Published 1979
| Version v1
Book
Experimental studies of PWR primary piping under LOCA conditions
- 1. Societe Franco-Americaine de Constructions Atomiques (FRAMATOME), 92 - Courbevoie (France)
- 2. CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-les-Durance (France)
Description
Tests have been performed on a 1/10 th scale model to study the mechanical behavior of a primary PWR pipe and the forces exerted on the neighbouring structures as a consequence of a break opening. A number of tests have been carried out with different pipe configurations (straight tube, elbow, S or U shaped tube) and different break types (single or double guillotine). The following aspects are investigated: - the dynamic behavior of the pipe and in particular the formation of a plastic hinge at the restraint; - impact function of a pipe on an energy-absorbing bumper; - lateral stability of both ends of a pipe consequently to a guillotine break. (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. F6/1 (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
- 12592555
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- LOSS OF COOLANT; MOCKUP; PIPES; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; RUPTURES
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; FAILURES; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; STRUCTURAL MODELS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- With figs.
- Secondary number(s)
- INKA-Conf--79-321-216.