R.W. Gilbert

Recent developments in stainless steels

Accident tolerant fuels for LWRs: A perspective

The effects of stress, temperature and hydrogen content on hydride-induced crack growth in Zr-2.5 Pct Nb

The effect of hydrogen on dislocation dynamics

Hydrogen Embrittlement Understood

Hydrogen embrittlement of α titanium: In situ tem studies

Extreme grain refinement by severe plastic deformation: A wealth of challenging science

Mechanisms of hydrogen induced delayed cracking in hydride forming materials

Experimental and Modeling Approach of Irradiation Defects Recovery in Zirconium Alloys: Impact of an Applied Stress

Microstructure dependence of irradiation creep and growth of zirconium alloys

Structural materials for fission & fusion energy

Hydrogen-enhanced localized plasticity—a mechanism for hydrogen-related fracture

Recycled aggregate from C&D waste & its use in concrete – A breakthrough towards sustainability in construction sector: A review

Anisotropic irradiation creep of zircaloy-2

Low cycle fatigue behaviour in vacuum of a 316L-type austenitic stainless steel between 20 and 600°C—Part II: Dislocation structure evolution and correlation with cyclic behaviour

Enhanced radiation tolerance of ultrafine grained Fe–Cr–Ni alloy

Modeling irradiation growth of zirconium and its alloys

Hydrogen interactions with defects in crystalline solids

Materials challenges in nuclear energy

Microencapsulated fuel technology for commercial light water and advanced reactor application

Wetting and spreading

〈〉 Component dislocations in annealed Zircaloy irradiated at about 570 K

Some comments on damage alignment in neutron-irradiated zirconium alloys

Dislocation loop generation and irradiation growth in a zirconium single crystal

Hydrides in zirconium-2.5 wt. % niobium alloy pressure tubing

The precipitation of γ-deuterides (hydrides) in titanium

Grain boundary sinks in neutron-irradiated Zr and Zr-alloys

Characterization of neutron irradiation damage in zirconium alloys — an international “round-robin” experiment

Dislocations generated by zirconium hydride precipitates in zirconium and some of its alloys