Pretest predictions for the response of a 1:8-scale steel LWR containment building model to static overpressurization
                            Technical Report
                            ·
                            
                            
                            
                    
                                
                                OSTI ID:5432061
                                
                            
                        The analyses used to predict the behavior of a 1:8-scale model of a steel LWR containment building to static overpressurization are described and results are presented. Finite strain, large displacement, and nonlinear material properties were accounted for using finite element methods. Three-dimensional models were needed to analyze the penetrations, which included operable equipment hatches, personnel lock representations, and a constrained pipe. It was concluded that the scale model would fail due to leakage caused by large deformations of the equipment hatch sleeves. 13 refs., 34 figs., 1 tab.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 5432061
- Report Number(s):
- NUREG/CR-4137; SAND-85-0175; ON: TI85015569
- Country of Publication:
- United States
- Language:
- English
Similar Records
                                
                                
                                    
                                        
                                        Analysis of a 1:8 scale steel containment model subject to internal static pressurization
                                        
Numerical simulation of an equipment hatch for a steel containment vessel to loading beyond the design basis
Behavior of a nuclear steel containment equipment hatch at large strain
                        
                                            Conference
                                            ·
                                            Sat Dec 31 23:00:00 EST 1983
                                            
                                            ·
                                            OSTI ID:6834270
                                        
                                        
                                        
                                    
                                
                                    
                                        Numerical simulation of an equipment hatch for a steel containment vessel to loading beyond the design basis
                                            Conference
                                            ·
                                            Mon Dec 31 23:00:00 EST 1984
                                            
                                            ·
                                            OSTI ID:5499772
                                        
                                        
                                        
                                    
                                
                                    
                                        Behavior of a nuclear steel containment equipment hatch at large strain
                                            Journal Article
                                            ·
                                            Sun May 01 00:00:00 EDT 1988
                                            · J. Pressure Vessel Technol.; (United States)
                                            ·
                                            OSTI ID:6735314
                                        
                                        
                                        
                                    
                                
                            Related Subjects
                                
                                    
                                        
                                        
                                            
                                                21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ALLOYS
BUILDINGS
BWR TYPE REACTORS
CHROMIUM ALLOYS
CONTAINMENT
CONTAINMENT BUILDINGS
CORROSION RESISTANT ALLOYS
DEFORMATION
FAILURE MODE ANALYSIS
FAILURES
FINITE ELEMENT METHOD
IRON ALLOYS
IRON BASE ALLOYS
LEAKS
NUMERICAL SOLUTION
PIPES
PRESSURE EFFECTS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
SCALE MODELS
SLEEVES
STAINLESS STEELS
STEELS
STRAINS
STRUCTURAL MODELS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
WATER COOLED REACTORS
WATER MODERATED REACTORS
                                            
                                        
                                    
                                
                            
                        210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ALLOYS
BUILDINGS
BWR TYPE REACTORS
CHROMIUM ALLOYS
CONTAINMENT
CONTAINMENT BUILDINGS
CORROSION RESISTANT ALLOYS
DEFORMATION
FAILURE MODE ANALYSIS
FAILURES
FINITE ELEMENT METHOD
IRON ALLOYS
IRON BASE ALLOYS
LEAKS
NUMERICAL SOLUTION
PIPES
PRESSURE EFFECTS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTORS
SCALE MODELS
SLEEVES
STAINLESS STEELS
STEELS
STRAINS
STRUCTURAL MODELS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
WATER COOLED REACTORS
WATER MODERATED REACTORS