Analysis of thermosyphoning in a steam generator model
An analysis of thermosyphoning in a stream generator model is presented. The model considers the transient development of buoyancy-driven steam flow in the steam generator tubing, secondary side heat transfer and an inlet plenum mixing model. Numerical solutions are obtained for conditions intended to simulate the natural circulation phenomena in a 3-Loop pressurized water reactor in a loss-of-coolant accident scenario. The relation between the circulation rate and the heating rate is determined. The sensitivity of the model to various key parameters is examined. 16 refs.
- Research Organization:
- Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
- Sponsoring Organization:
- USDOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 6174756
- Report Number(s):
- SAND-91-1307; ON: DE92002597
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PWR TYPE REACTORS
LOSS OF COOLANT
STEAM GENERATORS
THERMOSYPHON EFFECT
COMPUTERIZED SIMULATION
FLOW MODELS
HEAT TRANSFER
HYDRAULICS
NUMERICAL SOLUTION
REACTOR SAFETY
THERMOSYPHONS
ACCIDENTS
BOILERS
CONVECTION
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
MASS TRANSFER
MATHEMATICAL MODELS
MECHANICS
POWER REACTORS
REACTOR ACCIDENTS
REACTORS
SAFETY
SIMULATION
THERMAL REACTORS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PWR TYPE REACTORS
LOSS OF COOLANT
STEAM GENERATORS
THERMOSYPHON EFFECT
COMPUTERIZED SIMULATION
FLOW MODELS
HEAT TRANSFER
HYDRAULICS
NUMERICAL SOLUTION
REACTOR SAFETY
THERMOSYPHONS
ACCIDENTS
BOILERS
CONVECTION
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
MASS TRANSFER
MATHEMATICAL MODELS
MECHANICS
POWER REACTORS
REACTOR ACCIDENTS
REACTORS
SAFETY
SIMULATION
THERMAL REACTORS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled