Published June 1983 | Version v1
Journal article

Buckling and post-buckling behavior of the ACS support columns

  • 1. Argonne National Lab., IL (USA). Reactor Analysis and Safety Div.
  • 2. Northwestern Univ., Evanston, IL (USA). Dept. of Civil Engineering

Description

Computer program development and modeling procedures for above-core structures (ACS) have recently focused on modeling the buckling and post-buckling behavior of the ACS support columns. These developments are directed toward two considerations: (1) the prediction of the forces exerted by the column in a hypothetical core-disruptive accident (HCDA) in order that the motion of the ACS can be predicted in a coupled fluid-structure analysis, (2) the calculation of the strains and deformations of the support columns so that situations which lead to complete failure can be identified. One of the aims of this study was to examine the effect of the change in cross section, previously not treated, on the behvior of the support columns. For this purpose, models have been developed in which the portions of the column which undergo significant changes in cross section are modeled by plate elements. Results are presented for two sets of studies. In the first set, results are presented for a series of Stanford Research International scale model tests. Comparison of the tests with the computed results shows reasonable agreement. In the second, the column was displaced with a constant velocity at one end to examine its resistance as a function of displacement. The behavior of support columns consisting of two concentric cylinders has also been studied. The interesting feature of this design is that when one of the cylinders buckles, it moves laterally against the other, which may not have buckled. An effective but simple model was developed for representing the interaction between the columns. Results are presented for an HCDA corresponding to a release of 1000 MJ. (orig.)

Additional details

Publishing Information

Journal Title
Nucl. Eng. Des.
Journal Volume
75
Journal Issue
3
Series
CODEN: NEDEA.;Nucl. Eng. Des.
Journal Page Range
323-342
ISSN
0029-5493

Conference

Title
7. international seminar on computational aspects of the finite element method (CAFEM-7) in conjunction with the 7. international conference on structural mechanics in reactor technology (SMIRT-7).
Dates
22-26 Aug 1983.
Place
Chicago, IL (USA).

INIS

Country of Publication
Netherlands
Country of Input or Organization
Netherlands
INIS RN
15010055
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BUCKLING; COMPUTERIZED SIMULATION; DEFORMATION; REACTOR COMPONENTS; REACTOR CORE DISRUPTION; REACTOR CORES; REACTOR SAFETY; SUPPORTS
Descriptors DEC
ACCIDENTS; MECHANICAL STRUCTURES; REACTOR ACCIDENTS; SAFETY; SIMULATION

Optional Information

Notes
2. special issue on SMiRT-7.