This resource encapsulates an international forum, co-sponsored by TMS, the American Nuclear Society, and NACE, on the exchange of research results and reactor operating experiences associated with materials degradation in water-cooled nuclear power reactor systems. The 131 papers included cover degradation phenomena particular to the various reactor systems, BWRs, PWR primary and PWR secondary, as well as narrow topic areas, such as zircalloy and low alloy steels, and cross-cutting topics, such as nickel-base welds, irradiation effects, and irradiation assisted stress corrosion cracking. The subject of environmental effects in supercritical water is also covered.

The attachment below provides links to both abstracts and full papers.

T.R. Allen, P.J. King and L. Nelson, eds., 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors (Warrendale, PA: TMS, 2005).