Thermal hydraulic and two-phase phenomena in reflooding of nuclear reactor cores

Journal Article · Sat Dec 01 00:00:00 EST 1984 · J. Fluids Eng.; (United States)

DOI:https://doi.org/10.1115/1.3243153· OSTI ID:5116040

Ghiaasiaan, S M; Liu, H L

A quasi-steady, two-dimensional thermal hydraulic analysis of the two-phase region formed ahead of a quench front during reflooding of a slab or cylindrical core is carried out, and the results for slab geometry are compared with the experiment. It is shown that the two-phase level variation in the core is due to the transverse heat flux power profile, and is sensitive to the assumed pressure-drop boundary condition for the bundle, while the effects of crossflow and axial friction are small. Implicit expressions are given for predicting the quasi-steady two-phase level variation across slab and cylindrical cores.

• Research Organization: Science Applications International Corporation, Hermosa Beach, CA
• OSTI ID: 5116040
• Journal Information: J. Fluids Eng.; (United States), Vol. 106:4
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
REACTOR CORES
HEAT TRANSFER
HYDRAULICS
TWO-PHASE FLOW
CYLINDERS
FLUID-STRUCTURE INTERACTIONS
FRICTION
GEOMETRY
HEAT FLUX
MATHEMATICAL MODELS
PRESSURE DROP
SLABS
TWO-DIMENSIONAL CALCULATIONS
ENERGY TRANSFER
FLUID FLOW
FLUID MECHANICS
MATHEMATICS
MECHANICS
REACTOR COMPONENTS
220300* - Nuclear Reactor Technology- Fuel Elements