The authors propose an approach to the calculation of the levelized unit fuel cost (LUFC) of electricity generation for a fast reactor in a two-component nuclear energy system (NES) with regard for plutonium production. The approach is based on taking into account the additional economic effect, which can be achieved through the sale at the market price of the natural uranium released due to the substitution of thermal reactors by fast reactors with MOX fuel based on the plutonium bred in a fast reactor. This requires considering simultaneously the reactor parts of the fuel cycle for fast and thermal reactors. Relationships have been obtained which connect the key neutronic and fuel characteristics with the NPP and fuel cycle economic performance. The described methodology was used for the computational study of the LUFC for a fast sodium-cooled reactor. Calculations have shown that, in the considered case, taking into account the plutonium production leads to the LUFC reduction by nearly half and, therefore, to a major decrease in the total unit cost of electricity generation (levelized cost of electricity or LCOE).
{"title":"System levelized fuel cost of electricity generation in a two-component nuclear energy system with a closed uranium-plutonium NFC","authors":"A. Zrodnikov, V. Dekusar, O. Gurskaya","doi":"10.3897/nucet.7.78367","DOIUrl":"https://doi.org/10.3897/nucet.7.78367","url":null,"abstract":"The authors propose an approach to the calculation of the levelized unit fuel cost (LUFC) of electricity generation for a fast reactor in a two-component nuclear energy system (NES) with regard for plutonium production. The approach is based on taking into account the additional economic effect, which can be achieved through the sale at the market price of the natural uranium released due to the substitution of thermal reactors by fast reactors with MOX fuel based on the plutonium bred in a fast reactor. This requires considering simultaneously the reactor parts of the fuel cycle for fast and thermal reactors. Relationships have been obtained which connect the key neutronic and fuel characteristics with the NPP and fuel cycle economic performance. The described methodology was used for the computational study of the LUFC for a fast sodium-cooled reactor. Calculations have shown that, in the considered case, taking into account the plutonium production leads to the LUFC reduction by nearly half and, therefore, to a major decrease in the total unit cost of electricity generation (levelized cost of electricity or LCOE).","PeriodicalId":100969,"journal":{"name":"Nuclear Energy and Technology","volume":"21 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2021-12-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85682292","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}
Trouble-free operation of motor-driven valves (MDV) is one of the key factors behind the operating safety of NPPs. As critical components, MDVs are a part of a safety system and a safety-related system. This imposes the highest possible requirements on the MDV reliability. MDVs are the most numerous category of the NPP components. Depending on design, one power unit contains 1500 to 3000 motor-driven valves alone. It follows from an analysis of the NPP failures that many of these are caused by failed motor-driven valves of safety and safety-related systems. The paper presents a description of an automated system for diagnostics of shutoff and control MDVs used in the NPP pipelines. The developed diagnostic algorithms make it possible to take into account the variability of the MDV technical parameters, while taking into account, at the same time, rated restrictions on diagnostic parameters, if any.
{"title":"An expert neural system for diagnostics of motor-driven valves","authors":"E. Trykov, I. Trykova, Konstantin I. Kotsoyev","doi":"10.3897/nucet.7.78339","DOIUrl":"https://doi.org/10.3897/nucet.7.78339","url":null,"abstract":"Trouble-free operation of motor-driven valves (MDV) is one of the key factors behind the operating safety of NPPs. As critical components, MDVs are a part of a safety system and a safety-related system. This imposes the highest possible requirements on the MDV reliability.\u0000 MDVs are the most numerous category of the NPP components. Depending on design, one power unit contains 1500 to 3000 motor-driven valves alone. It follows from an analysis of the NPP failures that many of these are caused by failed motor-driven valves of safety and safety-related systems.\u0000 The paper presents a description of an automated system for diagnostics of shutoff and control MDVs used in the NPP pipelines. The developed diagnostic algorithms make it possible to take into account the variability of the MDV technical parameters, while taking into account, at the same time, rated restrictions on diagnostic parameters, if any.","PeriodicalId":100969,"journal":{"name":"Nuclear Energy and Technology","volume":"38 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2021-12-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"78957748","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}
D. A. Pakholik, O. Kochnov, V. Kolesov, V. V. Fomichev
There are various ways to obtain Mo-99. Some of them are widely used in industrial production, others are in the research stage with the aim of increasing the product yield. The main industrial method for obtaining Mo-99 using a nuclear reactor is the fragmentation method. This method provides for the presence of a uranium target and a nuclear reactor. The target is placed in the channel of the reactor core and irradiated with neutrons for the required time. After that, the target is removed from the channel to the “hot” chamber for the chemical separation of Mo-99. This is how Mo-99 is obtained practically all over the world. The paper considers the fragmentation method for producing Mo-99, which is implemented on the basis of the engineering and technological complex of the VVR-c research nuclear reactor. In order to increase the yield of Mo-99, a modernized model of the “tube-in-tube” target is proposed. The assessment of the production of Mo-99 and the cooling efficiency of the modernized target was carried out. The calculations were performed using the VisualBurnOut and Ansys CFX software packages. Computational studies have shown an increase in the energy release and the amount of the produced Mo-99 isotope in the target of the modernized design. In the most stressed zones, the target wall temperature exceeds the water saturation temperature. Surface boiling occurs in these zones. As a result, turbulization and mixing of the near-wall boundary water layer increases. This improves heat dissipation.
{"title":"Increasing the production of the Mo-99 isotope by modernizing the design of targets irradiated in the experimental channels of the VVR-c reactor","authors":"D. A. Pakholik, O. Kochnov, V. Kolesov, V. V. Fomichev","doi":"10.3897/nucet.7.78338","DOIUrl":"https://doi.org/10.3897/nucet.7.78338","url":null,"abstract":"There are various ways to obtain Mo-99. Some of them are widely used in industrial production, others are in the research stage with the aim of increasing the product yield. The main industrial method for obtaining Mo-99 using a nuclear reactor is the fragmentation method. This method provides for the presence of a uranium target and a nuclear reactor. The target is placed in the channel of the reactor core and irradiated with neutrons for the required time. After that, the target is removed from the channel to the “hot” chamber for the chemical separation of Mo-99. This is how Mo-99 is obtained practically all over the world.\u0000 The paper considers the fragmentation method for producing Mo-99, which is implemented on the basis of the engineering and technological complex of the VVR-c research nuclear reactor. In order to increase the yield of Mo-99, a modernized model of the “tube-in-tube” target is proposed. The assessment of the production of Mo-99 and the cooling efficiency of the modernized target was carried out. The calculations were performed using the VisualBurnOut and Ansys CFX software packages. Computational studies have shown an increase in the energy release and the amount of the produced Mo-99 isotope in the target of the modernized design. In the most stressed zones, the target wall temperature exceeds the water saturation temperature. Surface boiling occurs in these zones. As a result, turbulization and mixing of the near-wall boundary water layer increases. This improves heat dissipation.","PeriodicalId":100969,"journal":{"name":"Nuclear Energy and Technology","volume":"50 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2021-12-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"75810003","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}
Public support is one of the major challenges for maintaining a sustainable nuclear power program for any country. Although Bangladesh’s decision to build its maiden nuclear power plant (NPP) has received significant scholarly attention, the study regarding public perception is largely ignored. To fill this gap, this study investigated how Bangladeshis view the government’s decision to build NPPs. The study evaluated Bangladeshi youth’s knowledge, belief, and attitude toward the development of nuclear power. Applying the survey research technique, we found that 49% of the 450 respondents were positive toward NPPs, while 12% had no idea about NPPs. Women, in comparison to men, were found to have less knowledge of nuclear energy. Additionally, 41% of the respondents believed that the decision for establishing the country’s first NPP at Rooppur was right. However, 54% of the respondents expressed concerns over the safety, security, and sustainability of NPPs. Most importantly, a significant distrust among the respondents was observed in the capability of the regulator and operator for maintaining the NPP in a safe, secured, and sustainable manner. The study concludes that more policy actions are necessary to increase public support for nuclear power.
