In-vessel flow characterization under severe accident conditions

Conference · Thu Jan 01 00:00:00 EST 1987

OSTI ID:5991480

Nourbakhsh, H P; Kim, S B; Khatib-Rahbar, M

The purpose of this study is to provide a parametric framework for characterization of flow and heat transfer regimes and their associated phenomenological uncertainties following severe accidents using a two dimensional, heterogenous, porous media formulation. This approach extends the understanding of buoyancy-induced flow characteristics in the uncovered region of the reactor core and the upper plenum of a PWR vessel. The results of this study can be used to augment the boil-off steam flow in integrated one-dimensional severe accident codes such as the Source Team Code Package (STCP).

• Research Organization: Brookhaven National Lab., Upton, NY (USA); Nuclear Regulatory Commission, Washington, DC (USA)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 5991480
• Report Number(s): BNL-NUREG-39933; CONF-871101-37; ON: DE87011921; TRN: 87-035139
• Resource Relation: Conference: California State Air Resources Board, Los Angeles, CA, USA, 15 Nov 1987; Other Information: Portions of this document are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
42 ENGINEERING
CONTAINMENT
HEATING
HEAT TRANSFER
TWO-DIMENSIONAL CALCULATIONS
HYDRAULICS
MELTDOWN
PWR TYPE REACTORS
FLOW MODELS
LOSS OF COOLANT
REACTOR SAFETY
S CODES
SOURCE TERMS
STEAM
ACCIDENTS
COMPUTER CODES
ENERGY TRANSFER
FLUID MECHANICS
MATHEMATICAL MODELS
MECHANICS
REACTOR ACCIDENTS
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
420400 - Engineering- Heat Transfer & Fluid Flow