Projects
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NSUF 17-CINR-13004: Capacitive Discharge Resistance Welding of 14YWT for Cladding Applications
The objectives of the proposed work are to join cladding tubes of nano-...
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NSUF 17-CINR-13088: Improved Understanding of Zircaloy-2 Hydrogen Pickup Mechanism in BWRs
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NSUF 17-CINR-13106: Radiation Effects on Zirconium Alloys Produced by Powder Bed Fusion Additive Manufacturing Processes
The goal of this project is to understand the effects of radiation on...
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NSUF 18-1130: Post-irradiation analysis at the nanoscale of 14YWT after high dose (16.6 dpa) neutron irradiation at 386C and 412C
The objective of this investigation is to perform detailed microstructural...
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NSUF 18-1134: Understanding the Mechanism of Thermal-Hydraulic Enhancement On Gamma Irradiated Nuclear Materials Interfaces
The impact of Radiation Induced Surface Activation (RISA) on Critical Heat...
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NSUF 18-1144: In situ investigation of the thermomechanical performance of HCP metals and Zircaloy-4 under ion beam irradiation
In recent years, significant advances have been made in the use of ion beams...
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NSUF 18-1146: Micro-mechanical characterization of long range order in Ni-Cr alloys and their response to radiation damage
Separate effects testing will be performed on unaged, thermally aged and...
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NSUF 18-1151: Electron Tomography for Three-Dimensional Characterization of Intragranular Fission Product Transport in Neutron-Irradiated Silicon Carbide in TRISO Fuel
The overall goal of this project is to demonstrate the use of electron...
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NSUF 18-1156: Mechanical characterization of three heats (ORNL, LANL and EBR II) of HT-9 after side-by-side neutron irradiation at LWR and fast reactor relevant temperatures
HT-9 is being considered as a candidate structural material for fast,...
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NSUF 18-1157: Understanding the mechanism for mesopore development in irradiated graphite by high resolution gas adsorption measurements (N2 and Kr at 77 K)
High resolution gas adsorption (N2 and Kr) at 77 K will be used to...
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NSUF 18-1162: Pair distribution function analysis on recovery of irradiation induced defects in SiC
Recently, through an Advanced Fuel Campaign and NSUF RTE sponsored research...
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NSUF 18-1163: Evaluation of Irradiated Cr Coatings on Zirconium Alloys
The Westinghouse Accident Tolerant Fuel (ATF) utilizes 20 to 30 micron thick...
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NSUF 18-1165: Elevated Temperature In-situ SEM micro compression of UO2
Micro compression pillars will be used to measure the yield stress and...
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NSUF 18-1168: TEM in situ 4-point bend fracture testing of irradiated ODS alloys
The objective of this work is to evaluate fracture properties of irradiated...
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NSUF 18-1176: Atom Probe Tomography Investigations of nm-Scale Precipitates in Reactor Pressure Vessel Steels in the UCSB Advanced Test Reactor (ATR-2) Neutron Irradiation Experiment
This proposal covers APT characterization of a set of key RPV alloys to build...
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NSUF 18-1177: Atom probe tomography of fission gas bubble superlattice in U-Mo fuel
It has been postulated that bubble superlattice is an effective mechanism to...
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NSUF 18-1178: In situ study of “rim effect” microstructure modification of nuclear fuels (resubmitted)
[With the positive reviewers' comments from previous RTE call, this proposal...
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NSUF 18-1179: Microstructural characterization of ~7% burn-up MOX fuel
Attaining fundamental understanding of fuel performance requires detailed...
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NSUF 18-1181: In situ TEM observation of microstructural evolution of silicon carbide (SiC)-nanostructured ferritic alloy (NFA) composite under high temperature ion irradiation
Methods: This proposal is to use the Intermediate Voltage Electron Microscopy...
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NSUF 18-1192: Synchrotron X-ray Characterization of the Microstructural Evolution of U Alloys Irradiated to Low Fluences
Metallic fuels are relevant to many reactor types, including advanced...
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