Projects
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NSUF 18-1243: Microstructural Phase Characterization of Irradiated and Control U-10Zr Fuels
Mechanistic Fuel Failure-3 (MFF-3) consists of U-10wt%Zr fuels that are...
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NSUF 18-1243: Microstructural Phase Characterization of Irradiated and Control U-10Zr Fuels -г харах -
NSUF 18-1245: Radiation response of nanostructured steels with various types of defect sinks
Radiation response of nanostructured steels with various types of defect...
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NSUF 18-1245: Radiation response of nanostructured steels with various types of defect sinks -г харах -
NSUF 18-1253: Understanding the role of grain boundary character in segregation behavior of solute elements in neutron irradiated 304 SS using Atom Probe Tomography.
This project represents a critical step toward understanding quantitative...
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NSUF 18-1253: Understanding the role of grain boundary character in segregation behavior of solute elements in neutron irradiated 304 SS using Atom Probe Tomography. -г харах -
NSUF 18-1254: Characterization of grain boundaries of Alloy X-750 irradiated in EBR-II
The development of a quantitative relationship between microchemistry and...
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NSUF 18-1254: Characterization of grain boundaries of Alloy X-750 irradiated in EBR-II -г харах -
NSUF 18-1255: Ion irradiation of Aerosol Jet Printed Cu, Ag, and Ni Structures
To demonstrate the feasibility of AJP in the nuclear industry, our focus will...
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NSUF 18-1255: Ion irradiation of Aerosol Jet Printed Cu, Ag, and Ni Structures -г харах -
NSUF 18-1256: Fission Product Distribution Comparison in Irradiated and Safety Tested AGR-1 and AGR-2 TRISO Fuel Particles
TRISO-coated fuel is an important piece of developing new generation...
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NSUF 18-1256: Fission Product Distribution Comparison in Irradiated and Safety Tested AGR-1 and AGR-2 TRISO Fuel Particles -г харах -
NSUF 18-1257: Understand the Fission Products Behavior and Irradiation Effects in UCO Fuel Kernels of Irradiated AGR-1 and AGR-2 TRISO Fuel Particles Using Titan Themis 200 with ChemiSTEM Capability
TRISO-coated particle fuel is a center piece in developing the high...
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NSUF 18-1257: Understand the Fission Products Behavior and Irradiation Effects in UCO Fuel Kernels of Irradiated AGR-1 and AGR-2 TRISO Fuel Particles Using Titan Themis 200 with ChemiSTEM Capability -г харах -
NSUF 18-1262: In Situ Straining of 10-dpa Neutron Irradiated Austenitic Stainless Steels using Scanning Electron Microscope Electron Backscatter Diffraction
The proposed experiment will consist in manufacturing and preparing three...
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NSUF 18-1262: In Situ Straining of 10-dpa Neutron Irradiated Austenitic Stainless Steels using Scanning Electron Microscope Electron Backscatter Diffraction -г харах -
NSUF 18-1270: Microstructural examination of in-situ tensile creep SiC specimen irradiated in the Halden reactor
This proposed work will include TEM observation of irradiation induced...
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NSUF 18-1270: Microstructural examination of in-situ tensile creep SiC specimen irradiated in the Halden reactor -г харах -
NSUF 18-1276: Towards characterizing the microstructural evolution in nuclear fuel via neutron diffraction
The objective of this project is to characterize an aspect of the...
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NSUF 18-1276: Towards characterizing the microstructural evolution in nuclear fuel via neutron diffraction -г харах -
NSUF 18-1277: Interfacial Effects, Damage and Recovery in Binary Carbides
Through the application of in situ examination of induced radiation damage...
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NSUF 18-1277: Interfacial Effects, Damage and Recovery in Binary Carbides -г харах -
NSUF 18-1282: In-situ High Temperature Ion Irradiation Transmission Electron Microscopy to Understand Fission Product Transport in Silicon Carbide of TRISO Fuel
The overall goal of this project is to demonstrate the use of in-situ...
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NSUF 18-1282: In-situ High Temperature Ion Irradiation Transmission Electron Microscopy to Understand Fission Product Transport in Silicon Carbide of TRISO Fuel -г харах -
NSUF 18-1295: Reactor Hot Cell Laboratory Upgrades to Support the Integrated Nuclear Fuel and Structural Materials Research Center at the University of Florida Training Reactor
None
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NSUF 18-1295: Reactor Hot Cell Laboratory Upgrades to Support the Integrated Nuclear Fuel and Structural Materials Research Center at the University of Florida Training Reactor -г харах -
NSUF 18-1297: A Dedicated Laboratory for Radioactive Sample Handling
None
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NSUF 18-1297: A Dedicated Laboratory for Radioactive Sample Handling -г харах -
NSUF 18-1298: Increase Our Understanding of the Maryland University Training Reactor Core
None
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NSUF 18-1298: Increase Our Understanding of the Maryland University Training Reactor Core -г харах -
NSUF 18-1299: University Reactor Upgrades Infrastructure Support for: MITR Modular Hot Cells for Post-Irradiation Examination
None
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NSUF 18-1299: University Reactor Upgrades Infrastructure Support for: MITR Modular Hot Cells for Post-Irradiation Examination -г харах -
NSUF 18-1301: Establishing a Hot Cell Capability at the Pulstar Reactor
None
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NSUF 18-1301: Establishing a Hot Cell Capability at the Pulstar Reactor -г харах -
NSUF 18-1302: General Reactor Safety Improvement at Missouri S&T Reactor
None
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NSUF 18-1302: General Reactor Safety Improvement at Missouri S&T Reactor -г харах -
NSUF 18-1307: Upgrades for MURR Reactor Control and In-Pool Maintenance Operations
None
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NSUF 18-1307: Upgrades for MURR Reactor Control and In-Pool Maintenance Operations -г харах -
NSUF 18-1309: Reactor Control Console Upgrade for the University of Utah TRIGA Reactor
None
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NSUF 18-1309: Reactor Control Console Upgrade for the University of Utah TRIGA Reactor -г харах