Items where Author is "Stratton, R P"
Number of items: 2.
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.