Creep-fatigue interaction of inconel 617 at 950°C in simulated nuclear reactor helium

Strain-controlled fatigue tests have been conducted in impure helium, simulating the primary-circuit coolant of a high temperature gas-cooled reactor to ascertain the influence of strain rate (ε̇ = 4 × 10−3 to 2 × 10−5 s−1), hold condition at peak strains (tension-only, compression-only and tension-plus-compression holds) and hold time (up to 120 min) on the low cycle fatigue behaviour of Inconel 617. A strain range of 0.6% and a temperature of...