{"title":"Knowledge, belief, and attitude of Bangladeshi youth toward the development of nuclear power","authors":"M. Islam, A. Khan, Md. Sohel Rana","doi":"10.3897/nucet.7.69414","DOIUrl":"https://doi.org/10.3897/nucet.7.69414","url":null,"abstract":"Public support is one of the major challenges for maintaining a sustainable nuclear power program for any country. Although Bangladesh’s decision to build its maiden nuclear power plant (NPP) has received significant scholarly attention, the study regarding public perception is largely ignored. To fill this gap, this study investigated how Bangladeshis view the government’s decision to build NPPs. The study evaluated Bangladeshi youth’s knowledge, belief, and attitude toward the development of nuclear power. Applying the survey research technique, we found that 49% of the 450 respondents were positive toward NPPs, while 12% had no idea about NPPs. Women, in comparison to men, were found to have less knowledge of nuclear energy. Additionally, 41% of the respondents believed that the decision for establishing the country’s first NPP at Rooppur was right. However, 54% of the respondents expressed concerns over the safety, security, and sustainability of NPPs. Most importantly, a significant distrust among the respondents was observed in the capability of the regulator and operator for maintaining the NPP in a safe, secured, and sustainable manner. The study concludes that more policy actions are necessary to increase public support for nuclear power.","PeriodicalId":100969,"journal":{"name":"Nuclear Energy and Technology","volume":"78 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2021-12-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"80273991","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}
As of today, nuclear power together with hydropower provides three-quarters of global low-carbon electricity generation. Over the past 60 years since the time of its inception, the use of nuclear power has reduced CO2 emissions by over 60 gigatonnes. There is no doubt that nuclear power can play a major, and maybe even a decisive role in decarbonizing the electricity sector, as it is evident from the current energy mix of some European countries, especially France, and major economic powers like the Unites States, Russia and South Korea. It is also evident that in most advanced economies nuclear power has entered a phase of gradual decline with little new investment coming into new projects, regardless of the world’s desperate need for more low-carbon electricity. Although existing reactor and their corresponding fuel cycle technologies have enabled the global nuclear power fleet to reach ~ 400 GWe of net installed capacity, there is growing concern that the scale of NPP shutdowns expected in Europe and North America could offset new capacity additions in Asian markets. Theoretically, renewable energy could fill the void left by reactors taken offline but there is strong evidence that the potential of wind and solar for global decarbonization is limited by material, land and economic constraints. Large-scale renewable systems would also require massive energy storage capacity that would hamper economic sustainability of the energy supply for developing countries. Taking into account the potential benefits of developing nuclear power, some countries are determined to expand its share in their energy mix through technological innovation and application of new strategies, directed at improving or completely resolving current issues related to economics, environmental concerns or non-proliferation of nuclear weapons. There are many states in the world today pursuing some sort of nuclear power development. A limited number of countries envision expanding or transforming their nuclear energy system using truly game-changing strategies based on innovative reactor, fuel cycle and waste management technologies. The focus of this paper is to give an overview of the approaches to large-scale nuclear power development being applied today in Russia, China, USA and India.
