Projects
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NSUF 16-CINR-10432: Fission Product Transport in TRISO
This program will measure diffusion coefficients of fission products (FP) for...
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NSUF 16-CINR-10432: Fission Product Transport in TRISO ansehen -
NSUF 16-CINR-10468: Radial Heat Flux - Irradiation Synergism in SiC ATF Cladding
Synergism of neutron irradiation and high heat flux presents unique yet...
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NSUF 16-CINR-10468: Radial Heat Flux - Irradiation Synergism in SiC ATF Cladding ansehen -
NSUF 16-CINR-10480: Role of minor alloying elements on long range ordering in Ni-Cr alloys
High Cr, Ni-based alloys are an important class of structural materials due...
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NSUF 16-CINR-10480: Role of minor alloying elements on long range ordering in Ni-Cr alloys ansehen -
NSUF 16-CINR-10537: Enhancing irradiation tolerance of steels via nanostructuring by innovative manufacturing techniques
Equal-channel angular pressing (ECAP) and high-pressure torsion (HPT) are two...
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NSUF 16-CINR-10537: Enhancing irradiation tolerance of steels via nanostructuring by innovative manufacturing techniques ansehen -
NSUF 16-CINR-10584: Irradiation Performance Testing of Specimens Produced by Commercially Available Additive Manufacturing Techniques
The proposed project will collect first-ever irradiation performance data for...
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NSUF 16-CINR-10584: Irradiation Performance Testing of Specimens Produced by Commercially Available Additive Manufacturing Techniques ansehen -
NSUF 16-CINR-10696: Understand the phase transformation of thermal aged and neutron irradiated duplex stainless steels used in LWRs
Complemented by the TEM/APT studies and ex-situ mechanical tests on duplex...
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NSUF 16-CINR-10696: Understand the phase transformation of thermal aged and neutron irradiated duplex stainless steels used in LWRs ansehen -
NSUF 16-CINR-10737: Correlative Atom Probe and Electron Microscopy Study of Radiation Induced Segregation at Low and High Angle Grain Boundaries in Steels
A push currently exists to design materials capable of handling harsher...
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NSUF 16-CINR-10737: Correlative Atom Probe and Electron Microscopy Study of Radiation Induced Segregation at Low and High Angle Grain Boundaries in Steels ansehen -
NSUF 16-CINR-10764: Radiation-Enhanced Diffusion of Ag, Ag-Pd, Eu, and Sr in Neutron Irradiated PyC/SiC Diffusion Couples
The objective of the study is to investigate thermal diffusion and neutron...
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NSUF 16-CINR-10764: Radiation-Enhanced Diffusion of Ag, Ag-Pd, Eu, and Sr in Neutron Irradiated PyC/SiC Diffusion Couples ansehen -
NSUF 16-CINR-10834: Effect of Gamma Irradiation on the Microstructure and Mechanical Properties of Nano-modified Concrete
Motivation. Extending the service life and performance of used nuclear fuel...
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NSUF 16-CINR-10834: Effect of Gamma Irradiation on the Microstructure and Mechanical Properties of Nano-modified Concrete ansehen -
NSUF 16-CINR-639: Beamline Examination of a Hf-Al Metal-Matrix Composite Material
This project proposes to conduct post-irradiation examination of HfAl3 Al...
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NSUF 16-CINR-639: Beamline Examination of a Hf-Al Metal-Matrix Composite Material ansehen -
NSUF 16-SAM1: NSUF graphite and fiber optic irradiation
SAM-1 will consist of two research program experiments chosen by the NSUF...
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NSUF 16-SAM1: NSUF graphite and fiber optic irradiation ansehen -
NSUF 17-1001: APT and TEM study of redistribution of alloying elements in ZrNb alloys following proton irradiation: effects on in-reactor corrosion kinetics.
We propose to study the effect of proton irradiation on Nb redistribution...
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NSUF 17-1001: APT and TEM study of redistribution of alloying elements in ZrNb alloys following proton irradiation: effects on in-reactor corrosion kinetics. ansehen -
NSUF 17-1014: Radiation-Hardening and Microstructural Stability of NF709 Austenitic Stainless Steel
Austenitic stainless steel NF709 has been down-selected for development as a...
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NSUF 17-1014: Radiation-Hardening and Microstructural Stability of NF709 Austenitic Stainless Steel ansehen -
NSUF 17-1016: Site-specific Atom Probe Tomography Characterisation of Grain Boundaries in Archival Surveillance Steels From Advanced Test Reactor (ATR-2) Neutron Irradiation Experiment
This proposal focuses on the site-specific characterisation, via atom probe...
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NSUF 17-1016: Site-specific Atom Probe Tomography Characterisation of Grain Boundaries in Archival Surveillance Steels From Advanced Test Reactor (ATR-2) Neutron Irradiation Experiment ansehen -
NSUF 17-1023: Hardness profiling of ion irradiated 15-15Ti cladding steel using CSM nano-indentation
This work proposes CSM nano-indentation on self-ion irradiated 15-15Ti...
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NSUF 17-1023: Hardness profiling of ion irradiated 15-15Ti cladding steel using CSM nano-indentation ansehen -
NSUF 17-1025: Atom Probe Tomography Investigations of nm-Scale Precipitates in Advanced Reactor Pressure Vessel Super Clean Steels in the UCSB Advanced Test Reactor (ATR-2) Neutron Irradiation Experiment
This proposal covers characterization of a set of advanced RPV alloys by atom...
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NSUF 17-1025: Atom Probe Tomography Investigations of nm-Scale Precipitates in Advanced Reactor Pressure Vessel Super Clean Steels in the UCSB Advanced Test Reactor (ATR-2) Neutron Irradiation Experiment ansehen -
NSUF 17-1028: Microstructural Examination of Neutron Irradiated Al-HfAl3 Metal Matrix Composite Materials for Application to Neutron Spectrum Modification in Nuclear Reactors
Al-HfAl3 metal matrix composite (MMC) materials are under consideration for...
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NSUF 17-1028: Microstructural Examination of Neutron Irradiated Al-HfAl3 Metal Matrix Composite Materials for Application to Neutron Spectrum Modification in Nuclear Reactors ansehen -
NSUF 17-1029: Irradiation responses of ultrastrong nano precipitation martensite steel
The objective of this proposal is to study irradiation responses of a...
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NSUF 17-1029: Irradiation responses of ultrastrong nano precipitation martensite steel ansehen -
NSUF 17-1032: Radiation Tolerance of Advanced Joining Techniques for Oxide Dispersion Strengthened Steels under Ion Irradiation
The objective of this work is to examine the effect of high damage levels of...
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NSUF 17-1032: Radiation Tolerance of Advanced Joining Techniques for Oxide Dispersion Strengthened Steels under Ion Irradiation ansehen -
NSUF 17-1033: Pore size distribution in U-Mo fuel irradiated to low burnup
Attaining fundamental understanding of fuel performance requires detailed...
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NSUF 17-1033: Pore size distribution in U-Mo fuel irradiated to low burnup ansehen