Critical heat flux in a rod bundle cooled by forced flow of steam-water mixture under steady-state and transient conditions
- 1. Gosudarstvennyj Nauchno-Issledovatel'skij Ehnergeticheskij Inst., Moscow (USSR)
Description
Techniques and results were described of an investigation on critical heat exchange in rod assemblies with uniform and cosinusoidal heat transfers along the rod length under stationary and emergency decrease of coolant flow rate at the assembly inlet. The study was performed for operating conditions of WWER reactors. Experiments were carried out with four assemblies, heated lengths 1000, 1800 and 2500 mm. Three assemblies had longitudinally uniform heat transfer, and one stepwise heat emission, maximum in the middle (imitation of cosinusoidal heat emission). Tests on assemblies with longitudinally uniform heat emission were run under 105-190 atm, mass velocities 530-3230 kg/m2sec, relative inlet enthalpies from -0.9 to -0.02 and relative outlet enthalpies from -0.18 to 0.68. Tests on assemblies with cosinusoidal heat emission were run under 105 and 170 atm, mass velocities 510-2000 kg/m2sec, relative inlet enthalpies from -0.39 to -0.06, and relative outlet enthalpies from 0.15 to 0.74. The final data were compared with those of other authors
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Additional details
Additional titles
- Original title (Russian)
- Кризис теплообмена при вынужденном течении пароводяной смеси в сборке стержней в стационарных и нестационарных режимах
Publishing Information
- Imprint Title
- Seminar TF-74. Studies on the critical heat fluxes in fuel element clusters
- Imprint Pagination
- p. 67-78.
- Report number
- INIS-mf--3908
Conference
- Title
- Seminar TF-74 on studies of critical heat fluxes in fuel element clusters.
- Dates
- 29 Jan - 1 Feb 1974.
- Place
- Moscow, USSR.
INIS
- Country of Publication
- USSR
- Country of Input or Organization
- USSR
- INIS RN
- 9392315
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCURACY; COMPARATIVE EVALUATIONS; CRITICAL HEAT FLUX; DATA; DIAGRAMS; ENTHALPY; FLOW RATE; FUEL ELEMENT CLUSTERS; HIGH PRESSURE; LABORATORY EQUIPMENT; PRESSURE DEPENDENCE; TWO-PHASE FLOW; WATER; WATER VAPOR; WWER TYPE REACTORS
- Descriptors DEC
- ENRICHED URANIUM REACTORS; FLUID FLOW; FLUIDS; FUEL ASSEMBLIES; GASES; HEAT FLUX; HYDROGEN COMPOUNDS; INFORMATION; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; VAPORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 6 refs.; 9 figs. Imprint:Seminar TF-74. Issledovaniya kriticheskikh teplovykh potokov v puchkakh sterzhnej .