Abstract
Type 316 stainless steel with low carbon and medium nitrogen composition gains large interest because of its selection as a main structural material of the demonstration fast breeder reactor plant. As a part of the efforts for collecting strength data for design use, the authors have been conducting various strength tests on two product forms of this steel manufactured by hot-rolling and forging process, respectively. Using the results of these tests, they also examined the applicability of several creep-fatigue life prediction methods to this steel. It was found that the modified ductility exhaustion method proposed by one of the authors gave satisfactory agreement with the test results in comparison with the time fraction rule and classical ductility exhaustion method which have been used in design or integrity assessment of high-temperature reactor plants.
