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.