High temperature fatigue of 316FR steels for nuclear reactor use
Creators
- 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
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 36064107
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- AUSTENITIC STEELS; CREEP; ELONGATION; FAST REACTORS; RUPTURES; STRAIN RATE; STRESS ANALYSIS; TEMPERATURE RANGE 0400-1000 K; TENSILE PROPERTIES; THERMAL FATIGUE
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; DEFORMATION; EPITHERMAL REACTORS; FAILURES; FATIGUE; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; REACTORS; STEELS; TEMPERATURE RANGE; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- 16 refs., 8 figs., 4 tabs.