Ultimate pressure capacity analysis of a post-tensioned reinforced concrete nuclear reactor containment building
Conference
·
· Am. Soc. Mech. Eng., Pressure Vessels Piping Div., (Tech. Rep.) PVP; (United States)
OSTI ID:5625430
This paper presents a three dimensional nonlinear structural analysis of a post-tensioned reinforced concrete nuclear reactor containment building. The objective of the analysis was to develop and demonstrate modeling techniques appropriate for determining the global ultimate internal pressure capacity of this type of containment. The structural model developed for the ADINA computer code employed nonlinear material models with truss, shell and three dimensional continuum elements to represent the major structural members (tendons, rebars, ties, concrete and liner). In addition a special uniaxial elastic plastic shell material model was developed to facilitate representation of the dome tendon lacing pattern. Effective use of symmetry permitted all three dimensional effects to be represented in a 30/sup 0/ (0.52 rad) segment of the structure. The analysis suggested that gross failure of the structure at a quasistatic internal pressure of 99 psi (0.68 MPa) may have been precipitated by the nonaxisymmetric three dimensional nature of the stress field in the concrete near the tendon anchorages.
- Research Organization:
- EG and G Idaho Inc., Idaho Falls, Idaho
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5625430
- Report Number(s):
- CONF-830607-
- Conference Information:
- Journal Name: Am. Soc. Mech. Eng., Pressure Vessels Piping Div., (Tech. Rep.) PVP; (United States) Journal Volume: PVP-VOL. 76
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
BUILDING MATERIALS
COMPUTER CODES
CONCRETES
CONTAINMENT
CONTAINMENT BUILDINGS
CONTAINMENT SHELLS
ELASTICITY
MATERIALS
MECHANICAL PROPERTIES
NONLINEAR PROBLEMS
PLASTICITY
PRESSURE DEPENDENCE
REINFORCED CONCRETE
REINFORCED MATERIALS
STRESS ANALYSIS
STRESSES
TENSILE PROPERTIES
THREE-DIMENSIONAL CALCULATIONS
220200* -- Nuclear Reactor Technology-- Components & Accessories
BUILDING MATERIALS
COMPUTER CODES
CONCRETES
CONTAINMENT
CONTAINMENT BUILDINGS
CONTAINMENT SHELLS
ELASTICITY
MATERIALS
MECHANICAL PROPERTIES
NONLINEAR PROBLEMS
PLASTICITY
PRESSURE DEPENDENCE
REINFORCED CONCRETE
REINFORCED MATERIALS
STRESS ANALYSIS
STRESSES
TENSILE PROPERTIES
THREE-DIMENSIONAL CALCULATIONS