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Accession Number
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DE2012-1041194
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Title
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Multiscale Simulation of Thermo-Mechanical Processes in Irradiated Fission-Reactor Materials.
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Publication Date
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May 2012
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Media Count
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6p
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Personal Author
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A. El-Azab
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Abstract
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The phase field model development effort aimed to foster collaboration in the area of mesoscale modeling of irradiation-induced microstructure evolution in reactor materials, with emphasis on bringing the phase-field modeling capabilities into this important field. The model problem chosen for this collaboration among three CMSN team members is the problem of nucleation and growth of voids. Like all other microstructure and microchemical evolution processes in irradiated materials, especially alloys, void nucleation and growth is driven by the intense generation of point defects under neutron irradiation, and by the long-range diffusion and interactions of these defects.
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Keywords
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Alloys
Diffusion
Irradiation
Microstructure
Neutrons
Nucleation
Point defects
Reactor materials
Thermomechanical processes
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Source Agency
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Technical Information Center Oak Ridge Tennessee
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NTIS Subject Category
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77J - Reactor Materials
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Corporate Author
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Purdue Univ., West Lafayette, IN.
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Document Type
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Technical report
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Title Note
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N/A
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NTIS Issue Number
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1307
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Contract Number
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DE-FG02-07ER46367
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