Steam content of the two-phase flow in the Vk-50 boiling water cooled reactor draught section
Description
Results are presented of experimental investigation of the two-phase steam-water coolant flow hydrodynamics within the VK-50 reactor draught section. On the basis of the analysis of the obtained data a two-phase coolant flow model in a large diameter channel is proposed. It is shown that the steam-content distribution in the volume of the draught section has a pronounced non-equilibrium character manifested in the steam migration from the periphery to the central region. A minimum value of the steam content at the periphery is attained at the 0.7-1.0 m height; it is followed by a partial steam content levelling over the section. However the total steam content levelling over the cross section of the draught section does not take place. The steam distribution in the water layer over the draught section (overflow zone) is also nonuniform over the reactor section. The non-uniform steam distribution enchances with reduction nn pressure
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15056723.pdf
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Additional details
Additional titles
- Original title (Russian)
- Паросодержание двухфазного потока в тяговом участке кипящего реактора VK-50
Publishing Information
- Imprint Pagination
- 15 p.
- Report number
- NIIAR--33(598)
INIS
- Country of Publication
- USSR
- Country of Input or Organization
- USSR
- INIS RN
- 15056723
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COOLANTS; DIAGRAMS; HYDRAULICS; MEDIUM PRESSURE; POWER DENSITY; PRESSURE DEPENDENCE; PRIMARY COOLANT CIRCUITS; SPATIAL DISTRIBUTION; STEAM; TWO-PHASE FLOW; VK-50 REACTOR; VOID FRACTION; VORTICES; WATER
- Descriptors DEC
- BWR TYPE REACTORS; COOLING SYSTEMS; DISTRIBUTION; ENRICHED URANIUM REACTORS; FLUID FLOW; HYDROGEN COMPOUNDS; INFORMATION; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 9 refs.; 11 figs.