Projects
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NSUF 18-CINR-14741: Demonstration of a Methodology for Direct Validation of MARMOT Irradiation-Induced Microstructural Evolution and Physical Property Models Using U-10Zr
The objective of this project is to demonstrate, for the first time, a...
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NSUF 18-CINR-14741: Demonstration of a Methodology for Direct Validation of MARMOT Irradiation-Induced Microstructural Evolution and Physical Property Models Using U-10Zr ansehen -
NSUF 18-CINR-14749: Irradiation Behavior of Piezoelectric Materials for Nuclear Reactor Sensors
The purpose of the study is to investigate the physical behavior of...
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NSUF 18-CINR-14749: Irradiation Behavior of Piezoelectric Materials for Nuclear Reactor Sensors ansehen -
NSUF 18-CINR-14772: Understanding Swelling-Related Embrittlement of AISI316 Stainless Steel Irradiated in EBR-II
The objective of this proposal is to investigate the swelling-related...
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NSUF 18-CINR-14772: Understanding Swelling-Related Embrittlement of AISI316 Stainless Steel Irradiated in EBR-II ansehen -
NSUF 18-CINR-14783: Nanodispersion Strengthened Metallic Composites with Enhanced Neutron Irradiation Tolerance
We propose to significantly improve the fundamental understanding of the...
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NSUF 18-CINR-14783: Nanodispersion Strengthened Metallic Composites with Enhanced Neutron Irradiation Tolerance ansehen -
NSUF 18-CINR-14787: High-dose ion irradiation testing and relevant post-irradiation examination of friction-stir-welded ODS MA956 alloy
Since 2011 improved accident tolerant fuels (ATF) and claddings have been a...
1 Datensatz
NSUF 18-CINR-14787: High-dose ion irradiation testing and relevant post-irradiation examination of friction-stir-welded ODS MA956 alloy ansehen -
NSUF 18-CINR-14788: Irradiation Testing of Materials Produced by Additive Friction Stir Manufacturing
The purpose of this work is to perform irradiation and post-irradiation...
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NSUF 18-CINR-14788: Irradiation Testing of Materials Produced by Additive Friction Stir Manufacturing ansehen -
NSUF 18-LIBSUB1: Library Submission of Neutron-Interactions of Advanced Materials
Neutron-Interactions of Advanced Materials: project is aimed at neutron...
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NSUF 18-LIBSUB1: Library Submission of Neutron-Interactions of Advanced Materials ansehen -
NSUF 19-1541: Ion Irradiation for High Fidelity Simulation of High Dose Neutron Irradiation
The promise for developing new, advanced nuclear reactor concepts that...
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NSUF 19-1541: Ion Irradiation for High Fidelity Simulation of High Dose Neutron Irradiation ansehen -
NSUF 19-1619: Effect of laser weld repairs on deformation mechanisms of neutron irradiated austenitic steels
The objective of this project is to understand the change in deformation...
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NSUF 19-1619: Effect of laser weld repairs on deformation mechanisms of neutron irradiated austenitic steels ansehen -
NSUF 19-1621: In-situ separate effect studies of thermal and radiation effects on Xe diffusion in alpha-U and U-10Zr.
The proposed Rapid Turnaround Experiment aims at clarifying Xe diffusion in...
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NSUF 19-1621: In-situ separate effect studies of thermal and radiation effects on Xe diffusion in alpha-U and U-10Zr. ansehen -
NSUF 19-1624: Critical Evaluation of Solute Segregation and Precipitation Across Damage Rates in Dual Ion Irradiated T91 Steel
Prediction of material response to high irradiation damage levels is a key...
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NSUF 19-1624: Critical Evaluation of Solute Segregation and Precipitation Across Damage Rates in Dual Ion Irradiated T91 Steel ansehen -
NSUF 19-1632: On Surprising Dose Rate Effects in Neutron Irradiated Fe-Cr Alloys: A TEM Study of Composition Effects at DPA Rates that Vary by Only a Factor of 4
It is essential to be able to replicate the neutron damage expected within...
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NSUF 19-1632: On Surprising Dose Rate Effects in Neutron Irradiated Fe-Cr Alloys: A TEM Study of Composition Effects at DPA Rates that Vary by Only a Factor of 4 ansehen -
NSUF 19-1634: Bubble formation of in-situ He-implanted 14YWT and CNA advanced nanostructured ferritic alloys
Helium in irradiated materials can cause low-temperature hardening, void...
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NSUF 19-1634: Bubble formation of in-situ He-implanted 14YWT and CNA advanced nanostructured ferritic alloys ansehen -
NSUF 19-1635: Atom probe tomography study of the fuel cladding chemical interaction (FCCI) layer in irradiated U-10Zr fuel with HT-9 cladding
This project aims to understand the fuel cladding chemical interaction (FCCI)...
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NSUF 19-1635: Atom probe tomography study of the fuel cladding chemical interaction (FCCI) layer in irradiated U-10Zr fuel with HT-9 cladding ansehen -
NSUF 19-1636: Changes in mechanical and chemical-structural properties of gamma irradiated calcium silicate hydrates to an absorbed dose of 200 MGy with respect to pristine samples
The proposed project objectives are to study the changes in viscoelastic...
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NSUF 19-1636: Changes in mechanical and chemical-structural properties of gamma irradiated calcium silicate hydrates to an absorbed dose of 200 MGy with respect to pristine samples ansehen -
NSUF 19-1644: Impact of grain boundary mobility on fission gas bubble distribution of ion-irradiated monolithic U-Mo fuel
It has been postulated that fission gas bubble growth and distribution is...
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NSUF 19-1644: Impact of grain boundary mobility on fission gas bubble distribution of ion-irradiated monolithic U-Mo fuel ansehen -
NSUF 19-1648: In-Situ SEM Irradiation Enhanced Creep Studies of 14 YWT
The development of in-situ SEM heated instrumented tensile and compression...
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NSUF 19-1648: In-Situ SEM Irradiation Enhanced Creep Studies of 14 YWT ansehen -
NSUF 19-1649: 3D Microstructure Reconstruction of the Peripheral Region of MOX FBR Fuel
The structural and chemical components of a fuel are important aspects to...
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NSUF 19-1649: 3D Microstructure Reconstruction of the Peripheral Region of MOX FBR Fuel ansehen -
NSUF 19-1652: Local Deformation Mechanism of Neutron-Irradiated NF709 Austenitic Stainless Steel
This proposal is a follow-up to our previously awarded NSUF-RTE proposal...
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NSUF 19-1652: Local Deformation Mechanism of Neutron-Irradiated NF709 Austenitic Stainless Steel ansehen -
NSUF 19-1659: ChemiSTEM study of Nb redistribution in M5 irradiated at high burnup
We propose to study the Nb redistribution in terms of microstructure and...
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NSUF 19-1659: ChemiSTEM study of Nb redistribution in M5 irradiated at high burnup ansehen