French recent developments in support to rules for creep and creep-fatigue analyses
Description
RCC-MR proposes Design rules for creep and creep-fatigue damage evaluation in zones with no geometrical discontinuities. Rules have been developed, based on the σd concept, in order to consider zones with geometrical discontinuities. Rule for Weld are proposed in the paragraph relative to shell design rules and reduction coefficient due to material properties are given in Appendix A9. For fatigue analysis, last version of RCC-MR (1993) has proposed a reduction factor on fatigue curves (Jf value), derived from preliminary tests performed within European program. Studies have been carried out in order to have a better understanding of the phenomena involved in these fatigue reduction factors. Tests have been performed on large plates, with varying applied displacements, weld geometry, plate thickness, weld direction. It appears that material effect is not the only purpose to be considered but that it is necessary to think about the geometrical effect, linked to the welded zone dimensions, and the elastic follow-up effect between the two materials: base metal and weld metal. As a first approach, simplified calculations have been achieved with precise material characterization. Roche's method and Zarka method's give conservative result in comparison to tests results. (author). 3 refs, 4 tabs
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28043005.pdf
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Additional details
Publishing Information
- Imprint Title
- Creep-fatigue damage rules for advanced fast reactor design. Proceedings of a technical committee meeting
- Imprint Pagination
- 282 p.
- Journal Page Range
- p. 253-260.
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--933
Conference
- Title
- Technical committee meeting on creep-fatigue damage rules for advanced fast reactor design.
- Dates
- 11-13 Jun 1996.
- Place
- Manchester (United Kingdom).
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 28043005
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CREEP; EVALUATION; FATIGUE; FRANCE; LMFBR TYPE REACTORS; SAFETY ANALYSIS; VARIATIONS
- Descriptors DEC
- BREEDER REACTORS; DEVELOPED COUNTRIES; EPITHERMAL REACTORS; EUROPE; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; MECHANICAL PROPERTIES; REACTORS; WESTERN EUROPE