Components of Automated Intellectual Systems Supporting Decisions at the Stage of Operation and Equipment Diagnostics of Nuclear Power Units

Yefimov, О.V.; Pylypenko, M.M.; Potanina, Т.V.; Yesipenko, Tetyana; Kavertsev, Valerii; Harkusha, Tetyana

doi:10.46813/2020-125-127

Cited by 4 publications

(2 citation statements)

References 5 publications

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“…The cross-sectional mean velocities of the liquid and vapor phases of the flow are not equal to each other, and the difference in the velocities of the phases in the steadystate mode of motion of the two-phase flow depends on the mass flow rate of the steam-water mixture, its pressure, direction of flow, heating intensity, and other indicators. All this complicates experimental studies and calculations of parameters and hydrodynamic (gasdynamic) characteristics of two-phase flows of a steamwater mixture of a working substance in reactors and steam generators of nuclear power plants [4][5][6][7][8].…”

Section: Introductionmentioning

confidence: 99%

MATHEMATICAL RELATIONSHIPS OF MODELS OF TWO-PHASE FLOWS IN CHANNELS OF REACTORS AND STEAM GENERATORS OF NPP’s FOR CALCULATION OF THEIR HYDRODYNAMIC CHARACTERISTICS

Yefimov¹,

Pylypenko²,

Kavertsev³

et al. 2022

Problems of Atomic Science and Technology

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Two-phase flows of the working substance in the steam-generating channels of reactors of single-circuit NPP’s and steam generators of two- and three-circuit NPP’s represent the joint movement of liquid (feed water) and steam in the form of a steam-water mixture. The forms of movement of two-phase flows are much more diverse, and the laws of their movement are much more complicated than flows of single-phase media, and they are characterized by a large number of parameters. This is due to the fact that when the flow of the steam-water mixture moves in the steam-generating channels, mass exchange processes occur between the liquid and vapor phases of the mixture, in which the volumes of the phases change; the interfaces between the phases of the mixture vary along the length of the channel and often do not have a distinct character. The cross-sectional mean velocities of the liquid and vapor phases of the flow are not equal to each other, and the difference in the velocities of the phases in the steady-state mode of motion of the two-phase flow depends on the mass flow rate of the steam-water mixture, its pressure, direction of flow, heating intensity, and other indicators. All this complicates experimental studies and calculations of parameters and hydrodynamic (gas-dynamic) characteristics of two-phase flows of a steam-water mixture of a working substance in reactors and steam generators of nuclear power plants. The article discusses mathematical relationships for calculating the hydraulic characteristics of two-phase flows of different structures during the movement of a steam-water mixture in the steam-generating channels of reactors and steam generators of nuclear power plants, namely bubble, slug, rod, dispersed. The ratios are given for various designs of the channels of reactors and steam generators.

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Section: Introductionmentioning

confidence: 99%

MATHEMATICAL RELATIONSHIPS OF MODELS OF TWO-PHASE FLOWS IN CHANNELS OF REACTORS AND STEAM GENERATORS OF NPP’s FOR CALCULATION OF THEIR HYDRODYNAMIC CHARACTERISTICS

Yefimov¹,

Pylypenko²,

Kavertsev³

et al. 2022

Problems of Atomic Science and Technology

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“…The main equipment, in turn, should be divided into characteristic nodes. Such a division allows rationally, taking into account the specific features of the functional dependencies between the parameters of each node, to create their mathematical models and carry out optimization of both individual nodes and the main equipment of NPP power units through successive refinement [5].…”

mentioning

confidence: 99%

Optimization of Operating Modes of Power Units of Nuclear Power Plants

Yefimov,

Kavertsev,

Tiutiunyk

et al. 2023

ІДНРС

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The materials of the article consider the main methodological provisions of calculations and optimization of NPP power unit equipment parameters using mathematical modeling methods. For the effective implementation of tasks related to determining the optimal parameters and structures of NPP power unit equipment using mathematical modeling and well-developed multifactor optimization methods, it is necessary to fulfill a number of requirements at their productions. Practice shows that it is impractical to optimize with the help of a single mathematical (simulation) model the entire set of parameters characterizing a given power unit, because with such a formulation, the optimization tasks are often mutually incorrect due to a significant discrepancy in the accuracy of various source information, unequal influence of parameters on the target function, specific differences in the mathematical description of various units and elements of the power unit. In order to effectively optimize the parameters of NPP power units, it is necessary to create a system of interconnected mathematical models, which include: a group of detailed mathematical models of individual units and elements of power unit equipment; more generalized mathematical models for the main equipment of power units built on their basis; complete mathematical model of power units.

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Interval Models of Temperature Characteristics of Superheater Separators in Nuclear Power Plant Units With the Capacity of 1000 Mw

Yefimov¹,

Potanina²,

Kavertsev³

et al. 2022

Problems of Atomic Science and Technology

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The analysis of the influence of changes in the parameters of steam superheater separators SHS-1000 of nuclear power plant units with the capacity of 1000 MW on the efficiency and safety of their operation, including the temperature characteristics at the nominal and partial operating modes of power units, has been carried out. Based on the experimental data of the thermal tests of the power unit, the temperature characteristic of the second stage of the SHS-1000 has been constructed in the form of the dependence of the temperature change of the heated steam at the second stage of the SHS on the change in the operating mode of the power unit. To create a correct mathematical model of this dependence, taking into account the limited amount of experimental data and the uncertainty of information about the structure and the probabilistic nature of measurement error during testing, the use of numerical methods of interval analysis has been proposed. Interval analysis has allowed to obtain an interval model that describes the receiver, which contains all possible values of the dependence of temperature change of the heated steam at the second stage of SHS on the unit operating mode (the electrical load). It has been shown that in conditions of limited initial data and uncertainty of information about it, numerical methods of interval analysis allow to create interval models of operational (energy) characteristics technological processes and equipment of NPP units with the maximum possible correspondence to real processes and objects, which is important to ensure high efficiency and safe operation of power units.

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Components of Automated Intellectual Systems Supporting Decisions at the Stage of Operation and Equipment Diagnostics of Nuclear Power Units

Cited by 4 publications

References 5 publications

MATHEMATICAL RELATIONSHIPS OF MODELS OF TWO-PHASE FLOWS IN CHANNELS OF REACTORS AND STEAM GENERATORS OF NPP’s FOR CALCULATION OF THEIR HYDRODYNAMIC CHARACTERISTICS

MATHEMATICAL RELATIONSHIPS OF MODELS OF TWO-PHASE FLOWS IN CHANNELS OF REACTORS AND STEAM GENERATORS OF NPP’s FOR CALCULATION OF THEIR HYDRODYNAMIC CHARACTERISTICS

Optimization of Operating Modes of Power Units of Nuclear Power Plants

Interval Models of Temperature Characteristics of Superheater Separators in Nuclear Power Plant Units With the Capacity of 1000 Mw

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