Published March 1997 | Version v1
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Creep-fatigue crack initiation assessment on thick circumferentially notched 316L tubes under cyclic thermal shocks and uniform tension with the σd approach

  • 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

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Part of:
Creep-fatigue damage rules for advanced fast reactor design. Proceedings of a technical committee meeting

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

Optional Information