Once through steam generator AFW (auxiliary feedwater) flow distribution and heat transfer
Experiments have been conducted that model BandW Once Through Steam Generator (OTSG) heat transfer and fluid flow behavior during auxiliary feedwater (AFW) injection. The OTSG is a single-pass counterflow tube-in-shell heat exchanger in which decay heat removal capability is provided by injection of AFW into the steam generator boiler region. The experiments and analysis is described in this paper examine the basic phenomena of AFW radial and axial flow distribution, tube support plate (TSP) flooding, and tube heat transfer. Flow distribution is studied visually and measured in an unheated multitube (625 tubes) full scale 1/8 sector of the OTSG, which includes the top three TSP's. Steam flow is simulated by air flow. Heat transfer is examined in a heated single tube facility with either one or two broached hole support plates and either air or steam upflow. The flow distribution experiments indicate that radial, axial, and azimuthal spreading is a strong function of AFW flow rate and a weaker function of vapor upflow unless the flooding line is approached. A semi-empirical model of AFW penetration without gas flow is presented. The model is extended to include the influence of gas flow by correlation. The heat transfer experiments indicate that heat transfer is highly dependent on AFW injection rate, and in particular on whether or not the water flows down the tubes as a continuous film or breaks into rivulets. A computer model of heat transfer has been developed, and is described. 4 refs., 21 figs.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6814800
- Report Number(s):
- EGG-M-01188; CONF-881160-1; ON: DE88015223; TRN: 88-035590
- Resource Relation:
- Conference: Thermal hydraulics of nuclear steam generators/heat exchangers, Chicago, IL, USA, 28 Nov 1988; Other Information: Paper copy only, copy does not permit microfiche production
- Country of Publication:
- United States
- Language:
- English
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Flooding, AFW penetration, and visual investigations in scaled once through steam generator facilities
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Related Subjects
HEAT EXCHANGERS
HEAT TRANSFER
STEAM GENERATORS
FLUID FLOW
AUXILIARY WATER SYSTEMS
DESIGN BASIS ACCIDENTS
ENGINEERING DRAWINGS
FLOW MODELS
FLOWSHEETS
GAS FLOW
NUCLEAR POWER PLANTS
NUMERICAL DATA
ACCIDENTS
AUXILIARY SYSTEMS
BOILERS
DATA
DIAGRAMS
ENERGY TRANSFER
INFORMATION
MATHEMATICAL MODELS
NUCLEAR FACILITIES
POWER PLANTS
REACTOR ACCIDENTS
THERMAL POWER PLANTS
VAPOR GENERATORS
220200* - Nuclear Reactor Technology- Components & Accessories