The effect of matrix chemistry on dislocation evolution in an irradiated Zr alloy

Author:

Harte A.,Jädernäs D.,Topping M.,Frankel P.,Race C.P.,Romero J.,Hallstadius L.,Darby E.C.,Preuss M.

Funder

EPSRC Leadership Fellowship

Westinghouse, Studsvik and Rolls-Royce plc

Publisher

Elsevier BV

Subject

Metals and Alloys,Polymers and Plastics,Ceramics and Composites,Electronic, Optical and Magnetic Materials

Reference76 articles.

1. Cladding for high performance fuel;Hallstadius;Prog. Nucl. Energy,2012

2. Post-irradiation characterization of ultra-high fluence zircaloy-2, Zircon;Mahmood;Nucl. Ind. Twelfth Int. Symp. ASTM STP,2000

3. Review of deformation mechanisms, texture, and mechanical anisotropy in zirconium and zirconium base alloys;Tenckhoff;Zircon. Nucl. Ind. 14th Symp.,2005

4. Properties of Reactor Materials and the Effects of Irradiation Damage;Buckley,1961

5. Dislocation bias in an anisotropic diffusive medium and irradiation growth;Woo;J. Nucl. Mater.,1983

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