{"title":"Global outlook on large-scale nuclear power development strategies","authors":"E. Adamov, V. Rachkov, A. Kashirsky, A. Orlov","doi":"10.3897/nucet.7.74217","DOIUrl":"https://doi.org/10.3897/nucet.7.74217","url":null,"abstract":"As of today, nuclear power together with hydropower provides three-quarters of global low-carbon electricity generation. Over the past 60 years since the time of its inception, the use of nuclear power has reduced CO2 emissions by over 60 gigatonnes. There is no doubt that nuclear power can play a major, and maybe even a decisive role in decarbonizing the electricity sector, as it is evident from the current energy mix of some European countries, especially France, and major economic powers like the Unites States, Russia and South Korea. It is also evident that in most advanced economies nuclear power has entered a phase of gradual decline with little new investment coming into new projects, regardless of the world’s desperate need for more low-carbon electricity. Although existing reactor and their corresponding fuel cycle technologies have enabled the global nuclear power fleet to reach ~ 400 GWe of net installed capacity, there is growing concern that the scale of NPP shutdowns expected in Europe and North America could offset new capacity additions in Asian markets. Theoretically, renewable energy could fill the void left by reactors taken offline but there is strong evidence that the potential of wind and solar for global decarbonization is limited by material, land and economic constraints. Large-scale renewable systems would also require massive energy storage capacity that would hamper economic sustainability of the energy supply for developing countries. Taking into account the potential benefits of developing nuclear power, some countries are determined to expand its share in their energy mix through technological innovation and application of new strategies, directed at improving or completely resolving current issues related to economics, environmental concerns or non-proliferation of nuclear weapons. There are many states in the world today pursuing some sort of nuclear power development. A limited number of countries envision expanding or transforming their nuclear energy system using truly game-changing strategies based on innovative reactor, fuel cycle and waste management technologies. The focus of this paper is to give an overview of the approaches to large-scale nuclear power development being applied today in Russia, China, USA and India.","PeriodicalId":100969,"journal":{"name":"Nuclear Energy and Technology","volume":"2 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2021-12-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"87443810","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}
{"title":"Professor Igor Pioro on his 65th birthday","authors":"G. Tikhomirov","doi":"10.3897/nucet.7.78206","DOIUrl":"https://doi.org/10.3897/nucet.7.78206","url":null,"abstract":"<jats:p />","PeriodicalId":100969,"journal":{"name":"Nuclear Energy and Technology","volume":"31 2","pages":""},"PeriodicalIF":0.0,"publicationDate":"2021-12-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"91554981","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}
M. Tuchkov, P. V. Povarov, A. I. Tikhonov, Margarita M. Litvak
This article is focused on the current issue of developing an operator information support system (OISS) for the Novovoronezh NPP II project. One of the main reasons to raise this topic is the MCR operator’s overload with data due to the greatly increased information flows related to the VVER-1200 Process I&C compared to the serially produced VVER-1000 power units. The other important reason, in the authors’ opinion, is the increased volume of existing procedures in hard copy due to the strengthened requirements for their registration and attempts to describe all possible failures and deviations in the programs and plant evolution sheet, which complicates the work on them. In the era of ubiquitous digitalization, the paper procedures can only distract the attention of the operator, who is overloaded with information even without that. The obvious solution is to create a system providing automatic collection and analysis of information. In addition, the functionality of the operator information support system allows the use of operating experience, thus minimizing the impact of the human factor. The lack of knowledge or experience could be especially challenging with procedures being applied infrequently, for example, for starting up and shutting down the unit. The authors consider the development and functionality of interactive procedures and applicable requirements for them. Particular attention is paid to the ergonomics of the workplace and the convenience of operating personnel working with an interactive procedure. Since the transition from the paper version of the programs can cause problems with reading the procedures and, ultimately, lead to the failure of the unit start-up time, the personnel of the operating station were directly involved in the development of the interactive programs. Based on the review results, conclusions were made about the correctness of the approaches in developing the interactive procedures and validated solutions to be disseminated for all routine operations.
{"title":"Development and validation of the interactive unit start-up procedure as a software tool in the implementation of the operator information support system at the NVNPP","authors":"M. Tuchkov, P. V. Povarov, A. I. Tikhonov, Margarita M. Litvak","doi":"10.3897/nucet.7.73182","DOIUrl":"https://doi.org/10.3897/nucet.7.73182","url":null,"abstract":"This article is focused on the current issue of developing an operator information support system (OISS) for the Novovoronezh NPP II project. One of the main reasons to raise this topic is the MCR operator’s overload with data due to the greatly increased information flows related to the VVER-1200 Process I&C compared to the serially produced VVER-1000 power units. The other important reason, in the authors’ opinion, is the increased volume of existing procedures in hard copy due to the strengthened requirements for their registration and attempts to describe all possible failures and deviations