Modeling and database for melt-water interfacial heat transfer

Conference · Wed Jan 01 00:00:00 EST 1992

OSTI ID:5582000

Farmer, M T; Spencer, B W ^[1]; Schneider, J P ^[2]; Bonomo, B ^[3]; Theofanous, G ^[4]

---

1. Argonne National Lab., IL (United States)
2. Illinois Univ., Urbana, IL (United States)
3. Northwestern Univ., Evanston, IL (United States)
4. California Univ., Berkeley, CA (United States)

A mechanistic model is developed to predict the transition superficial gas velocity between bulk cooldown and crust-limited heat transfer regimes in a sparged molten pool with a coolant overlayer. The model has direct applications in the analysis of ex-vessel severe accidents, where molten corium interacts with concrete, thereby producing sparging concrete decomposition gases. The analysis approach embodies thermal, mechanical, and hydrodynamic aspects associated with incipient crust formation at the melt/coolant interface. The model is validated against experiment data obtained with water (melt) and liquid nitrogen (coolant) simulants. Predictions are then made for the critical gas velocity at which crust formation will occur for core material interacting with concrete in the presence of water.

• Research Organization: Argonne National Lab., IL (United States)
• Sponsoring Organization: EPRI; Electric Power Research Inst., Palo Alto, CA (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 5582000
• Report Number(s): ANL/CP-75621; CONF-9204105-2; ON: DE92010504; CNN: Rp-3047-08
• Resource Relation: Conference: 2. Organization for Economic Cooperation and Development (OECD)/Committee on the Safety of Nuclear Installations (CSNI) specialists meeting, Karlsruhe (Germany), 1-3 Apr 1992
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
CONCRETES
INTERACTIONS
QUENCHING
CORIUM
INTERFACES
WATER
BUBBLES
C CODES
FLOW MODELS
FLUID FLOW
HEAT TRANSFER
HYDRAULICS
M CODES
MELTDOWN
THERMODYNAMICS
ACCIDENTS
BUILDING MATERIALS
COMPUTER CODES
ENERGY TRANSFER
FLUID MECHANICS
HYDROGEN COMPOUNDS
MATERIALS
MATHEMATICAL MODELS
MECHANICS
OXYGEN COMPOUNDS
REACTOR ACCIDENTS
220900* - Nuclear Reactor Technology- Reactor Safety
220200 - Nuclear Reactor Technology- Components & Accessories
990200 - Mathematics & Computers