Estimation of interfacial shear stress in countercurrent flow in bundles

Conference · Fri Jan 01 04:00:00 EST 1993 · Transactions of the American Nuclear Society; (United States)

OSTI ID:5884147

Lin, Y Z; Nam, D T ^[1]

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1. Moscow Power Engineering Institute Krasnokazarmennaya (Russian Federation)

Countercurrent flow (CCF) is one of the most important phenomena occurring during a loss-of-coolant accident (LOCA) in a light water reactor because CCF affects the mass flow of core cooling water by limiting the water flow from the upper plenum to the core, from the downcomer to the lower plenum, and from the tubes in the steam generator to the steam generator inlet plenum. Recently, reactor safety analysis codes such as the TRACPF1 code, the RELAP5 code and others have been developed as so-called best-estimate codes for precise analysis of various phenomena during a LOCA. Most of these codes are based on the two-fluid model. In the two-fluid model, the basic equations for vapor and liquid phases are solved with closure laws for the interfacial and wall friction factors and for the interfacial and wall heat transfer coefficients. Accurate constitutive equations are essential to obtain precise results within the framework of the two-fluid models.

• OSTI ID: 5884147
• Report Number(s): CONF-930601--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 68
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
ACCIDENTS
ALGORITHMS
COMPUTER CODES
COMPUTERIZED SIMULATION
FLUID FLOW
FORTRAN
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
LOSS OF COOLANT
MATHEMATICAL LOGIC
PROGRAMMING LANGUAGES
R CODES
REACTOR ACCIDENTS
SIMULATION
THREE-DIMENSIONAL CALCULATIONS
TURBULENT FLOW