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
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.