Numerical and experimental investigation of 3D coolant temperature distribution in the hot legs of primary circuit of reactor plant with WWER-1000
Creators
- 1. JSC ''Atomtechenergo'', Novovoronezh Filial ''Novovoronezhatomtechenergo'', Novovoronezh (Russian Federation)
- 2. JSC ''Atomtechenergo'', Mytishi (Russian Federation)
- 3. NSC ''Kharkov Institute of Physics and Technology'', The Science and Technical Establishment ''Nuclear Fuel Cycle'', Kharkov (Ukraine)
Description
Nowadays the demands for accuracy of determining the weighted mean reactor power significantly increases due to implementing programs aimed at increasing installed power at nuclear power plants with WWER-1000 reactors. This accuracy strongly depends on the coolant temperature stratification in the primary circuit pipes, especially in the hot legs. Thus, the acute problem is to investigate the phenomenon on the basis of the full-scale tests experimental data and the calculated data of computational fluid dynamics simulations. The paper presents the full-scale experimental data on the coolant temperature distribution in the hot legs obtained via I and C systems, primarily via in-core monitoring system. These data were obtained at the pilot operation stage of Unit 4 Kalinin nuclear power plant in a stationary mode at nominal power level. To present the results of calculating simulation for the same mode CFD codes are used.
Additional details
Publishing Information
- Journal Title
- Kerntechnik (1987)
- Journal Volume
- 80
- Journal Issue
- 4
- Journal Page Range
- p. 366-372
- ISSN
- 0932-3902
- CODEN
- KERNEU
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 46116732
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTERIZED SIMULATION; COOLANTS; FLUID MECHANICS; NUCLEAR POWER PLANTS; PIPES; PRIMARY COOLANT CIRCUITS; TEMPERATURE DISTRIBUTION; THREE-DIMENSIONAL CALCULATIONS; WWER TYPE REACTORS
- Descriptors DEC
- COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; MECHANICS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SIMULATION; THERMAL POWER PLANTS; THERMAL REACTORS; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS