Experimental J and COD analysis of crack initiation in through-thickness cracked pipes
Creators
- 1. Pisa Univ. (Italy). Ist. di Impianti Nucleari
- 2. Comitato Nazionale per l'Energia Nucleare, Casaccia (Italy). Centro di Studi Nucleari
Description
The paper relates on results of a research, carried out at Laboratories of the Istituto di Impianti Nucleari of the University of Pisa in cooperation with CNEN-Casaccia Laboratories, on experimental J and COD analysis of crack initiation in through-thickness cracked pipes. General aim of the research is to utilize EPFM parameters in order to forecast the fracture behaviour of pipes, considered as simple structures. Testing is carried out at room temperature on low carbon steel pipes, that are 100 mm in outer diameter and 4 mm thick, in two basic conditions: - burst tests under internal pressure on longitudinally cracked pipes; - four point bending tests on circumferentially cracked pipes. During the tests, both the clip gauge opening displacement and the load Application point displacement are recorded seperately in terms of the load. Heat tinting technique is also used for measuring crack growth. J and COD crack initiation related values are also compared with the results of tensile tests obtained on no-standard cracked specimens made with the self-same material of the tested pipes. (orig.)
Additional details
Publishing Information
- Publisher
- North-Holland Publishing Co.
- Imprint Place
- Amsterdam, Netherlands
- ISBN
- 0444 85362 6
- Imprint Title
- Structural mechanics in reactor technology. Transactions. Vol. F
- Journal Page Range
- p. F5/13 (1-7).
Conference
- Title
- 5. international conference on structural mechanics in reactor technology (SMIRT-5). 9. international seminar and 2. international seminar on structural reliability of mechanical components and subassemblies of nuclear power plants and 2. international seminar on containment of fast breeder reactors (CONFABRE-2).
- Dates
- 9 - 21 Aug 1979.
- Place
- Berlin, Germany, F.R.
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 12588741
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CARBON STEELS; CRACKS; FRACTURES; PIPES; REACTOR COMPONENTS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; FAILURES; IRON ALLOYS; IRON BASE ALLOYS; STEELS; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- With figs.
- Secondary number(s)
- INKA-Conf--79-321-215.