Buckling limit evaluation for reactor vessel of KALIMER liquid metal reactor under lateral seismic loads

Citation
Gh. Koo et al., Buckling limit evaluation for reactor vessel of KALIMER liquid metal reactor under lateral seismic loads, INT J PRES, 78(5), 2001, pp. 321-330
Citations number
11
Language
INGLESE
art.tipo
Article
Categorie Soggetti
Mechanical Engineering
Journal title
INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING
ISSN journal
0308-0161 → ACNP
Volume
78
Issue
5
Year of publication
2001
Pages
321 - 330
Database
ISI
SICI code
0308-0161(200105)78:5<321:BLEFRV>2.0.ZU;2-S
Abstract
The purpose of this paper is to evaluate the buckling limit of a conceptual ly designed reactor vessel of the Korea advanced liquid metal reactor (KALI MER). For evaluation of the critical buckling load, evaluation formulae and numerical simulation methods using finite element analysis are used. In th e numerical simulation methods, eigenvalue buckling analysis, and non-linea r buckling analysis with and without plasticity effects are carried out. Fr om the calculated results of the critical buckling load in the KALIMER reac tor vessel, it is shown that plasticity behavior significantly affects the buckling strength but the initial geometrical imperfections have little eff ect on it. In checking the buckling limits of the KALIMER reactor vessel fo r safe shutdown earthquake (SSE) lateral seismic load using the ASME B and PV Section m, subsection NH, a non-seismic isolation design does not satisf y the buckling limit requirements but a seismic isolation design sufficient ly satisfies the requirements. From the experimental verification tests per formed for the cylindrical shells of the reduced scale, it is confirmed tha t the non-linear numerical simulation method used in the buckling strength evaluation can assure accurate results for buckling strength and buckling m ode shape. (C) 2001 Published by Elsevier Science Ltd.