Background:In super-critical water-cooled reactor

creep-fatigue under high working temperature will affect life of various equipments.Purpose:Understanding characteristics of creep-fatigue interaction correlation is important before evaluating its damage by ASME code.Methods:In order to study creep-fatigue interaction of 316 stainless steel（316SS）

three types of creep-fatigue interaction have been taken into consideration in our experiments

which include traditional creep-fatigue interaction subjected to cycling load with hold times at its peak and also creep-fatigue interaction by decoupling creep and fatigue load.Based on the experimental data

the different types of creep-fatigue interaction have been compared and discussed.Moreover

suitability of ASME NH rules in assessing various creep-fatigue interactions of 316SS produced in China is investigated.Results:Creep-fatigue damage envelop of 316SS from ASME can cover the experimental results from the three types of experiments mentioned above.Conclusions:This experimental study is useful as a reference in creep-fatigue interaction experiments

application of ASME code and study of mechanical characteristic of high temperature structural materials in generation IV nuclear power plant.