Creep-fatigue evaluation rules in design guide for DRBR in Japan

The structural design guide has been unproved for the elevated temperature components of Demonstration Fast Breeder Reactor (DFBR) in Japan. The basic concept is as same as the ``Elevated Temperature Design Guide for Class 1 Components of Prototype Fast Breeder Reactor`` (ETSDG) and some improvements based upon the recent R and D results are introduced for the structural and material characteristic of DFBR. This paper describes the creep-fatigue damage evaluation rules, which includes the advanced method for the inelastic strain range calculation and creep damage estimation.