Simplified method for evaluating the seismic buckling capacity of unstiffened steel containment structures
Description
A simplified method is presented for evaluating the seismic buckling capacity of unstiffened, free-standing steel containment structures. The method is consistent with current US Nuclear Regulatory Commission seismic design standards and with containment buckling interaction equations given in the American Society of Mechanical Engineers Boiler and Pressure Vessel Code which includes the influence of geometrical imperfections of the shell on buckling. Stresses to be considered in the interaction equations are determined from beam theory using standard response spectrum analysis. An empirical correction factor is developed to account for hoop stresses that are not explicitly represented in the beam theory. As the results of these analyses are very sensitive to the damping that is assumed, the extensive three-dimensional finite element analyses that were performed to develop the hoop stress reduction factor were also used to study the sensitivity of containment buckling to the assumed damping. Experiments on model containment structures were then performed to further investigate the damping properties exhibited by these structures. The study is concluded by showing that the simplified method reasonably predicts seismic buckling capacities when compared with independently determined predictions from detailed finite element analyses. (orig.)
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 158
- Journal Issue
- 1
- Journal Page Range
- p. 31-45.
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 27036617
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BUCKLING; COMPARATIVE EVALUATIONS; CONTAINMENT; DAMPING; DAVIS BESSE-1 REACTOR; DEFORMATION; ELASTICITY; ENTROPY; KEWAUNEE REACTOR; LUCIE-1 REACTOR; NUMERICAL ANALYSIS; PRAIRIE ISLAND-1 REACTOR; SEISMIC EFFECTS; STEELS; STRESS ANALYSIS; STRESSES; THREE-DIMENSIONAL CALCULATIONS; WATERFORD-3 REACTOR
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; ENRICHED URANIUM REACTORS; EVALUATION; IRON ALLOYS; IRON BASE ALLOYS; MATHEMATICS; MECHANICAL PROPERTIES; PHYSICAL PROPERTIES; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS