Degradation of a Ni-Cr-Fe alloy in a pressurised-water nuclear power plant
Degradacija zlitin Ni-Cr-Fe v tlačnovodnih jedrskih elektrarnah

english

2011

volume 45, issue 2

Inštitut za kovinske materiale in tehnologije
(Obvezni izvod spletne publikacije)

In the early days of pressurized-water nuclear-power-plant design Ni-based alloys were selected because of their good mechanical properties and corrosion resistance. Alloy 600 was used for some reactor-coolant pressure-boundary components and Alloy 82/182 was used for welds. Industrial experience in the past three decades has shown that Alloy 600 components and Alloy 82/182 welds are susceptible to primary-water stress-corrosion cracking (PWSCC). PWSCC is the intergranular or transgranular cracking due to the combined action of stresses, temperatures and components in contact with the primary water (reactor coolant). PWSCC leaks and cracks were detected on the reactor-coolant pressure-boundary components. In this work some characteristics of the Alloy 600 and Alloy 82/182 welds and their PWSCC degradation are presented.

27.02.2012