Published February 2005 | Version v1
Journal article

High temperature fatigue of 316FR steels for nuclear reactor use

  • 1. National Inst. for Materials Science, Tsukuba, Ibaraki (Japan)

Description

Evaluation of high temperature fatigue properties of an austenitic steel 316FR, which was newly developed as a structural material used for fast breeder reactors, was carried out in view of extension of creep lifetimes. The material is based on SUS316 steel, kept carbon quantity as low as 0.008% and instead nitrogen quantity up to 0.073% which will prevent inter-granular deposition of carbides and thus creep-fatigue controlling. First, the authors explain a parametric analysis method to evaluate the temperature and strain-rate dependence of high temperature low cycle fatigue lifetimes based on thermal activation process, followed by its application to the case of 316 FR steels and the demonstration of extrapolating the method to ultra-low cycle fatigue case. Finally, the guideline for designing a better fatigue lifetime material with adding a trace amount of elements and/or preparing crystallites and grains. Applicability of the present analytic method was discussed. (S. Ohno)

Additional details

Publishing Information

Journal Title
Zairyo No Kagaku To Kogaku
Journal Volume
42
Journal Issue
1
Journal Page Range
p. 58-63
ISSN
1347-4774

Optional Information

Notes
16 refs., 8 figs., 4 tabs.