Creep and low cycle fatigue behaviour of fast reactor structural materials

8Citations
Citations of this article
27Readers
Mendeley users who have this article in their library.

Abstract

Low cycle fatigue and long-term creep properties, as well as compatibility with liquid sodium coolant, govern the choice of materials for out-of-core structural and steam generator components of sodium cooled fast reactors (SFRs). 316L(N) SS is preferred for all high temperature structural components while modified 9Cr-1Mo steel is preferred for the steam generator components for which resistance to stress corrosion cracking in steam is an additional requirement. A thorough understanding of the deformation, damage and fracture behavior of these materials helps to improve confidence in the design of the components and performance in service, and also to develop improved materials. The cyclic and creep deformation behavior have to be understood under complex stress conditions and in the liquid sodium, operating environment. This paper highlights the creep, low cycle fatigue and creep-fatigue properties of current SFR materials in air and sodium environments, and discusses the studies underway to develop improved materials for future SFRs for longer design life. © 2013 The Authors.

Cite

CITATION STYLE

APA

Mathew, M. D., Laha, K., & Sandhya, R. (2013). Creep and low cycle fatigue behaviour of fast reactor structural materials. In Procedia Engineering (Vol. 55, pp. 17–26). Elsevier Ltd. https://doi.org/10.1016/j.proeng.2013.03.213

Register to see more suggestions

Mendeley helps you to discover research relevant for your work.

Already have an account?

Save time finding and organizing research with Mendeley

Sign up for free