Results of two-phase natural circulation in hot-leg U-bend simulation experiments
Description
In order to study the two-phase natural circulation and flow termination during a small break loss of coolant accident in LWR, simulation experiments have been performed using two different thermal-hydraulic loops. The main focus of the experiment was the two-phase flow behavior in the hot-leg U-bend typical of B and W LWR systems. The first group of experiments was carried out in the nitrogen gas-water adiabatic simulation loop and the second in the Freon 113 boiling and condensation loop. Both of the loops have been designed as a flow visualization facility and built according to the two-phase flow scaling criteria developed under this program. The nitrogen gas-water system has been used to isolate key hydrodynamic phenomena such as the phase distribution, relative velocity between phases, two-phase flow regimes and flow termination mechanisms, whereas the Freon loop has been used to study the effect of fluid properties, phase changes and coupling between hydrodynamic and heat transfer phenomena. Significantly different behaviors have been observed due to the non-equilibrium phase change phenomena such as the flashing and condensation in the Freon loop. The phenomena created much more unstable hydrodynamic conditions which lead to cyclic or oscillatory flow behaviors
Additional details
Publishing Information
- Imprint Title
- Proceedings of the US Nuclear Regulatory Commission fifteenth water reactor safety information meeting: Volume 4, Separate effects/experiments and analyses, Source term uncertainty analysis, Integral systems testing, 2D/3D research
- Journal Page Range
- p. 81-105.
- Report number
- NUREG/CP--0091-Vol.4
Conference
- Title
- 15. water reactor safety information meeting.
- Dates
- 26-30 Oct 1987.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20019256
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BW STANDARD REACTOR; COMPUTERIZED SIMULATION; FLOW MODELS; FLOW VISUALIZATION; FREONS; FRICTION FACTOR; HEAT TRANSFER; HYDRODYNAMICS; LOSS OF COOLANT; MATHEMATICAL MODELS; NITROGEN; REACTOR COOLING SYSTEMS; REACTOR SAFETY; TWO-PHASE FLOW; WATER
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; ELEMENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; FLUID MECHANICS; HYDROGEN COMPOUNDS; MECHANICS; NONMETALS; ORGANIC COMPOUNDS; ORGANIC HALOGEN COMPOUNDS; OXYGEN COMPOUNDS; POLAR SOLVENTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; SIMULATION; SOLVENTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS