An Overview of Creep-Fatigue Damage Evaluation Methods and an Alternative Approach

Renewed interest in elevated temperature nuclear reactors has occasioned a reassessment of creep-fatigue damage evaluation methods. Points to be improved in the current methods employed in Subsection NH of the ASME BP either directly through inelastic analysis or indirectly through manipulation of elastic analyses. Second, because the test specimen itself incorporates the hardening, softening and aging effects of the structure it represents, it is not necessary do rely on theoretical modeling of these effects in an artificial separate accounting of creep and fatigue damage.Copyright © 2008 by ASME