Failure evauation of a reinforced-concrete, Mark III containment structure under uniform pressure. [BWR]
Technical Report
·
OSTI ID:6210466
An analysis of a Mark III reactor-containment vessel subjected to a uniformly increasing internal pressure and gravity loads is carried out in order to ascertain the load-carrying capacity of the structure under hydrogen burn. The analysis is conducted by using a nonlinear finite-element model that includes nonlinearities in the strain-displacement relations as well as in the material constitutive equations. In this analysis, the nonlinea behavior of the liner and reinforcement steels is described by a von Mises elastic plastic model with isotropic hardening. Results pertaining to the critical regions of the containment where cracking of the concrete, yielding of the reinforcement bars, and substantial straining of the liner take place are discussed in detail in the text that follows.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 6210466
- Report Number(s):
- NUREG/CR-1967; BNL-NUREG-51543; ON: DE83010164
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BUILDING MATERIALS
BWR TYPE REACTORS
CHEMICAL REACTIONS
COMBUSTION
CONCRETES
CONTAINMENT
CONTAINMENT BUILDINGS
ELEMENTS
HYDROGEN
LOSS OF COOLANT
MATERIALS
NONMETALS
OXIDATION
PRESSURE GRADIENTS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
REINFORCED CONCRETE
REINFORCED MATERIALS
SAFETY
STRESS ANALYSIS
THERMOCHEMICAL PROCESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BUILDING MATERIALS
BWR TYPE REACTORS
CHEMICAL REACTIONS
COMBUSTION
CONCRETES
CONTAINMENT
CONTAINMENT BUILDINGS
ELEMENTS
HYDROGEN
LOSS OF COOLANT
MATERIALS
NONMETALS
OXIDATION
PRESSURE GRADIENTS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
REINFORCED CONCRETE
REINFORCED MATERIALS
SAFETY
STRESS ANALYSIS
THERMOCHEMICAL PROCESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS