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Multinivå-modellering av mekaniska egenskaper hos bestrålat Zr och ZrH

Contact person: Pär Olsson
Responsible: Pär Olsson
Partner: Studsvik Nuclear Corporation
Funding: KK-stifelsen
Timeframe: 2013-09-01 -- 2015-08-31
Faculty/Department: Faculty of Technology and Society, Department of Materials Science and Applied Mathematics

Due to their low thermal neutron capture cross section and good corrosion resistance, zirconium-base alloys are commonly used as fuel cladding material in the cores of nuclear power reactors. During the service life, the fuel cladding is constantly subjected to heavy bombardment of high energy neutrons, causing displacement cascades in the material which give rise to microstructural damage in the forms of vacancy and self-interstitial clusters and increased dislocation density. This causes a hardening of the material, which results in increased yield and ultimate stresses, loss of ductility and an irradiation induced deviation in the elastic properties.

The scope of this proposed project is to quantify the effects of irradiation on the mechanical properties of zirconium and zirconium hydrides. The project comprises two parts: modeling and experimental validation. The modeling will be conducted through atomic scale molecular dynamics simulations and quantum mechanical DFT calculations. The atomistic results will be validated experimentally through nanoindentation testing of irradiated samples.

 

 

 

Senast uppdaterad av Magnus Jando