POSTTEST ANALYSIS OF A 1 1O-SCALE TOP SLAB MODEL OF ABWR/RCCV SUBJECTED TO INTERNAL-PRESSURE/

Citation
H. Saito et al., POSTTEST ANALYSIS OF A 1 1O-SCALE TOP SLAB MODEL OF ABWR/RCCV SUBJECTED TO INTERNAL-PRESSURE/, Nuclear Engineering and Design, 145(3), 1993, pp. 339-353
Citations number
4
Language
INGLESE
art.tipo
Article
Categorie Soggetti
Nuclear Sciences & Tecnology
ISSN journal
0029-5493
Volume
145
Issue
3
Year of publication
1993
Pages
339 - 353
Database
ISI
SICI code
0029-5493(1993)145:3<339:PAOA11>2.0.ZU;2-5
Abstract
Construction of the first Advanced Boiling Water Reactor (ABWR) in Jap an employing a reinforced concrete containment vessel (RCCV) was start ed in 1991. As RCCV itself is the first structure of its kind in Japan , thorough verification tests have been performed. This paper presents the results of simulation analysis of the Top Slab partial model of t he RCCV subjected to internal pressure beyond design load. The Top Sla b portion is complicated, being composed of a flat Top Slab, cylindric al wall and fuel pool girders, that its simulation analysis requires t he evaluation of nonlinear structural behavior of reinforced concrete members due to membrane, bending and shear forces. This paper reports that Finite Element analysis with 3-D solid elements has given a good quantitative agreement between experimental and analysis results with respect to deformation, failure load and each nonlinear behavior.