Post-test analysis of a 1:10-scale top slab model of ABWR/RCCV subjected to internal pressure
Creators
- 1. Tokyo Electric Power Co., Civil Engineering and Architectural Div., Nuclear Power Construction Dept. (Japan)
- 2. Toshiba Corp., Plant Design and Engineering Section, Plant and Equipment Engineering Dept., Nuclear Energy Group, Tokyo (Japan)
- 3. Hitachi Works, Hitachi Ltd., Nuclear Equipment 1st Design Section, Ibaraki (Japan)
- 4. Shimizu Corp., Nuclear Power Div., Tokyo (Japan)
Description
Construction of the first Advanced Boiling Water Reactor (ABWR) in Japan employing a reinforced concrete containment vessel (RCCV) was started 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 the RCCV subjected to internal pressure beyond design load. The Top Slab portion is complicated, being composed of a flat Top Slab, cylindrical wall and fuel pool girders, that its simulation analysis requires the 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. (orig.)
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 145
- Journal Issue
- 3
- Journal Page Range
- p. 339-353.
- ISSN
- 0029-5493
- CODEN
- NEDEAU
Conference
- Title
- 5. workshop on containment integrity for nuclear power plants.
- Dates
- 12-14 May 1992.
- Place
- Washington, DC (United States).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 25034365
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTERIZED SIMULATION; CONTAINMENT SYSTEMS; DYNAMIC LOADS; FUEL STORAGE POOLS; JAPAN; MECHANICAL PROPERTIES; MOCKUP; PRESSURIZATION; REACTOR SAFETY EXPERIMENTS; REINFORCED CONCRETE; SCALE MODELS; THERMAL SHOCK; VERIFICATION
- Descriptors DEC
- ASIA; BUILDING MATERIALS; COMPOSITE MATERIALS; CONCRETES; CONTAINMENT; DEVELOPED COUNTRIES; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; MATERIALS; POWER REACTORS; REACTORS; REINFORCED MATERIALS; SIMULATION; STRUCTURAL MODELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS