Stability and Bifurcation Analyses of Two-Phase Flow Using a Drift Flux Model and Bifurcation Code BIFDD
Creators
- 1. Paul Scherrer Institut, 5232 Villigen PSI (Switzerland)
- 2. Swiss Federal Institute of Technology, CH-1015, Lausanne (Switzerland)
- 3. College of Engineering, University of Illinois at Urbana-Champaign, 216 Talbot Laboratory, MC-234, 104 South Wright Street, Urbana, IL 61801 (United States)
Description
Nonlinear boiling water reactor (BWR) studies are generally pursued by employing large system codes, like RAMONA and RETRAN. However, detailed investigations using this approach in which parametric studies are to be carried out over large regions of parameter space are very expensive and time consuming. Therefore, it is necessary to use the so-called reduced order models containing a 'manageable' number of system equations incorporating the essential features of the physical phenomena. Since the thermal-hydraulic model determines the main feedback gain and the associated time delay (void feedback reactivity), the modelling of the fluid dynamics is of paramount importance for the reduced order model analyses for BWRs. For a certain set of hydraulic parameter values, the system of nonlinear differential equations describing the fluid dynamics generates the so-called self-sustained density wave oscillations (DWO), which is a typical two-phase flow instability. (authors)
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers - ASME
- Imprint Place
- New York (United States)
- Imprint Pagination
- 7 p.
Conference
- Title
- 10. international conference on nuclear engineering
- Acronym
- ICONE-10
- Dates
- 14-18 Apr 2002
- Place
- Arlington - Virginia (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 39086172
- Subject category
- S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BIFURCATION; BWR TYPE REACTORS; DENSITY; DIFFERENTIAL EQUATIONS; FEEDBACK; GAIN; HYDRODYNAMICS; INSTABILITY; NONLINEAR PROBLEMS; OSCILLATIONS; PARAMETRIC ANALYSIS; REACTIVITY; SIMULATION; SPACE; STABILITY; THERMAL HYDRAULICS; TIME DELAY; TWO-PHASE FLOW; VOIDS
- Descriptors DEC
- AMPLIFICATION; ENRICHED URANIUM REACTORS; EQUATIONS; FLUID FLOW; FLUID MECHANICS; HYDRAULICS; MECHANICS; PHYSICAL PROPERTIES; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS