Effects of lateral separation of oxidic and metallic core debris on the BWR MK I containment drywell floor
In evaluating core debris/concrete interactions for a BWR MK I containment design, it is common practice to assume that at reactor vessel breach, the core debris is homogeneous and of low viscosity, so that it flows through the pedestal doorway and spreads in a radially uniform fashion throughout the drywell floor. In a recent study performed by the NRC-sponsored Severe Accident Sequence Analysis (SASA) program at Oak Ridge National Laboratory, calculations indicate that at reactor vessel bottom head failure, the debris temperature is such that the debris metals (Zr, Fe, Ni, Cr) are completely molten while the oxides (UO/sub 2/ ZrO/sub 2/, FeO) are completely frozen. Thus, the frozen oxides are expected to remain within the reactor pedestal while the molten metals radially separate from the frozen oxides, flow through the reactor pedestal doorway, and spread over the annular region of the drywell floor between the pedestal and the containment shell. This paper assesses the impact on calculated containment response and the production and release of fission product-laden aerosols for two different cases of debris distribution: uniform distribution and the laterally separated case of 95% oxides-5% metals inside the pedestal and 5% oxides-95% metals outside the pedestal. The computer codes used are CORCON-MOD2, MARCON 2.1B and VANESA.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 5408170
- Report Number(s):
- CONF-8609126-1; ON: TI86014646
- Country of Publication:
- United States
- Language:
- English
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Effects of lateral separation of oxidic and metallic core debris on the BWR (Boiling Water Reactor) MK I containment drywell floor
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22 GENERAL STUDIES OF NUCLEAR REACTORS
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220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AEROSOLS
BUILDING MATERIALS
BWR TYPE REACTORS
C CODES
CHALCOGENIDES
COLLOIDS
COMPUTER CODES
COMPUTERIZED SIMULATION
CONCRETES
CONTAINMENT
CONTAINMENT SYSTEMS
CORIUM
DESIGN
DISPERSIONS
ENGINEERED SAFETY SYSTEMS
FISSION PRODUCT RELEASE
FLUID-STRUCTURE INTERACTIONS
M CODES
MATERIALS
MELTDOWN
OXIDES
OXYGEN COMPOUNDS
RADIOACTIVE AEROSOLS
REACTOR ACCIDENTS
REACTOR MATERIALS
REACTORS
RESEARCH PROGRAMS
SIMULATION
SOLS
V CODES
WATER COOLED REACTORS
WATER MODERATED REACTORS