Projects
-
NSUF 21-4242: Computational Thermochemistry of Pathways Toward Synthesis of Uranium Nitride
The proposed work seeks to leverage INL’s high performance computing...
0 የመረጃ ስብስቦች
NSUF 21-4242: Computational Thermochemistry of Pathways Toward Synthesis of Uranium Nitride አሳይ -
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...
0 የመረጃ ስብስቦች
NSUF 21-4245: Comparison of Solute Cluster Formation and Evolution in Neutron-Irradiated ATR-2 to Thermally-Aged Low-Alloy Steels አሳይ -
NSUF 21-4247: Coupling CFD and ML to transform the coated nuclear fuels fabrication process
Current Tristructural Isotropic (TRISO) fuel particle development is...
0 የመረጃ ስብስቦች
NSUF 21-4247: Coupling CFD and ML to transform the coated nuclear fuels fabrication process አሳይ -
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...
0 የመረጃ ስብስቦች
NSUF 21-4248: Microstructural Evolution in Model & Real RPV steel due to Thermal Aging and Low-Dose Irradiation using Atom Probe Tomography አሳይ -
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...
0 የመረጃ ስብስቦች
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. አሳይ -
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...
0 የመረጃ ስብስቦች
NSUF 21-4257: The sink strength and radiation parameter effects on microchemical evolution in dual-ion irradiated additively manufactured and wrought HT9 አሳይ -
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...
0 የመረጃ ስብስቦች
NSUF 21-4259: Microstructural characterization of neutron irradiated NF616 (Grade 92) as a function of doses and temperatures አሳይ -
NSUF 21-4263: Local thermal properties of fast reactor MOX fuels
This work will be the first application of the thermal conductivity...
0 የመረጃ ስብስቦች
NSUF 21-4263: Local thermal properties of fast reactor MOX fuels አሳይ -
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...
0 የመረጃ ስብስቦች
NSUF 21-4265: Study of minor actinides redistribution and fission products in high burnup MOX using Electron Probe Micro Analysis (EPMA) አሳይ -
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...
0 የመረጃ ስብስቦች
NSUF 21-4269: Pre-oxidation effect on ATF cladding performance by characterization of irradiated FeCrAl-UO2 capsules አሳይ -
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...
0 የመረጃ ስብስቦች
NSUF 21-4272: The Role of Precipitate Coherency on Helium Trapping in Additively Manufactured Alloy 718 አሳይ -
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...
0 የመረጃ ስብስቦች
NSUF 21-4275: Defect generation and phase stability in single crystal mixed uranium-thorium actinide oxides አሳይ -
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...
0 የመረጃ ስብስቦች
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 አሳይ -
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 የመረጃ ስብስብ
NSUF 21-4280: Microstructural Examination of Irradiation Effects on Metal Matrix Composite Neutron Absorber አሳይ -
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...
0 የመረጃ ስብስቦች
NSUF 21-4282: Heavy Ion Irradiation and Characterization of Light-Refractory, BCC High-Entropy Alloys አሳይ -
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...
0 የመረጃ ስብስቦች
NSUF 21-4296: Irradiation of stainless steel claddings produced by additive manufacturing for in-core applications አሳይ -
NSUF 21-4304: Assessing the Radial Thermal Conductivity Change in FBR MOX Fuel
Radial variations in temperature and burnup result in nonuniform...
0 የመረጃ ስብስቦች
NSUF 21-4304: Assessing the Radial Thermal Conductivity Change in FBR MOX Fuel አሳይ -
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...
0 የመረጃ ስብስቦች
NSUF 21-4307: Ion Irradiation and Examination of Additive Friction Stir Manufactured 316 Stainless Steel Component አሳይ -
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...
0 የመረጃ ስብስቦች
NSUF 21-4320: The effects of stress on void superlattice formation during Cr+ self-ion-irradiation of chromium አሳይ -
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...
0 የመረጃ ስብስቦች
NSUF 21-4325: In-situ mechanical testing of neutron-irradiated 304SS exhibiting unusual deformation and fracture behavior with respect to temperature አሳይ