Items where Author is "Stratton, R P"

SMITH, Alan and STRATTON, R P (1991). Thermal treatment, grain boundary composition and intergranular attack resistance of alloy 690. In: Proceedings of the fifth international symposium on environmental degradation of materials in nuclear power system water reactors. La Grange Park, Illinois, American Nuclear Society, 855-861.

SMITH, Alan and STRATTON, R P (1990). Relationship between composition, microstructure and corrosion behaviour of alloy 690 steam generator tubing for PWR systems. In: CUBICCIOTTI, D, (ed.) Proceedings of the fourth international symposium on environmental degradation of materials in nuclear power systems - water reactors. Houston, Texas, National association of corrosion engineers.