in the programs and plant evolution sheet, which complicates the work on them. In the era of ubiquitous digitalization, the paper procedures can only distract the attention of the operator, who is overloaded with information even without that. The obvious solution is to create a system providing automatic collection and analysis of information. In addition, the functionality of the operator information support system allows the use of operating experience, thus minimizing the impact of the human factor. The lack of knowledge or experience could be especially challenging with procedures being applied infrequently, for example, for starting up and shutting down the unit. The authors consider the development and functionality of interactive procedures and applicable requirements for them. Particular attention is paid to the ergonomics of the workplace and the convenience of operating personnel working with an interactive procedure. Since the transition from the paper version of the programs can cause problems with reading the procedures and, ultimately, lead to the failure of the unit start-up time, the personnel of the operating station were directly involved in the development of the interactive programs. Based on the review results, conclusions were made about the correctness of the approaches in developing the interactive procedures and validated solutions to be disseminated for all routine operations.","PeriodicalId":100969,"journal":{"name":"Nuclear Energy and Technology","volume":"29 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2021-09-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"90157245","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}
I. Tormyshev, A. Gulevich, Vladimir A. Yeliseev, V. Stogov
The article discusses the neutron flux stability in the core of a high-power sodium-cooled fast reactor (of the BN-type) without feedbacks. The importance of this problem for high-power BN-type reactors is associated with the specific features of the layout of their cores, including a large diameter and height/diameter ratio about 5. The technique used to substantiate the stability of neutron fields is based on the analysis of the spectrum of the matrix of the system of spatial kinetics equations describing the core of a high-power BN-type reactor without feedbacks. A computational model of the spatial kinetics of a high-power BN-type reactor has been developed in the modal approximation based on the representation of an unsteady flux as a sum of orthogonal functions multiplied by time-dependent amplitudes. The eigenfunctions of the conditionally critical problem are used in the diffusion approximation, which in the discrete case form a complete system. The spectrum of the matrix of the system of ordinary differential equations describing the spatial kinetics of the reactor has been calculated. It is shown that the neutron flux in the core of a high-power BN-type reactor without feedbacks is stable. Test calculations have illustrated the damping of perturbations of the power distribution for a reactor in a critical state.
{"title":"Assessment of the neutron flux stability in a high power BN-type reactor in terms of modal spatial kinetics","authors":"I. Tormyshev, A. Gulevich, Vladimir A. Yeliseev, V. Stogov","doi":"10.3897/nucet.7.73488","DOIUrl":"https://doi.org/10.3897/nucet.7.73488","url":null,"abstract":"The article discusses the neutron flux stability in the core of a high-power sodium-cooled fast reactor (of the BN-type) without feedbacks. The importance of this problem for high-power BN-type reactors is associated with the specific features of the layout of their cores, including a large diameter and height/diameter ratio about 5. The technique used to substantiate the stability of neutron fields is based on the analysis of the spectrum of the matrix of the system of spatial kinetics equations describing the core of a high-power BN-type reactor without feedbacks. A computational model of the spatial kinetics of a high-power BN-type reactor has been developed in the modal approximation based on the representation of an unsteady flux as a sum of orthogonal functions multiplied by time-dependent amplitudes. The eigenfunctions of the conditionally critical problem are used in the diffusion approximation, which in the discrete case form a complete system. The spectrum of the matrix of the system of ordinary differential equations describing the spatial kinetics of the reactor has been calculated. It is shown that the neutron flux in the core of a high-power BN-type reactor without feedbacks is stable. Test calculations have illustrated the damping of perturbations of the power distribution for a reactor in a critical state.","PeriodicalId":100969,"journal":{"name":"Nuclear Energy and Technology","volume":"134 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2021-09-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"84022965","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}
N. V. Gorin, Aleksey A. Yekidin, Olga S. Golovikhina
Population supports the need for switching to green power, which is most often understood to mean the use of solar and wind energy. It would be however a mistake to think that solar and wind power plants will solve in full the problem of uninterrupted power supply for all sectors of economy due to the instability of generation modes and the scale of such energy production. Experts suggest that the only possible way to address global energy and environmental issues is further evolution of nuclear power. Nuclear power is not listed explicitly as a national priority project but it is a component of the Science national project and is expected to contribute to the implementation of the Ecology, Education, and International Cooperation and Export projects. In the context of the Ecology project, nuclear power is capable to play a key role in preventing environmental contamination. In the framework of the International Cooperation and Export project, it is possible to export high-technology fast neutron reactors. The experience of interaction with the interested public, and the developed and implemented occupational training programs will provide for the shaping of radiological literacy among young people as part of the Education project.
