Reliability analysis of RC containment structures under combined loads
Conference
·
OSTI ID:6070228
This paper discusses a reliability analysis method and load combination design criteria for reinforced concrete containment structures under combined loads. The probability based reliability analysis method is briefly described. For load combination design criteria, derivations of the load factors for accidental pressure due to a design basis accident and safe shutdown earthquake (SSE) for three target limit state probabilities are presented.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA); Taisei Construction Co. Ltd., Tokyo (Japan)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 6070228
- Report Number(s):
- BNL-NUREG-35623; CONF-8405286-1; ON: TI85005896; TRN: 85-006388
- Resource Relation:
- Conference: 4. international conference on structural safety and reliability - ICOSSAR '84, Kobe, Japan, 27 May 1984
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
CONTAINMENT BUILDINGS
SEISMIC EFFECTS
STRESS ANALYSIS
NUCLEAR POWER PLANTS
PWR TYPE REACTORS
DESIGN
EARTHQUAKES
MATHEMATICAL MODELS
REACTOR SAFETY
REACTOR SHUTDOWN
REINFORCED CONCRETE
RELIABILITY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
BUILDING MATERIALS
BUILDINGS
CONCRETES
CONTAINMENT
MATERIALS
NUCLEAR FACILITIES
POWER PLANTS
REACTORS
REINFORCED MATERIALS
SAFETY
SEISMIC EVENTS
SHUTDOWNS
THERMAL POWER PLANTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
CONTAINMENT BUILDINGS
SEISMIC EFFECTS
STRESS ANALYSIS
NUCLEAR POWER PLANTS
PWR TYPE REACTORS
DESIGN
EARTHQUAKES
MATHEMATICAL MODELS
REACTOR SAFETY
REACTOR SHUTDOWN
REINFORCED CONCRETE
RELIABILITY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
BUILDING MATERIALS
BUILDINGS
CONCRETES
CONTAINMENT
MATERIALS
NUCLEAR FACILITIES
POWER PLANTS
REACTORS
REINFORCED MATERIALS
SAFETY
SEISMIC EVENTS
SHUTDOWNS
THERMAL POWER PLANTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled