This paper compares stress corrosion crack growth rates measured in the laboratory with stress corrosion crack growth rates derived from field experience in three different applications of the power generating industry: Pressurized water reactor (PWR) pressure vessel head penetrations with alloy 600, boiling water reactor (BWR) and RBMK (the Russian, watercooled graphite moderated channel-type power reactor, for example Chernobyl) welded nuclear reactor coolant pipes with stabilized stainless steels, and generator rotor retaining rings made from a high strength austenitic steel. It is shown that the minimum time to failure in service can well be predicted from Iaboratoty crack growth rate tests. Keywords: Stress corrosion cracking, crack growth rate, service experience, alloy 600, austenitic steel.