Projects
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NSUF 17-1043: Microstructural characterization of 21% burn-up MOX fuel
Attaining fundamental understanding of fuel performance requires detailed...
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NSUF 17-1047: Examining microstructural differences in irradiated HT9, correlated with differences in processing prior to irradiation
The goal of this project is to do an examination of the irradiated...
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NSUF 17-1052: Study of the factors affecting the radiation tolerance of MAX phases for innovative fuel cladding concepts
This project aims at understanding the factors affecting the radiation...
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NSUF 17-1055: Post-irradiation observation following high-rate self-ion irradiation of previously neutron-irradiated 304 stainless steel
The project aims to combine two types of irradiation to forecast the behavior...
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NSUF 17-1065: Fundamental Study of Alloying Complexity Effects on the Irradiation Process in High Entropy Alloys
High entropy alloys (HEAs) have attracted wide attention for its potential...
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NSUF 17-1066: Changes on viscoelastic behavior, morphology and chemical structure of gamma irradiated calcium silicate hydrates to 1.94 MGy with respect to non-irradiated samples
The proposed project objectives are to study the changes in viscoelastic...
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NSUF 17-1069: Atomic Probe Tomography Studies of Irradiated Cold Spray Coatings for Accident Tolerant Cladding
The goal of the proposed RTE research, led by the University of Wisconsin,...
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NSUF 17-1073: Ion irradiation response of nanostructured alloys: In-situ TEM observations vs. ex-situ characterization
In-situ transmission electron microscopy (TEM) combined with ion irradiation...
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NSUF 17-1076: Characterization of Grain Boundary Damage in Highly Irradiated Specimens Exposed to Irradiation Assisted Stress Corrosion Cracking.
The objective of this work is to quantify, at the microscopic scale, the...
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NSUF 17-1080: Post-irradiation analysis of hybrid metallic coatings on SiC after neutron irradiation 290-330°C
The objective of the project is to examine and understand the post-...
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NSUF 17-1081: Microstructure and microchemical characterization of neutron and proton irradiated Alloy D9 using APT and TEM
The objective of this study is to understand the effect of irradiation on the...
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NSUF 17-1090: In situ amorphization studies of forsterite, diopside and quartz under ion irradiation
The proposed project objectives are to redefine the critical ion doses for...
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NSUF 17-1091: Characterize the Irradiated Microstructure and Understand the Fission Product Behavior in an Irradiated and Safety Tested AGR-1 TRISO Fuel Particle New Proposal
TRISO-coated particle fuel is a center piece in developing the high...
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NSUF 17-1092: Effect of Phosphorous (P) on precipitation and segregation behavior in neutron irradiated Reactor Pressure Vessel steels in the Advanced Test Reactor (ATR-2): An Atom Probe study.
The objective of this study is to understand the effect of Phosphorous (P) on...
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View NSUF 17-1092: Effect of Phosphorous (P) on precipitation and segregation behavior in neutron irradiated Reactor Pressure Vessel steels in the Advanced Test Reactor (ATR-2): An Atom Probe study. -
NSUF 17-1093: AsTeROID (follow-on AsTeR (Advanced Test Reactor) project to Optimize hydrogen-assisted Irradiation growth and Dimensional stability)
The scientific objective of this project is to develop a better understanding...
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NSUF 17-1098: An in-situ TEM characterization of tensile testing of ion irradiated HT-UPS steel at RT and 400°C
The objective of this research is to develop an understanding of the...
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NSUF 17-1099: In Situ Transmission Electron Microscopy Study of Radiation Damage Effects on the d-Hydride Microstructure in Irradiated Zircaloy-4
Hydride formation is one of the major embrittling mechanisms for zirconium-...
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NSUF 17-1104: Radiation tolerance of Mn+1AXn phase nuclear fuel cladding materials
In this project, 1 MeV Kr ions will be used to irradiate Ti2AlC, Cr2AlC,...
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NSUF 17-1105: The effectiveness of coherent and incoherent twin boundaries in alleviating radiation damage in heavy-ion-irradiated 316L austenitic stainless steels
The proposed experiment will consist in carrying out TEM in-situ ion...
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View NSUF 17-1105: The effectiveness of coherent and incoherent twin boundaries in alleviating radiation damage in heavy-ion-irradiated 316L austenitic stainless steels -
NSUF 17-1115: Heavy ion irradiation and ex situ transmission electron microscopy study of the effectiveness of twin boundaries in alleviating radiation damage in 316 austenitic stainless steels
Interfaces can act as radiation defect sinks and thus reduce defect density...
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