Stability of natural circulation with gravity-induced flashing

Conference · Fri Jan 01 04:00:00 EST 1988 · Transactions of the American Nuclear Society; (USA)

OSTI ID:5682060

Zhou, Z W; Yadigaroglu, G

The recent development of low-power, boiling water district-heating reactors has drawn attention to some two-phase flow phenomena related to the low-pressure and low-quality operation characterizing this type of reactor. Several proposed designs include a long adiabatic riser above the core to enhance natural circulation. Under such conditions, an important part of the steam generation takes place as flashing driven by the reduction of the hydrostatic pressure in the riser. Investigation of the transient behavior and of the so-called gravity-domain density-wave instabilities of such natural-circulation loops is an important part of their analysis. There is a large body of theoretical and experimental research and state-of-the-art computer codes for stability analysis of conventional and nuclear power systems, but there is no known analysis including the effects of time and space-dependent flashing that characterizes the systems considered here. A linearized density-wave stability analysis model fully taking into account time and space-dependent vaporization is presented here. It is based on the one-dimensional, thermal-equilibrium mixture conservation equations obtained using the widely used drift-flux model.

• OSTI ID: 5682060
• Report Number(s): CONF-881011--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 57
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
BWR TYPE REACTORS
COMPUTER CODES
CONVECTION
COOLING SYSTEMS
DISTRICT HEATING
DUAL-PURPOSE POWER PLANTS
EIGENVALUES
EIGENVECTORS
ENERGY SYSTEMS
ENERGY TRANSFER
EVAPORATION
FLASHED STEAM SYSTEMS
FLASHING
FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HEATING
HYDRAULICS
INTEGRAL TRANSFORMATIONS
LAPLACE TRANSFORMATION
MASS TRANSFER
MATHEMATICAL MODELS
MECHANICS
N CODES
NATURAL CONVECTION
ONE-DIMENSIONAL CALCULATIONS
PHASE TRANSFORMATIONS
POWER PLANTS
PRESSURE DROP
PRIMARY COOLANT CIRCUITS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR STABILITY
REACTORS
S CODES
SPACE DEPENDENCE
STABILITY
STEAM SYSTEMS
TEST FACILITIES
TIME DEPENDENCE
TRANSFORMATIONS
TWO-PHASE FLOW
VOID FRACTION
WATER COOLED REACTORS
WATER MODERATED REACTORS