivity Change in FBR MOX Fuel ansehen -
NSUF 21-4307: Ion Irradiation and Examination of Additive Friction Stir Manufactured 316 Stainless Steel Component
Stainless steels are extremely relevant for current and next generation...
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NSUF 21-4307: Ion Irradiation and Examination of Additive Friction Stir Manufactured 316 Stainless Steel Component ansehen -
NSUF 21-4320: The effects of stress on void superlattice formation during Cr+ self-ion-irradiation of chromium
Chromium coating has been proposed as an accident tolerant fuel (ATF) concept...
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NSUF 21-4320: The effects of stress on void superlattice formation during Cr+ self-ion-irradiation of chromium ansehen -
NSUF 21-4325: In-situ mechanical testing of neutron-irradiated 304SS exhibiting unusual deformation and fracture behavior with respect to temperature
This RTE proposal assesses micro-tensile testing as a cost-effective...
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NSUF 21-4325: In-situ mechanical testing of neutron-irradiated 304SS exhibiting unusual deformation and fracture behavior with respect to temperature ansehen