학술논문

Initial-value methods for a simplified subchannel model of thermal-hydraulic behavior
Document Type
Journal Article
Author
Source
Nucl. Sci. Eng.; (United States); 76:3
Subject
22 GENERAL STUDIES OF NUCLEAR REACTORS REACTOR CHANNELS
FLOW BLOCKAGE
HYDRAULICS
THERMODYNAMICS
REACTOR COOLING SYSTEMS
CALCULATION METHODS
COOLANTS
MATHEMATICAL MODELS
NUMERICAL ANALYSIS
NUMERICAL DATA
COOLING SYSTEMS
DATA
ENERGY SYSTEMS
FLUID MECHANICS
INFORMATION
MATHEMATICS
MECHANICS
REACTOR COMPONENTS 220200* -- Nuclear Reactor Technology-- Components & Accessories
Language
English
Abstract
It is shown that many of the numerical difficulties and phenomena encountered in subchannel analysis have counterparts within a simple two-subchannel model, which permits analytic study of these matters. Results are presented that suggest that the reported inability of initial-value techniques for subchannel models to cope with flow-blockage problems may be peculiar to the particular initial-value techniques frequently used.