Pub Date : 2021-09-26DOI: 10.55176/2414-1038-2021-3-143-157
A. Avdeenkov, O. Achakovskiy
An engineering model has been analyzed for a self-consistent calculation of the growth of an oxide film in circulation circuits with a heavy liquid metal coolant and concentrations of impurities (oxygen, iron, and magnetite) from the point of view of a possible uncertainty in determining the oxygen activity. The modeling of thermohydraulic and physicochemical processes is based on solving the associated three-dimensional equations of hydrodynamics, heat transfer, convective-diffusive transport, and the formation of chemically interacting impurity components in the coolant volume and on the surface of steels. The yield of iron and the formation of magnetite are due precisely to the specifics of self-consistent physicochemical processes in the oxide film and at the interface. There have been conducted model calculations of the influence of the uncertainty of oxygen activity on the speed and the integral yield of iron, which under the given conditions of the oxygen regime after an interaction with oxygen causes the appearance of magnetite. It has been numerically demonstrated that in the saturation mode there is a model-independent characteristic, which is determined by the parabolic constant and thickness of the oxide film characteristic of steel.
{"title":"NUMERICAL AND ANALYTICAL STUDY OF THE FORMATION AND ACCUMULATION OF DEPOSITS ON THE CIRCUIT WITH HLMC WITHIN THE CONSISTENT MODEL FOR PHYSICAL AND CHEMICAL PROCESSES","authors":"A. Avdeenkov, O. Achakovskiy","doi":"10.55176/2414-1038-2021-3-143-157","DOIUrl":"https://doi.org/10.55176/2414-1038-2021-3-143-157","url":null,"abstract":"An engineering model has been analyzed for a self-consistent calculation of the growth of an oxide film in circulation circuits with a heavy liquid metal coolant and concentrations of impurities (oxygen, iron, and magnetite) from the point of view of a possible uncertainty in determining the oxygen activity. The modeling of thermohydraulic and physicochemical processes is based on solving the associated three-dimensional equations of hydrodynamics, heat transfer, convective-diffusive transport, and the formation of chemically interacting impurity components in the coolant volume and on the surface of steels. The yield of iron and the formation of magnetite are due precisely to the specifics of self-consistent physicochemical processes in the oxide film and at the interface. There have been conducted model calculations of the influence of the uncertainty of oxygen activity on the speed and the integral yield of iron, which under the given conditions of the oxygen regime after an interaction with oxygen causes the appearance of magnetite. It has been numerically demonstrated that in the saturation mode there is a model-independent characteristic, which is determined by the parabolic constant and thickness of the oxide film characteristic of steel.","PeriodicalId":20426,"journal":{"name":"PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2021-09-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"87841157","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2021-09-26DOI: 10.55176/2414-1038-2021-3-11-34
A. Egorov, V. Piksaikin, D. Gremyachkin, K. Mitrofanov, V. Mitrofanov
In the present work the estimation of the 8-group delayed neutron energy spectra emitted in the fission of 235U by thermal neutrons have been done. Aggregate delayed neutron spectra that were measured with high resolution in the different time intervals after the thermal neutron irradiation of the 235U sample presented in the IAEA reference database for beta-delayed neutron emission have been used for the estimation process. Due to the lack of the uncertainties for the spectra presented in this database and the necessity of this data in the process of estimation of delayed neutron group spectra at first the estimation of uncertainties of these spectra have been done. In the estimation process the following components of uncertainty have been considered: statistical; the component due to the neutron background; component due to the distinctive features of neutron spectra restoration process measured using spectrometer filled by helium-3 and also the component appearing due to introduction of the correction on the distortion of the neutron spectra as a result of passing through the lead sheilding. Estimation of spectra have been made using the technique based on the Kalman filter that allows to take into account the uncertainties of the input data. Estimation results are shown in the numerical and graphic form.
