Time-dependent Materials Properties and Predictive Models for Advanced Structural Alloys in Fast Reactor Systems

摘要

The Global Nuclear Energy Partnership (GNEP) will develop and demonstrate Advanced Burner Reactor (ABR) and/or advanced fast reactors, as a key element of an integrated fuel recycling capability. Code qualification of structural materials and high temperature design methodology are crucial for the design and licensing of sodium-cooled ABR systems. The U.S. Nuclear Regulatory Commission (NRC) raised a number of issues and concerns related to material database and design methodology during the licensing process of the Clinch River Fast Breeder Reactor (CRBR) and Power Reactor Innovative Small Module (PRISM)[1,2]. These issues need to be reexamined and resolved for the ABR design. For example, the widely used bilinear creep-fatigue damage model may not be applicable to all materials, and the current creep-fatigue evaluation does not account for environmental effects. So far only five structural alloys have been qualified for elevated-temperature component service under the ASME Section III, Subsection NH [3]. For the ABR applications, new and advanced alloys may be needed for improved thermal efficiency, long lifetime, and reduced cost.