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Accession Number DE2012-1041194
Title Multiscale Simulation of Thermo-Mechanical Processes in Irradiated Fission-Reactor Materials.
Publication Date May 2012
Media Count 6p
Personal Author A. El-Azab
Abstract 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.
Keywords Alloys
Point defects
Reactor materials
Thermomechanical processes

Source Agency Technical Information Center Oak Ridge Tennessee
NTIS Subject Category 77J - Reactor Materials
Corporate Author Purdue Univ., West Lafayette, IN.
Document Type Technical report
Title Note N/A
NTIS Issue Number 1307
Contract Number DE-FG02-07ER46367

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