Abstract
NUPEC and USNRC have been jointly sponsoring "Structural Behavior Test" as Sandia National Laboratory (SNL) in "Cooperative Containment Research Program" to investigate the response of representative models of nuclear reactor containment structure due to internal pressure loading beyond the design basis accident and to establish analytical prediction methods. The Steel Containment Vessel (SCV) model test was carried out at SNL on December 11-12 1996. In this report, we applied the analytical prediction method to an actual scale SCV model under the Severe Accident (SA) condition.