{"title":"APPLICATION OF KALMAN FILTER TO THE ESTIMATION OF 8-GROUP DE-LAYED NEUTRON SPECTRA FOR THE 235U THERMAL NEUTRON FISSION","authors":"A. Egorov, V. Piksaikin, D. Gremyachkin, K. Mitrofanov, V. Mitrofanov","doi":"10.55176/2414-1038-2021-3-11-34","DOIUrl":"https://doi.org/10.55176/2414-1038-2021-3-11-34","url":null,"abstract":"In the present work the estimation of the 8-group delayed neutron energy spectra emitted in the fission of 235U by thermal neutrons have been done. Aggregate delayed neutron spectra that were measured with high resolution in the different time intervals after the thermal neutron irradiation of the 235U sample presented in the IAEA reference database for beta-delayed neutron emission have been used for the estimation process. Due to the lack of the uncertainties for the spectra presented in this database and the necessity of this data in the process of estimation of delayed neutron group spectra at first the estimation of uncertainties of these spectra have been done. In the estimation process the following components of uncertainty have been considered: statistical; the component due to the neutron background; component due to the distinctive features of neutron spectra restoration process measured using spectrometer filled by helium-3 and also the component appearing due to introduction of the correction on the distortion of the neutron spectra as a result of passing through the lead sheilding. Estimation of spectra have been made using the technique based on the Kalman filter that allows to take into account the uncertainties of the input data. Estimation results are shown in the numerical and graphic form.","PeriodicalId":20426,"journal":{"name":"PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2021-09-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"83480557","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2021-09-26DOI: 10.55176/2414-1038-2021-3-35-48
S. Enin, A. Belozerova, V. Pavlov, T. Chernisheva
A program for refining the energy spectra of neutron radiation in the neutron trap, core and reflector of the SM-3 reactor after modernization using the certified equipment and verified methods is presented in the article. The relevance of the article lies in familiarization with the experimental implementation of the methods in order to compare the experimental neutron-physical characteristics of the reactor before and after the last reconstruction. During the program creation, the previous experience of spectrometric measurements was taken into account, as well as experiments were carried out under conditions close to those of spectrometry after reconstruction. The results of the research are necessary for the planning of irradiation experiments and verification of calculation methods for determining the neutron-physical characteristics. The results of the described researches cover most science and technology areas, many aspects of human practice, including healthcare. The authors presented results of accompanying experiments, which made it possible to work out the regulations and features of short-term measurements. The developed and optimized program of neutron spectrometry in the SM-3 reactor channels will allow to obtain reliable information on the density of neutron fluxes for the first time after modernization to verify analytical data and to optimize the use of the SM-3 reactor facility to increase the production of transplutonium elements and radionuclide products.
{"title":"THE SCHEDULE OF THE NEUTRON FIELDS SPECTROMETRY IN THE SM REACTOR AFTER THE MODERNIZATION","authors":"S. Enin, A. Belozerova, V. Pavlov, T. Chernisheva","doi":"10.55176/2414-1038-2021-3-35-48","DOIUrl":"https://doi.org/10.55176/2414-1038-2021-3-35-48","url":null,"abstract":"A program for refining the energy spectra of neutron radiation in the neutron trap, core and reflector of the SM-3 reactor after modernization using the certified equipment and verified methods is presented in the article. The relevance of the article lies in familiarization with the experimental implementation of the methods in order to compare the experimental neutron-physical characteristics of the reactor before and after the last reconstruction. During the program creation, the previous experience of spectrometric measurements was taken into account, as well as experiments were carried out under conditions close to those of spectrometry after reconstruction. The results of the research are necessary for the planning of irradiation experiments and verification of calculation methods for determining the neutron-physical characteristics. The results of the described researches cover most science and technology areas, many aspects of human practice, including healthcare. The authors presented results of accompanying experiments, which made it possible to work out the regulations and features of short-term measurements. The developed and optimized program of neutron spectrometry in the SM-3 reactor channels will allow to obtain reliable information on the density of neutron fluxes for the first time after modernization to verify analytical data and to optimize the use of the SM-3 reactor facility to increase the production of transplutonium elements and radionuclide products.","PeriodicalId":20426,"journal":{"name":"PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2021-09-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79504439","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2021-09-26DOI: 10.55176/2414-1038-2021-3-174-183
