Pretest Round Robin Analysis of a Prestressed Concrete Containment Vessel Model (NUREG/CR-6678)
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Manuscript Completed: June 2000
Date Published: August 2000
Sandia National Laboratories
Albuquerque, NM 87185-0744
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001
NRC Job Code Extreme Loads JCN A1401
NRC Project Manager: J.F. Costello
Systems Safety Department
Nuclear Power Engineering Corporation
Tokyo 105, Japan
NUPEC Project Manager: S. Shibata
The Nuclear Power Engineering Corporation of Japan and the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, are co-sponsoring and jointly funding a Cooperative Containment Research Program at Sandia National Laboratories in Albuquerque, New Mexico. As a part of the program, a prestressed concrete containment vessel model will be tested to failure at Sandia in September 2000. The model, uniformly scaled at 1:4, is representative of the containment structure of an actual pressurized-water reactor plant (OHI-3) in Japan. The objectives of the internal pressurization test are to obtain data on the structural response of the model to pressure loading beyond design basis accident in order to validate analytical modeling, to find the model's pressure capacity, and to observe its response and failure mechanisms.
Seventeen organizations participated in a pretest Round Robin analysis to predict the structural response of the model under overpressurization. Each organization was supplied with the same basic information to use in its analysis. This information included the design drawings of the prestressed concrete containment vessel model and the material properties of the structural components. Each organization worked independently, using its own analytical methods, to produce analysis results for 55 specified locations on the model. The Round Robin analysis provides a forum for participants to discuss pretest predictions of the deformation behavior of the prestressed concrete containment vessel model, as well as to compare them to the test data.
This report contains the analytical modeling procedures and the pretest predictions submitted by each organization. This report also includes composite plots of participants' analysis results at the 55 specified locations on the model. These plots, which were discussed among participants at the pretest analysis meeting, held October 12-14, 1999, in Albuquerque, will be compared to the test data generated during the internal pressurization test.
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