High-Temperature Crack Growth Considerations for Next Generation Nuclear Reactors

摘要

The GEN IV reactor concepts require structural components to operate at high temperatures in a regime where creep damage may occur and cracks may grow. The US NRC has identified the lack of a quantitative methodology for evaluating creep and creep crack growth as a shortcoming of the ASME Subsection NH (Class 1 Components in Elevated Temperature Service) standard. This paper summarizes the efforts at examining creep fatigue crack growth methods that may be used to assess cracks in high temperature reactors. The strengths of current methods are presented and necessary improvements for GEN IV conditions are summarized.