O. Lavrova, R. Askhadullin, A. Legkikh
The oxygen content in liquid sodium is an important normalized parameter that must be controlled during the operation of reactor fasilities with a sodium coolant. When developing a means of monitoring oxygen in liquid sodium, a careful selection of materials from which the sensitive elements of the control device (sensor) will be made is necessary. The criteria for selecting the sensor material include: acceptable corrosion resistance in liquid sodium under operating conditions; sufficient conductivity of oxygen ions at operating temperatures to generate a useful signal; and satisfactory resistance to thermal shock. Thermodynamic analysis allows to select materials that are potentially corrosion resistant to sodium in the sensitive element of the oxygen control sensor. The article presents a thermodynamic analysis of some metal oxide systems in contact with the sodium heat carrier of a sealed non-isothermal circulation circuit and an analysis of the stability of oxide systems in liquid sodium, which are the basis of ceramic sensing elements. It is shown that under certain conditions, deoxidized sodium can partially reduce the oxides of ceramics based on zirconium and hafnium with the addition of oxides of certain lanthanides. In addition, sodium reduces silicon oxide, on the basis of which sitall is produced, which is a candidate material for sealing the sensor sensor element. The analysis is performed using diagrams in the “electromotive force - temperature” coordinates constructed from thermodynamic data.
{"title":"THERMODYNAMIC EVALUATION OF THE OXIDE SYSTEMS STABILITY AS APPLIED TO THE MATERIALS OF THE OXYGEN CONTROL SENSOR IN SODIUM","authors":"O. Lavrova, R. Askhadullin, A. Legkikh","doi":"10.55176/2414-1038-2021-3-174-183","DOIUrl":"https://doi.org/10.55176/2414-1038-2021-3-174-183","url":null,"abstract":"The oxygen content in liquid sodium is an important normalized parameter that must be controlled during the operation of reactor fasilities with a sodium coolant. When developing a means of monitoring oxygen in liquid sodium, a careful selection of materials from which the sensitive elements of the control device (sensor) will be made is necessary. The criteria for selecting the sensor material include: acceptable corrosion resistance in liquid sodium under operating conditions; sufficient conductivity of oxygen ions at operating temperatures to generate a useful signal; and satisfactory resistance to thermal shock. Thermodynamic analysis allows to select materials that are potentially corrosion resistant to sodium in the sensitive element of the oxygen control sensor. The article presents a thermodynamic analysis of some metal oxide systems in contact with the sodium heat carrier of a sealed non-isothermal circulation circuit and an analysis of the stability of oxide systems in liquid sodium, which are the basis of ceramic sensing elements. It is shown that under certain conditions, deoxidized sodium can partially reduce the oxides of ceramics based on zirconium and hafnium with the addition of oxides of certain lanthanides. In addition, sodium reduces silicon oxide, on the basis of which sitall is produced, which is a candidate material for sealing the sensor sensor element. The analysis is performed using diagrams in the “electromotive force - temperature” coordinates constructed from thermodynamic data.","PeriodicalId":20426,"journal":{"name":"PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2021-09-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82284054","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2021-09-26DOI: 10.55176/2414-1038-2021-3-5-10
A. Egorov, D. Gremyachkin, V. Piksaikin, K. Mitrofanov, V. Mitrofanov, U. Kobets, D. Kolesnikov, E. Chaplygin, O. Matveev, I. Sutyagin
Development of the technologies of nuclear energy utilization, particularly involving of the minor actinides nuclides in the fuel cycle, due to the differences of time characteristics of the fissioning systems and the number of neutrons emitted by nuclides in the fission process, including its growth with the growth of primary neutron energy require the increase of accuracy and the volume of nuclear data. In the present work the behavior of the time dependence of delayed neutron intensity is studied for the neutron induced fission of the 237Np with the growth of the excitation energy. In the process of the comparative analysis there have been used the data calculated using GEF code and experimental data. Comparative analysis of the mass distributions of fission fragments for the fission of 237Np by neutrons with energies 1 and 18 MeV shows the difference in the magnitude of the separate masses from 15 times in the region of the asymmetric fission to 100 times in the region of the symmetric fission, that is the evidence of the differences in the time behavior of the decay curves of delayed neutron intensity. Using the set-up, that allows registering the delayed neutrons, installed of the neutron-physical research channel of Tandem-3M accelerator there have been made the measurement of the decay curves of delayed neutron intensity using the primary neutrons with different energy.
{"title":"RESEARCH OF TIME DEPENDENCE OF DELAYED NEUTRON INTENSITY FOR THE FISSION OF 237Np WITH DIFFERENT EXCITATION ENERGY","authors":"A. Egorov, D. Gremyachkin, V. Piksaikin, K. Mitrofanov, V. Mitrofanov, U. Kobets, D. Kolesnikov, E. Chaplygin, O. Matveev, I. Sutyagin","doi":"10.55176/2414-1038-2021-3-5-10","DOIUrl":"https://doi.org/10.55176/2414-1038-2021-3-5-10","url":null,"abstract":"Development of the technologies of nuclear energy utilization, particularly involving of the minor actinides nuclides in the fuel cycle, due to the differences of time characteristics of the fissioning systems and the number of neutrons emitted by nuclides in the fission process, including its growth with the growth of primary neutron energy require the increase of accuracy and the volume of nuclear data. In the present work the behavior of the time dependence of delayed neutron intensity is studied for the neutron induced fission of the 237Np with the growth of the excitation energy. In the process of the comparative analysis there have been used the data calculated using GEF code and experimental data. Comparative analysis of the mass distributions of fission fragments for the fission of 237Np by neutrons with energies 1 and 18 MeV shows the difference in the magnitude of the separate masses from 15 times in the region of the asymmetric fission to 100 times in the region of the symmetric fission, that is the evidence of the differences in the time behavior of the decay curves of delayed neutron intensity. Using the set-up, that allows registering the delayed neutrons, installed of the neutron-physical research channel of Tandem-3M accelerator there have been made the measurement of the decay curves of delayed neutron intensity using the primary neutrons with different energy.","PeriodicalId":20426,"journal":{"name":"PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2021-09-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"74105443","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2021-09-26DOI: 10.55176/2414-1038-2021-3-88-105
O. Vilenskii, S. Dushev, D. Lapshin, E. Novinskii, N. Rusinov
The main results are presented for the analysis of the process of falling of the in-object transportation packaging set (ITPS) in case of fracture of the fixing or slinging elements and estimation of the consequences of ITPS falling during transportation and processing (handling) operations. The ITPS is permitted to transfer to the limiting condition in the result of falling, when its further operation is not acceptable, and recovery of its functional condition is not expedient, excluding the possibility of falling out of the nuclear fuel (NF) or distortion of the relative position of the NF in the ITPS. To reduce the costs at the design stage the following representative calculation research of the ITPS was carried out for dynamic impacts to identify weak points of the design in case of an emergency situation. The computational analysis of falling was carried out using the module for dynamic analysis LS DYNA of ANSYS software, certified by the Rostekhnadzor authorities. LS-DYNA module is designed for computational analysis of highly nonlinear dynamic processes using an explicit integration scheme for dynamic equations.The completed full-scale mathematical 3D modeling permitted to carry out sufficiently deep and detailed analysis of dynamic processes, reducing the design duration, and it permitted to reduce the self-cost of the developed design. The results obtained for different variant of the ITPS falling permitted to analyze the collision process, to determine the values of the plastic deformation appearing in the ITPS elements and to provide recommendations for its modification.
{"title":"ESTIMATION OF THE CONSEQUENCE OF THE ITPS FALLS DURING TRANSPORTATION AND PROCESSING (HANDLING) OPERATIONS","authors":"O. Vilenskii, S. Dushev, D. Lapshin, E. Novinskii, N. Rusinov","doi":"10.55176/2414-1038-2021-3-88-105","DOIUrl":"https://doi.org/10.55176/2414-1038-2021-3-88-105","url":null,"abstract":"The main results are presented for the analysis of the process of falling of the in-object transportation packaging set (ITPS) in case of fracture of the fixing or slinging elements and estimation of the consequences of ITPS falling during transportation and processing (handling) operations. The ITPS is permitted to transfer to the limiting condition in the result of falling, when its further operation is not acceptable, and recovery of its functional condition is not expedient, excluding the possibility of falling out of the nuclear fuel (NF) or distortion of the relative position of the NF in the ITPS. To reduce the costs at the design stage the following representative calculation research of the ITPS was carried out for dynamic impacts to identify weak points of the design in case of an emergency situation. The computational analysis of falling was carried out using the module for dynamic analysis LS DYNA of ANSYS software, certified by the Rostekhnadzor authorities. LS-DYNA module is designed for computational analysis of highly nonlinear dynamic processes using an explicit integration scheme for dynamic equations.The completed full-scale mathematical 3D modeling permitted to carry out sufficiently deep and detailed analysis of dynamic processes, reducing the design duration, and it permitted to reduce the self-cost of the developed design. The results obtained for different variant of the ITPS falling permitted to analyze the collision process, to determine the values of the plastic deformation appearing in the ITPS elements and to provide recommendations for its modification.","PeriodicalId":20426,"journal":{"name":"PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2021-09-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85490503","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2021-06-26DOI: 10.55176/2414-1038-2021-2-167-173
Y. Kryglikov, O. Supotnitskaya, L. Yantseva
An important factor for the analysis of hydrogen safety is to take into account the effect of possible hydrogen combustion on the parameters of NPP containment atmosphere. In order to evaluate this effect a model of adiabatic isochoric complete combustion (AICC) of hydrogen was developed and implemented in the KUPOL-M containment code. With the model of adiabatic isochoric complete combustion of hydrogen included in the KUPOL-M code, this code will become applicable for the VVER NPP safety analysis performed with the aim to estimate possible thermal mechanical loads on the containment in case of hydrogen burning. This model is simple, conservative and based on the laws of conservation of mass and energy. The following assumptions are made in the model of adiabatic isochoric complete combustion of hydrogen: the volume in which burning takes place is constant; there is no heat transfer; the limiting component (in most cases it is hydrogen) burns down completely; intermediate stages of chemical transformations are not considered. The test results of this model on experimental data are presented in the article. There is a good agreement between the data of calculations and experiments in a wide range of hydrogen concentrations in gas mixtures. Based on the test results it can be concluded that implementation of AICC model in the KUPOL-M code allows conservatively evaluating the parameters in the containment atmosphere without significantly increasing the calculation time.
{"title":"CALCULATION OF GAS PARAMETERS IN A NPP CONTAINMENT TAKING INTO ACCOUNT THE ADIABATIC ISOCHORIC COMPLETE COMBUSTION OF HYDROGEN BY THE KUPOL-M CODE","authors":"Y. Kryglikov, O. Supotnitskaya, L. Yantseva","doi":"10.55176/2414-1038-2021-2-167-173","DOIUrl":"https://doi.org/10.55176/2414-1038-2021-2-167-173","url":null,"abstract":"An important factor for the analysis of hydrogen safety is to take into account the effect of possible hydrogen combustion on the parameters of NPP containment atmosphere. In order to evaluate this effect a model of adiabatic isochoric complete combustion (AICC) of hydrogen was developed and implemented in the KUPOL-M containment code. With the model of adiabatic isochoric complete combustion of hydrogen included in the KUPOL-M code, this code will become applicable for the VVER NPP safety analysis performed with the aim to estimate possible thermal mechanical loads on the containment in case of hydrogen burning. This model is simple, conservative and based on the laws of conservation of mass and energy. The following assumptions are made in the model of adiabatic isochoric complete combustion of hydrogen: the volume in which burning takes place is constant; there is no heat transfer; the limiting component (in most cases it is hydrogen) burns down completely; intermediate stages of chemical transformations are not considered. The test results of this model on experimental data are presented in the article. There is a good agreement between the data of calculations and experiments in a wide range of hydrogen concentrations in gas mixtures. Based on the test results it can be concluded that implementation of AICC model in the KUPOL-M code allows conservatively evaluating the parameters in the containment atmosphere without significantly increasing the calculation time.","PeriodicalId":20426,"journal":{"name":"PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2021-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79132248","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2021-06-26DOI: 10.55176/2414-1038-2021-2-116-126
N. Loginov
Three types of magnetohydrodynamic devices using in liquid metal circulating loops are known. These are electromagnetic pumps, flow meters, and throttles. Electromagnetic pumps and throttles are induction type, as a rule, using alternating current and alternating magnetic field. Electromagnetic flowmeters for liquid metals, as a rule, are conduction type using direct current and permanent magnetic field. Every of each device serves one function only. Operating principle and some designs of universal conduction magnetohydrodynamic devices, which are possible provide simultaneously two of three functions, (pump and flow meter, or throttle and flow meter) are described at the paper. They are called pump-flow meter and throttle-flow meter. These devices are proposed for small experimental facilities with flow rate of liquid metal 1-500 l/h and for auxiliary circulating loops of big facilities. Theoretical basis of fulfilment of two function simultaneously and needed mathematical formulas presented at the paper. Three variants of pump-flow meters tested and corresponding results are described.
{"title":"MANIFUNCTIONAL MAGNETOHYDRODYNAMIC DEVICE","authors":"N. Loginov","doi":"10.55176/2414-1038-2021-2-116-126","DOIUrl":"https://doi.org/10.55176/2414-1038-2021-2-116-126","url":null,"abstract":"Three types of magnetohydrodynamic devices using in liquid metal circulating loops are known. These are electromagnetic pumps, flow meters, and throttles. Electromagnetic pumps and throttles are induction type, as a rule, using alternating current and alternating magnetic field. Electromagnetic flowmeters for liquid metals, as a rule, are conduction type using direct current and permanent magnetic field. Every of each device serves one function only. Operating principle and some designs of universal conduction magnetohydrodynamic devices, which are possible provide simultaneously two of three functions, (pump and flow meter, or throttle and flow meter) are described at the paper. They are called pump-flow meter and throttle-flow meter. These devices are proposed for small experimental facilities with flow rate of liquid metal 1-500 l/h and for auxiliary circulating loops of big facilities. Theoretical basis of fulfilment of two function simultaneously and needed mathematical formulas presented at the paper. Three variants of pump-flow meters tested and corresponding results are described.","PeriodicalId":20426,"journal":{"name":"PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2021-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"78256904","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2021-06-26DOI: 10.55176/2414-1038-2021-2-200-217
V. Delnov
The article deals with application of flow patterns and hydrodynamic effects in the course of upgrading distribution header systems (DHS) used in heat exchangers and reactors of nuclear power plants (NPP). Consideration is given to four typical axisymmetric DHSs of flat and cylindrical types, which differ in the ways of fluid supply to the collector and its removal from it. The schematic diagrams of flow patterns are shown for different DHS designs of the cylindrical types with central and lateral fluid inlets of the collector. Besides, the water flow pattern is given for the flow path of various DHS designs of a flat type, also with central and lateral fluid inlets of the collector. Hydrodynamic features of the fluid flow in the DHS have been analyzed. It is shown that in a restricted and free DHS the coolant flow is of a jet nature. The fluid flow in the header is characterized by transformation of some types of jets into others, by the presence of eddy and stagnant zones. The designs of heat exchangers and reactors for nuclear power plants with the considered typical DHS characteristics implemented are presented. The DHS designs upgraded with the use of the indicated patterns and effects are demonstrated. The revealed regularity of liquid distribution at the outlet of the DHS flow paths and the hydrodynamics identity property for axially symmetric DHS with flow reversal are analyzed.
{"title":"APPLICATION OF FLOW PATTERNS AND ACCOUNTING OF HYDRODYNAMIC EFFECTS IN THE COURSE OF UPGRADING DISTRIBUTION HEADER SYSTEMS OF NPP HEAT EXCHANGERS AND REACTORS","authors":"V. Delnov","doi":"10.55176/2414-1038-2021-2-200-217","DOIUrl":"https://doi.org/10.55176/2414-1038-2021-2-200-217","url":null,"abstract":"The article deals with application of flow patterns and hydrodynamic effects in the course of upgrading distribution header systems (DHS) used in heat exchangers and reactors of nuclear power plants (NPP). Consideration is given to four typical axisymmetric DHSs of flat and cylindrical types, which differ in the ways of fluid supply to the collector and its removal from it. The schematic diagrams of flow patterns are shown for different DHS designs of the cylindrical types with central and lateral fluid inlets of the collector. Besides, the water flow pattern is given for the flow path of various DHS designs of a flat type, also with central and lateral fluid inlets of the collector. Hydrodynamic features of the fluid flow in the DHS have been analyzed. It is shown that in a restricted and free DHS the coolant flow is of a jet nature. The fluid flow in the header is characterized by transformation of some types of jets into others, by the presence of eddy and stagnant zones. The designs of heat exchangers and reactors for nuclear power plants with the considered typical DHS characteristics implemented are presented. The DHS designs upgraded with the use of the indicated patterns and effects are demonstrated. The revealed regularity of liquid distribution at the outlet of the DHS flow paths and the hydrodynamics identity property for axially symmetric DHS with flow reversal are analyzed.","PeriodicalId":20426,"journal":{"name":"PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2021-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85656907","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2021-06-26DOI: 10.55176/2414-1038-2021-2-64-81
A. Glebov
The supercritical Water-cooled Reactor (SCWR) was adopted as one of the promising IV-generation reactors within the framework of the international forum “Generation-IV” (MFP). More than 45 organizations in 16 countries with advanced nuclear power are developing SCWR concept proposals for this program. The SCWR concept is based on the implementation of a direct-flow single-circuit scheme of a nuclear power plant, cooled by SCP water. The introduction of this type of nuclear power plant will increase the efficiency up to 45 %, increase the fuel reproduction coefficient, reduce metal consumption and construction volumes, and improve economic and environmental performance. Countries participating in the SCWR MFP consider the development of a reactor with a thermal neutron spectrum and uranium fuel as a priority task, but in the subsequent stages, with increasing problems with the storage of spent nuclear fuel (SNF) and small actinides (SA), it is possible to switch to a reactor with a fast neutron spectrum, MOX fuel and a closed fuel cycle (CFC). Within the framework of the MFP, various versions of SCWR are being developed differing in the parameters of the coolant and its circulation schemes in the core. Groups have been created to study the issues of physics, thermohydraulics, heat transfer, materials, personnel training. Water-cooled reactors research carried out during ~15 years in A.I. Leypunsky Institute for Physics and Power Engineering (IPPE), OKB “Gidropress”, NRC “Kurchatov Institute” with supercritical thermal and fast neutron spectra, it seems more promising to develop a reactor with fast spectrum of neutrons. For ~10 years, IPPE and OKB “Gidropress” have been working together on the VVER-SKD concept project - a single-circuit RC with a coolant SCP with a fast-resonance neutron spectrum with a capacity of Ne = 1700 MW. This rector is recognized as a prospect for the development of VVER technology with the possibility of using uranium fuel and switching in the future to MOX-based fuel (U-Pu-Th) and to SNF. When developing VVER-SKD, it is necessary to solve a complex of scientific and technical problems: development and verification of calculation codes of improved estimation for neutron physics, hydrodynamics and water heat transfer of SCP in fuel assemblies (FA) of the core and throughout the reactor; development of fuel elements and FA structures, justification of their operability; analysis of reactor stability under transient and emergency conditions; selection of heat-resistant structural materials for fuel rods and reactor vessel with high corrosion resistance; justification and development of optimal water-chemical regime, etc. Some of these problems are investigated in bench and loop tests, but to solve most of them and justify the technology for subsequent licensing, it is necessary to create an experimental test reactor. In relation to the VVER-SKD reactor Ne = 1700 MW, the paper presents the results of calculations of fuel cycle
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