Modeling and calculation of corium/concrete interaction in a MARK-I containment
It is anticipated that following low-pressure corium ejection from a reactor pressure vessel (RPV) into the dry well of a boiling water reactor (BWR) pressure suppression containment, a large amount of hot, mostly molten corium may collect on the dry well floor. The products of concrete ablation pass into the corium pool and start reacting with the various corium constituents, such as zirconium, chromium, iron, and UO{sub 2}, and with other materials released from the concrete, such as SiO{sub 2}, CaO, and Fe{sub 2}O{sub 3}. In order to estimate the effect of the chemical reactions due to these metal/concrete interactions on the amount and energy of gas released into the containment air spaces, a new analytical model has been developed. This model has been extensively tested and validated as the stand-alone subroutine, JIA. This subroutine has also been implemented into the APRIL computer code.
- OSTI ID:
- 6023119
- Report Number(s):
- CONF-900608-; CODEN: TANSA; TRN: 91-008254
- Journal Information:
- Transactions of the American Nuclear Society; (USA), Vol. 61; Conference: American Nuclear Society (ANS) annual meeting, Nashville, TN (USA), 10-14 Jun 1990; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
REACTOR CORE DISRUPTION
A CODES
CALCIUM OXIDES
CARBON MONOXIDE
CHROMIUM
CONTAINMENT SYSTEMS
CORIUM
FISSION PRODUCTS
HYDROGEN
IRON
IRON OXIDES
MATHEMATICAL MODELS
MELTDOWN
PRESSURE VESSELS
REACTOR ACCIDENTS
REACTOR SAFETY
SILICON OXIDES
URANIUM DIOXIDE
ZIRCONIUM
ACCIDENTS
ACTINIDE COMPOUNDS
ALKALINE EARTH METAL COMPOUNDS
CALCIUM COMPOUNDS
CARBON COMPOUNDS
CARBON OXIDES
CHALCOGENIDES
COMPUTER CODES
CONTAINERS
CONTAINMENT
ELEMENTS
ENGINEERED SAFETY SYSTEMS
IRON COMPOUNDS
ISOTOPES
MATERIALS
METALS
NONMETALS
OXIDES
OXYGEN COMPOUNDS
RADIOACTIVE MATERIALS
REACTORS
SAFETY
SILICON COMPOUNDS
TRANSITION ELEMENT COMPOUNDS
TRANSITION ELEMENTS
URANIUM COMPOUNDS
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled