Process models and calculation of temperature field in resistance furnaces of silicon carbide production

Kuzevanov, V.S.; Zakozhurnikov, S S; Zakozhurnikova, G S; Garyayev, A.B.

doi:10.17588/2072-2672.2017.4.021-029

Cited by 4 publications

(4 citation statements)

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“…The core is described as a continuous medium with weighted average temperatures in the calculated cells. The heat conduction equation in the form (Kuzevanov et al 2017, Kuzevanov andPodgorny 2019a, b) is used as the energy conservation equation:…”

Section: Homogeneous Core Energy Conservation Equationmentioning

confidence: 99%

“…Another thing is a homogeneous core, which, moreover, is presented as a continuous medium. For such an core, the energy equation can be written in the form of the heat conduction equation (Kuzevanov et al 2017, Kuzevanov andPodgorny 2019a, b). The numerical solution of this equation can be arranged as an efficient procedure with a small computation time at the computing power available to any user.…”

Section: Introductionmentioning

confidence: 99%

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Real-time temperature field recovery of a heterogeneous reactor based on the results of calculations in a homogeneous core

Kuzevanov¹,

Podgorny²

2022

NUCET

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Advanced pressurized water reactors are the main part of a new generation of nuclear power plant projects under development that provide cost-effective power production for various needs (Yemelyanov et al. 1982, Klimov 2002, Boyko et al. 2005, Baklushin 2011, Bays et al. 2019, Nuclear Technology Review 2019). The innovative technologies are aimed at improving the safety and reliability as well as at reducing the cost of NPPs. At the same time, improvements in design, technological and layout solutions are focused primarily on the reactor core. Assessments of the efficiency of these improvements are preceded by numerical simulations of the processes in the core, in particular heat generation and sink, with account for the difference between the study object and the standard version tested in operational practice. The authors of the article propose a method for calculating the temperature field in the core of a heterogeneous reactor (using the example of a pressurized water reactor), which makes it possible to quickly assess the level of temperature safety of various changes in the core and has the necessary speed for analyzing transients in real time. This method is based on the energy equation for an equivalent homogeneous core in the form of a heat equation that takes into account the main features of the simulated heterogeneous structure. The procedure for recovering the temperature field of a heterogeneous reactor uses the analytical relation obtained in this work for the heat sink function, taking into account inter-fuel element heat leakage losses. Calculations of temperature fields in the model of the PWR type reactor (The Westinghouse Pressurized Water Reactor Nuclear Plant 1984) were carried out in stationary and transient operating modes. The calculation results were compared with the results of CFD simulation. The area of competing use of the temperature field recovery method was indicated.

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Section: Homogeneous Core Energy Conservation Equationmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Real-time temperature field recovery of a heterogeneous reactor based on the results of calculations in a homogeneous core

Kuzevanov¹,

Podgorny²

2022

NUCET

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“…A check was carried out on the performance of the model describing the process of condensation of moisture transferred in the filtration process of the gaseous component in the reaction zone of the charge. The check was based on numerical experiments on the program for calculating the temperature regimes of production, describing the drying of the wet mixture, filtration and chemical transformations in the production of silicon carbide [19][20][21]. The algorithm for calculating the temperature fields [22] of this program as a submodel included the procedure for taking into account the condensation of moisture transferred from the evaporation zone to the condensation region.…”

Section: Introductionmentioning

confidence: 99%

Peculiarities of Heat and Mass Transfer in Porous Moistened Mediums at High Thermal Loads

Kuzevanov¹,

Zakozhurnikova²,

Zakozhurnikov³

2020

SSP

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“…Distributions of flowrate and thermal parameters of coolant inside cooling channels of high-temperature helium-cooled nuclear reactor were investigated in details in (Podgorny and Kuzevanov 2017, 2018. Analysis was performed of different principles of core profiling intended to maintain constant the following parameters:…”

Section: Introductionmentioning

confidence: 99%

Temperature field in gas-cooled reactor core in transient conditions under different approaches to mass flow profiling

Kuzevanov¹,

Podgorny²

2019

NUCET

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Positive effect of profiling the gas-cooled reactor core within the framework of the GT-MHR project was investigated in (Podgorny and Kuzevanov 2017, Kuzevanov and Podgorny 2017, 2018). The necessity arises to supplement already implemented analysis of equilibrium conditions of core operation with investigation of effects of profiling on the temperature field in transient modes of reactor core operation. The present paper is dedicated to the investigation of development of transients in gas-cooled nuclear reactor core subject to the implementation of different principles of core profiling. Investigation of transients in reactor core represents complex problem, solution of which by conducting direct measurements is beyond the resources available to the authors. Besides the above, numerical simulation based on advanced CFD software complexes (ANSYS 2016, 2016a, 2016b, Shaw 1992, Anderson et al. 2009, Petrila and Trif 2005, Mohammadi and Pironneau 1994) is also fairly demanding in terms of required computer resources. The algorithm for calculating temperature fields using the model where the reactor core is represented as the solid medium with gas voids was developed by the authors and the assumption was made that heat transfer due to molecular heat conductivity can be described by thermal conductivity equation written for continuous medium with thermal physics parameters equivalent to respective parameters of porous object in order to get the possibility of obtaining prompt solutions of this type of problems. Computer code for calculating temperature field in gas-cooled reactor in transient operation modes was developed based on the suggested algorithm. Proprietary computation code was verified by comparing the results of numerous calculations with results of CFD-modeling of respective transients in the object imitating the core of gas-cooled nuclear reactor. The advantage of the developed computer code is the possibility of real-time calculation of evolution of conditions in complex configurations of gas-cooled reactor cores with different channel diameters. This allows using the computer code in the calculations of transients in loops of reactor facility as a whole, in particular for developing reactor simulators. Results are provided of calculations of transients for reactor core imitating the core of gas-cooled nuclear reactor within the framework of GT-MHR project performed for different approaches to profiling coolant mass flow. Results of calculations unambiguously indicate the significant difference of temperature regimes during transients in the reactor core with and without profiling and undeniable enhancement of reliability of nuclear reactor (Design of the Reactor Core 2005, International Safeguards 2014, Safety of Nuclear Power Plants 2014) with profiling of coolant mass flow in the reactor core as a whole.

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Process models and calculation of temperature field in resistance furnaces of silicon carbide production

Cited by 4 publications

References 1 publication

Real-time temperature field recovery of a heterogeneous reactor based on the results of calculations in a homogeneous core

Real-time temperature field recovery of a heterogeneous reactor based on the results of calculations in a homogeneous core

Peculiarities of Heat and Mass Transfer in Porous Moistened Mediums at High Thermal Loads

Temperature field in gas-cooled reactor core in transient conditions under different approaches to mass flow profiling

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Process models and calculation of temperature field in resistance furnaces of silicon carbide production

Cited by 4 publications

References 1 publication

﻿Real-time temperature field recovery of a heterogeneous reactor based on the results of calculations in a homogeneous core

﻿Real-time temperature field recovery of a heterogeneous reactor based on the results of calculations in a homogeneous core

Peculiarities of Heat and Mass Transfer in Porous Moistened Mediums at High Thermal Loads

Temperature field in gas-cooled reactor core in transient conditions under different approaches to mass flow profiling

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Real-time temperature field recovery of a heterogeneous reactor based on the results of calculations in a homogeneous core

Real-time temperature field recovery of a heterogeneous reactor based on the results of calculations in a homogeneous core