Stability of natural circulation with gravity-induced flashing
Creators
Description
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
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 57
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 379-380
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- Joint meeting of the European Nuclear Society and the American Nuclear Society.
- Dates
- 30 Oct - 4 Nov 1988.
- Place
- Washington, DC (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21007907
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTER CODES; DISTRICT HEATING; DUAL-PURPOSE POWER PLANTS; EIGENVALUES; EIGENVECTORS; FLASH HEATING; HEAT TRANSFER; HYDRAULICS; LAPLACE TRANSFORMATION; MATHEMATICAL MODELS; N CODES; NATURAL CONVECTION; ONE-DIMENSIONAL CALCULATIONS; PRESSURE DROP; PRIMARY COOLANT CIRCUITS; REACTOR CORES; REACTOR STABILITY; S CODES; SPACE DEPENDENCE; TEST FACILITIES; TIME DEPENDENCE; TWO-PHASE FLOW; VOID FRACTION
- Descriptors DEC
- CONVECTION; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; HEATING; INTEGRAL TRANSFORMATIONS; POWER PLANTS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; STABILITY; THERMAL REACTORS; TRANSFORMATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-881011--.