Numerical simulation of an equipment hatch for a steel containment vessel to loading beyond the design basis
Conference
·
OSTI ID:5499772
A preliminary analysis of the sealing deformations of a large equipment hatch with a pressure-seated gasket due to overpressurization was performed. An axisymmetric finite element analysis of the penetration sleeve revealed that its surface can undergo large rotations; values for sealing surface rotation of 7/sup 0/ were computed. Estimates for the order of magnitude of leakage due to the sealing surface rotation were made. 10 refs., 7 figs., 1 tab.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31-109-ENG-38
- OSTI ID:
- 5499772
- Report Number(s):
- CONF-850809-56; ON: DE85010485
- Resource Relation:
- Conference: 8. international conference on structural mechanics in reactor technology, Brussels, Belgium, 19 Aug 1985
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
CONTAINMENT BUILDINGS
CLOSURES
DEFORMATION
STRESS ANALYSIS
PWR TYPE REACTORS
COMPUTERIZED SIMULATION
CONTAINMENT SYSTEMS
FINITE ELEMENT METHOD
GASKETS
LEAKS
MATHEMATICAL MODELS
PRESSURE EFFECTS
REACTOR SAFETY
STEELS
TEMPERATURE EFFECTS
TRANSIENTS
ALLOYS
BUILDINGS
CONTAINMENT
ENGINEERED SAFETY SYSTEMS
IRON ALLOYS
IRON BASE ALLOYS
NUMERICAL SOLUTION
REACTORS
SAFETY
SEALS
SIMULATION
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
BWR TYPE REACTORS
CONTAINMENT BUILDINGS
CLOSURES
DEFORMATION
STRESS ANALYSIS
PWR TYPE REACTORS
COMPUTERIZED SIMULATION
CONTAINMENT SYSTEMS
FINITE ELEMENT METHOD
GASKETS
LEAKS
MATHEMATICAL MODELS
PRESSURE EFFECTS
REACTOR SAFETY
STEELS
TEMPERATURE EFFECTS
TRANSIENTS
ALLOYS
BUILDINGS
CONTAINMENT
ENGINEERED SAFETY SYSTEMS
IRON ALLOYS
IRON BASE ALLOYS
NUMERICAL SOLUTION
REACTORS
SAFETY
SEALS
SIMULATION
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