Projects
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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 19-1632: 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 19-1634: 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 19-1635: 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 19-1636: 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 19-1644: 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 19-1648: 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 19-1649: 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 19-1652: 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 19-1659: 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 19-1663: Ion irradiation of ThO2 and UO2 single crystals
The technical objective of this RTE is to generate dislocation loop dominated...
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NSUF 19-1665: Defect Clustering in 316H Stainless Steel and High Entropy Alloy Under In-situ Irradiation at 600-700°C
Despite the promising results about the irradiation resistance of high...
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NSUF 19-1666: Nanoindentation of Phases in Irradiated and Control U-10Zr Fuels
A subset of the Mechanistic Fuel Failure-3 (MFF-3) irradiations included...
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NSUF 19-1670: A study of the tensile response of HT-9 alloys following ATR irradiation to doses between 0.01 and 10 dpa at 300, 450 and 550C
The objective of this program is to investigate the tensile properties of...
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NSUF 19-1672: Microstructure characterization on neutron irradiated and post-tensile duplex stainless steels
The work is planned to systemically understand the microstructural evolution...
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NSUF 19-1674: Radiation tolerance of Ln3TaO7 weberite-type nuclear waste matrix materials
In this project, 1 MeV Kr ions will be used to irradiate La3TaO7, Sm3TaO7,...
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NSUF 19-1676: Thermal diffusivity and microstructure analysis of in-core molten salt irradiated graphite
From the success of the Molten Salt Reactor Experiment (MSRE) operated at Oak...
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NSUF 19-1680: In-situ small-scale mechanical testing of fast reactor advance metallic fuel alloy.
The main objective of this project is the determination of hardness, elastic...
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NSUF 19-1681: Effects of dose and temperature on microstructural evolution of Zircaloy-4 alloys during proton irradiation
Proton irradiation is commonly used to mimic neutron irradiation since it is...
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NSUF 19-1683: Resolving the Puzzle of Flux Effects on High Fluence Precipitation and Embrittlement of RPV Steels
This proposal covers characterization 5 alloys by Atom Probe Tomography (APT)...
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