Published 1979 | Version v1
Book

Applicability of flat plate methods in determining fluid/structure interaction effects in BWR pressure suppression systems

  • 1. California Univ., Livermore (USA). Lawrence Livermore National Lab.

Description

Flat plate chord tests are on experimental method used to investigate how fluid/structure interaction (FSI) effects modify the impulsive loading in nuclear reactor pressure suppression pools. This analytical study examines the applicability of using a flexible flat plate in an otherwise rigid shell to model dynamic pool wall response in a flexible shell pressure suppression torus. Bubble pressures varying by a factor of seven are used as input to two-dimensional finite-element models. Boundary response to various plate and shell thicknesses are compared on the basis of equivalent natural frequency. Results indicate the qualitative flat plate response compares well with the flexible shell but absolute pressures vary significantly and nonconservatively. (orig.)

Additional details

Publishing Information

Publisher
North-Holland Publishing Co.
Imprint Place
Amsterdam, Netherlands
ISBN
0 444 85358 8
Imprint Title
Structural mechanics in reactor technology. Transactions. Vol. B
Journal Page Range
p. B8/8 (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
12588922
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; CONTAINMENT SPRAY SYSTEMS; FLUID FLOW; INTERACTIONS; MECHANICAL STRUCTURES; PLATES; PRESSURE SUPPRESSION; SHELLS
Descriptors DEC
CONTAINMENT; CONTAINMENT SYSTEMS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
INKA-Conf--79-321-071.