Creep-fatigue crack initiation assessment on thick circumferentially notched 316L tubes under cyclic thermal shocks and uniform tension with the σd approach
Creators
- 1. CEA Centre d'Etudes de Cadarache, 13 - Saint-Paul-lez-Durance (France)
Description
For crack initiation assessment under creep fatigue loading, in high temperature Fast Reactor's components, specific approaches based on fracture mechanics analysis had to be developed. In the present paper the crack initiation assessment method proposed in the A16 document is presented. The so called ''σd method'' is also validated on experimental results for tubular specimens with internal axisymmetric surface cracks. Experimental data are extracted from the TERFIS program carried out on a sodium test device at the CEA Cadarache. Metallurgical examinations on TERFIS specimens confirm that the initiation assessment of the ''σd'' approach is conservative even for a different geometry than the CT specimen on which the method was set up. However, the conservatism is reduced when the creep residual stress field is relaxed during the hold time. An investigation concerning this last point is needed in order to know if relaxing the stress, when using a lower bound of the mechanical properties, always keeps a safety margin. (author). 14 refs, 10 figs, 4 tabs
Files
28042996.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. 117-129.
- 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
- 28042996
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRACKS; CREEP; FATIGUE; LMFBR TYPE REACTORS; REACTOR COMPONENTS; THERMAL CYCLING; THERMAL SHOCK; TUBES
- Descriptors DEC
- BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; MECHANICAL PROPERTIES; REACTORS