Projects
-
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,...
Keine Datensätze
NSUF 18-1553: In-situ high temperature Transmission Electron Microscopy (TEM) of radiogenic He in high burnup fast reactor MOX ansehen -
NSUF 18-1556: TEM Characterization of High Burnup MOX Fuel
MOX fuels offer the potential to power next generation nuclear reactors,...
Keine Datensätze
NSUF 18-1556: TEM Characterization of High Burnup MOX Fuel ansehen -
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...
Keine Datensätze
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 ansehen -
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...
Keine Datensätze
NSUF 18-1561: Grain Size Effects on He and Xe behavior in UO2 and ThO2 ansehen -
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...
Keine Datensätze
NSUF 18-1565: Characterization of Radiation Tolerance of Advanced Joining Techniques for Oxide Dispersion Strengthened Steels under Ion Irradiation ansehen -
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...
Keine Datensätze
NSUF 18-1566: In-situ TEM deformation of neutron irradiated FeCrAl alloys ansehen -
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-...
Keine Datensätze
NSUF 18-1570: Phase Evolution of Uranium-Zirconium Alloys Under In-Situ TEM Heating ansehen -
NSUF 18-1584: Understanding the local atomic structure in variable composition, irradiated perovskites
Ceramics have varying uses across the nuclear industry, and have been...
Keine Datensätze
NSUF 18-1584: Understanding the local atomic structure in variable composition, irradiated perovskites ansehen -
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...
Keine Datensätze
NSUF 18-1589: Irradiation Damage in (Hf0.2Zr0.2Ta0.2Nb0.2Ti0.2)C High-Entropy Ceramics ansehen -
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...
Keine Datensätze
NSUF 18-1590: 3D Microstructural Assessment of Irradiated and Control U-10Zr Fuels ansehen -
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...
Keine Datensätze
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 ansehen -
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...
Keine Datensätze
NSUF 18-1596: Micro-structural investigation of the pore structure of uncrept and crept irradiated PCEA graphite specimens with SEM and FIB tomography ansehen -
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...
Keine Datensätze
NSUF 18-1600: Investigation of Ag, Pd, I, Ru, and Sr fission products in bulk and grain boundaries of neutron irradiated SiC ansehen -
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...
Keine Datensätze
NSUF 18-1603: APT Characterization of RPV Steels from the UCSB ATR-2 Neutron Irradiation Experiment ansehen -
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...
Keine Datensätze
NSUF 18-1606: Neutron Irradiation and Activation of Fe, Co and Ni Aerosol Jet Printed Structures ansehen -
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...
Keine Datensätze
NSUF 18-1610: IVEM Investigation of Defect Evolution in Bulk High Entropy Alloys under Single- and Dual-beam Heavy-ion Irradiation ansehen -
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...
Keine Datensätze
NSUF 18-671: Radiation-Induced Changes to the Nanometer-Sized Pores in Fine-Grained Nuclear Graphite ansehen -
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...
Keine Datensätze
NSUF 18-CINR-14704: Facilitating MARMOT Modeling of Radiation Phenomena in U-Pu-Zr fuels through experiments (MORPH experiment) ansehen -
NSUF 18-CINR-14717: Rapid Simulation of Irradiation Damage in PWR Internals
A significant portion of Pressurized Water Reactor (PWR) core internals, such...
Keine Datensätze
NSUF 18-CINR-14717: Rapid Simulation of Irradiation Damage in PWR Internals ansehen -
NSUF 18-CINR-14730: HIgh-performance nanostructured thermoelectric materials and generators for in-pile harvesting
The project goal is to develop irradiation-resistant nanostructured...
Keine Datensätze
NSUF 18-CINR-14730: HIgh-performance nanostructured thermoelectric materials and generators for in-pile harvesting ansehen