Projects
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NSUF 18-1553: In-situ high temperature Transmission Electron Microscopy (TEM) of radiogenic He in high burnup fast reactor MOX
The fuel cross-section mount for the present study will be retrieved,...
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뷰 NSUF 18-1553: In-situ high temperature Transmission Electron Microscopy (TEM) of radiogenic He in high burnup fast reactor MOX -
NSUF 18-1556: TEM Characterization of High Burnup MOX Fuel
MOX fuels offer the potential to power next generation nuclear reactors,...
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뷰 NSUF 18-1556: TEM Characterization of High Burnup MOX Fuel -
NSUF 18-1558: In-situ investigation of the Threshold Incubation Dose for the formation of c-component loops in additively manufactured and powder metallurgy rolled Ti-6Al-4V
In-situ TEM irradiation offers the unique capability to investigate the...
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뷰 NSUF 18-1558: In-situ investigation of the Threshold Incubation Dose for the formation of c-component loops in additively manufactured and powder metallurgy rolled Ti-6Al-4V -
NSUF 18-1561: Grain Size Effects on He and Xe behavior in UO2 and ThO2
It has been reported that radiation tolerance of materials increases as the...
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뷰 NSUF 18-1561: Grain Size Effects on He and Xe behavior in UO2 and ThO2 -
NSUF 18-1565: Characterization of 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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뷰 NSUF 18-1565: Characterization of Radiation Tolerance of Advanced Joining Techniques for Oxide Dispersion Strengthened Steels under Ion Irradiation -
NSUF 18-1566: In-situ TEM deformation of neutron irradiated FeCrAl alloys
The objectives of this in-situ TEM study on neutron irradiated FeCrAl-based...
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뷰 NSUF 18-1566: In-situ TEM deformation of neutron irradiated FeCrAl alloys -
NSUF 18-1570: Phase Evolution of Uranium-Zirconium Alloys Under In-Situ TEM Heating
The binary uranium-zirconium (U-Zr) and the ternary uranium-plutonium-...
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뷰 NSUF 18-1570: Phase Evolution of Uranium-Zirconium Alloys Under In-Situ TEM Heating -
NSUF 18-1584: Understanding the local atomic structure in variable composition, irradiated perovskites
Ceramics have varying uses across the nuclear industry, and have been...
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뷰 NSUF 18-1584: Understanding the local atomic structure in variable composition, irradiated perovskites -
NSUF 18-1589: Irradiation Damage in (Hf0.2Zr0.2Ta0.2Nb0.2Ti0.2)C High-Entropy Ceramics
The objective of this project is examine the irradiation damage behavior in...
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뷰 NSUF 18-1589: Irradiation Damage in (Hf0.2Zr0.2Ta0.2Nb0.2Ti0.2)C High-Entropy Ceramics -
NSUF 18-1590: 3D Microstructural Assessment of Irradiated and Control U-10Zr Fuels
Mechanistic Fuel Failure-3 (MFF-3) include U-10wt%Zr (U-10Zr) fuels that are...
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뷰 NSUF 18-1590: 3D Microstructural Assessment of Irradiated and Control U-10Zr Fuels -
NSUF 18-1593: Understand the Fission Products Behavior and Irradiation Effects in UCO Fuel Kernels of Irradiated AGR-1 and AGR-2 TRISO Fuel Particles by Using Atom Probe Tomography
TRISO-coated particle fuel is a center piece in developing the high...
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뷰 NSUF 18-1593: Understand the Fission Products Behavior and Irradiation Effects in UCO Fuel Kernels of Irradiated AGR-1 and AGR-2 TRISO Fuel Particles by Using Atom Probe Tomography -
NSUF 18-1596: Micro-structural investigation of the pore structure of uncrept and crept irradiated PCEA graphite specimens with SEM and FIB tomography
Graphite has been proposed as a moderator material for the Very High...
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뷰 NSUF 18-1596: Micro-structural investigation of the pore structure of uncrept and crept irradiated PCEA graphite specimens with SEM and FIB tomography -
NSUF 18-1600: Investigation of Ag, Pd, I, Ru, and Sr fission products in bulk and grain boundaries of neutron irradiated SiC
A series of irradiation experiments have been carried out on tristructural...
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뷰 NSUF 18-1600: Investigation of Ag, Pd, I, Ru, and Sr fission products in bulk and grain boundaries of neutron irradiated SiC -
NSUF 18-1603: APT Characterization of RPV Steels from the UCSB ATR-2 Neutron Irradiation Experiment
We propose to use APT to characterize of a set of key RPV alloys to build on...
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뷰 NSUF 18-1603: APT Characterization of RPV Steels from the UCSB ATR-2 Neutron Irradiation Experiment -
NSUF 18-1606: Neutron Irradiation and Activation of Fe, Co and Ni Aerosol Jet Printed Structures
A fundamental challenge that this project intends to explore is the...
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뷰 NSUF 18-1606: Neutron Irradiation and Activation of Fe, Co and Ni Aerosol Jet Printed Structures -
NSUF 18-1610: IVEM Investigation of Defect Evolution in Bulk High Entropy Alloys under Single- and Dual-beam Heavy-ion Irradiation
The proposed study will investigate the microstructural evolution under...
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뷰 NSUF 18-1610: IVEM Investigation of Defect Evolution in Bulk High Entropy Alloys under Single- and Dual-beam Heavy-ion Irradiation -
NSUF 18-671: Radiation-Induced Changes to the Nanometer-Sized Pores in Fine-Grained Nuclear Graphite
Graphite is a critical material for the deployment of multiple Generation-IV...
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뷰 NSUF 18-671: Radiation-Induced Changes to the Nanometer-Sized Pores in Fine-Grained Nuclear Graphite -
NSUF 18-CINR-14704: Facilitating MARMOT Modeling of Radiation Phenomena in U-Pu-Zr fuels through experiments (MORPH experiment)
The objectives of this proposal are to increase fundamental understanding of...
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뷰 NSUF 18-CINR-14704: Facilitating MARMOT Modeling of Radiation Phenomena in U-Pu-Zr fuels through experiments (MORPH experiment) -
NSUF 18-CINR-14717: Rapid Simulation of Irradiation Damage in PWR Internals
A significant portion of Pressurized Water Reactor (PWR) core internals, such...
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뷰 NSUF 18-CINR-14717: Rapid Simulation of Irradiation Damage in PWR Internals -
NSUF 18-CINR-14730: HIgh-performance nanostructured thermoelectric materials and generators for in-pile harvesting
The project goal is to develop irradiation-resistant nanostructured...
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뷰 NSUF 18-CINR-14730: HIgh-performance nanostructured thermoelectric materials and generators for in-pile harvesting