Publisher's Synopsis
This CD encapsulates an international forum 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. What makes this compilation of even greater value is the question–and–answer section following each paper, which represents the dialogue that occurred between the speaker and the audience of scientists and engineers from 15 countries. Professionals representing utilities, reactor vendors, regulators, national laboratories and universities will find this publication of great value.
