Modeling of drift effects in CANDU reactors

Conference · Wed Jan 01 04:00:00 EST 1986 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:6891895

Sami, S M

In the most of the Canada deuterium uranium (CANDU) reactor thermohydraulic codes, the two-phase fluid is assumed to be both homogeneous and in thermal equilibrium. However, to account for the unequal velocity effects, several slip and drift correlations are incorporated within these codes. These correlations are in many respects nonmechanistic and inadequate since they do not account for countercurrent or gravity-dominated flow effects. The model described in the paper is the most realistic approach that can be used to describe slip in a transient multipurpose code. Simplified assumptions are made such that only four differential equations must be solved in the code. They are the code continuity, momentum and energy equations for mixture, and one additional equation which describes the spatial- and temporal-dependent behavior of the velocity difference. This latter equation is an arrangement of the two-fluid model equations. The resultant equation gives a time-dependent relation between the phase velocities which are a function of the pressure gradient, phase inertias, volume fraction, the flow regime, and additional constitutive relations.

• Research Organization: Univ. of Sherbrooke, Quebec
• OSTI ID: 6891895
• Report Number(s): CONF-861102-
• Conference Information: Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 53
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210400* -- Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated
ACCIDENTS
CANDU TYPE REACTORS
COMPUTER CODES
COMPUTERIZED SIMULATION
COUNTER CURRENT
ENERGY TRANSFER
F CODES
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HEAVY WATER MODERATED REACTORS
HYDRAULICS
LOSS OF COOLANT
MATHEMATICAL MODELS
MECHANICS
PRESSURE TUBE REACTORS
PWR TYPE REACTORS
R CODES
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
S CODES
SAFETY
SIMULATION
STEADY-STATE CONDITIONS
THERMAL REACTORS
TURBULENT FLOW
TWO-PHASE FLOW
WATER COOLED REACTORS
WATER MODERATED REACTORS