Elastic plastic fracture toughness values for a hastelloy alloy sample submitted to a static load
Description
In the High Temperature Reactor research programm of the french CEA, Hastelloy alloy plates contain mineral fibers used as insulating material and as such prevent the concrete core vessel from receiving excess heat. Due to the high pressure exerted on this insulating material, the Hastelloy plates are heavily stressed and, therefore, it is important to know their fracture strength. In the case of an elastic, brittle material, the fracture toughness is commonly defined through the well knownKsub(1c) parameter. But, for plastic materials, measuring Ksub(1c) requires very large samples and it was found more convenient to measure the fracture parameter Jsub(1c) instead of Ksub(1c). This parameter was determined according to the RICE or to the more sophisticated HERKLE and CORTEN formula. Two independent ways were followed to measure Jsub(1c): In the first one the shape of the crack after loading was made apparent by some fatigue cycles. After complete fracture of the sample, the amount of crack extension appears clearly and it becomes possible to generate a J resistance curve. As an alternative, we partially unloaded the specimen to get its compliance: the change in compliance was then supposed to coincide with the start of the crack extension. Finally a finite element code was used to compute the specimen state at the beginning of the crack extension. So we are able to obtain the shape of the Load-Displacement curve and to compare it with the experimental one. (orig.)
Additional details
Additional titles
- Original title (French)
- Resistance a la rupture, sous chargement statique d'un alliage X
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. F5/9 (1-8).
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
- 12589047
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONCRETES; FRACTURE PROPERTIES; HASTELLOYS; HTGR TYPE REACTORS; PRESSURE VESSELS; RUPTURES; STRESSES; THERMAL INSULATION
- Descriptors DEC
- ALLOYS; BUILDING MATERIALS; CONTAINERS; FAILURES; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HEAT RESISTING ALLOYS; IRON ALLOYS; MECHANICAL PROPERTIES; MOLYBDENUM ALLOYS; NICKEL ALLOYS; REACTORS; TRANSITION ELEMENT ALLOYS
Optional Information
- Secondary number(s)
- INKA-Conf--79-321-211.