Steels for Fission and Fusion Nuclear-Reactors
Elongation of Irradiated Steels
Optimisation of fusion experiments
Charpy properties of irradiated steel
Introduction to fusion power plant materials
Design of new Fe-9CrWV reduced-activation martensitic steels for creep properties at 650°C
Analysis of Irradiation Hardening in Low-Activation Steels
Practical Mechanically Alloyed ODS Iron-base and Nickel-base Alloys
Void nucleation in irradiated materials
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Bainite
Martensite
Widmanstätten ferrite
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