{"title":"Nuclear power in Russia’s national projects","authors":"N. V. Gorin, Aleksey A. Yekidin, Olga S. Golovikhina","doi":"10.3897/nucet.7.72393","DOIUrl":"https://doi.org/10.3897/nucet.7.72393","url":null,"abstract":"Population supports the need for switching to green power, which is most often understood to mean the use of solar and wind energy. It would be however a mistake to think that solar and wind power plants will solve in full the problem of uninterrupted power supply for all sectors of economy due to the instability of generation modes and the scale of such energy production. Experts suggest that the only possible way to address global energy and environmental issues is further evolution of nuclear power. Nuclear power is not listed explicitly as a national priority project but it is a component of the Science national project and is expected to contribute to the implementation of the Ecology, Education, and International Cooperation and Export projects. In the context of the Ecology project, nuclear power is capable to play a key role in preventing environmental contamination. In the framework of the International Cooperation and Export project, it is possible to export high-technology fast neutron reactors. The experience of interaction with the interested public, and the developed and implemented occupational training programs will provide for the shaping of radiological literacy among young people as part of the Education project.","PeriodicalId":100969,"journal":{"name":"Nuclear Energy and Technology","volume":"217 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2021-09-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"76596239","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}
Artyom Z. Gayazov, A. Leshchenko, V. P. Smirnov, P. A. Ilyin, V. G. Teplov
Introduction. The paper addresses studies on the accumulation of combustible gases during underwater handling simulations for the leaky spent nuclear fuel from the AM reactor. Two fuel compositions were studied- uranium-molybdenum dispersed in magnesium and uranium carbide dispersed in calcium. Methods. The 137Cs release rate was measured during underwater storage of the uranium-molybdenum fuel. The kinetics of hydrogen release for both fuels and methane release for the carbide SNF were obtained. The kinetics approximate most with exponential dependences that formally correspond to first-order chemical reactions. A contribution of radiolytic hydrogen to the gases generated during the experiments was estimated. It was demonstrated that the determining source of the gases is the chemical interaction between the spent fuel and the water. The experiment with the uranium-molybdenum fuel demonstrated a pronounced passivation effect of the chemical processes on the fuel surface due to insoluble corrosion products. For the carbide SNF, an incubation period of about 20 hours was observed followed by an intensive release of hydrogen and methane. Results. The obtained results were subject to a comparative analysis against publications on the behavior of the fuel components in water. Conclusion. The findings can be applied to justify fire and explosion safety of underwater handling techniques for the damaged spent nuclear fuel with the considered fuel compositions (the spent fuel from reactors AM, AMB, EGP-6, etc.), e.g., to justify underwater preparations of the AMB spent fuel for reprocessing.
{"title":"Study on combustible gas generation and radionuclide release during underwater handling of the AM reactor spent fuel","authors":"Artyom Z. Gayazov, A. Leshchenko, V. P. Smirnov, P. A. Ilyin, V. G. Teplov","doi":"10.3897/nucet.7.73491","DOIUrl":"https://doi.org/10.3897/nucet.7.73491","url":null,"abstract":"Introduction. The paper addresses studies on the accumulation of combustible gases during underwater handling simulations for the leaky spent nuclear fuel from the AM reactor. Two fuel compositions were studied- uranium-molybdenum dispersed in magnesium and uranium carbide dispersed in calcium.\u0000 Methods. The 137Cs release rate was measured during underwater storage of the uranium-molybdenum fuel. The kinetics of hydrogen release for both fuels and methane release for the carbide SNF were obtained. The kinetics approximate most with exponential dependences that formally correspond to first-order chemical reactions.\u0000 A contribution of radiolytic hydrogen to the gases generated during the experiments was estimated. It was demonstrated that the determining source of the gases is the chemical interaction between the spent fuel and the water.\u0000 The experiment with the uranium-molybdenum fuel demonstrated a pronounced passivation effect of the chemical processes on the fuel surface due to insoluble corrosion products. For the carbide SNF, an incubation period of about 20 hours was observed followed by an intensive release of hydrogen and methane.\u0000 Results. The obtained results were subject to a comparative analysis against publications on the behavior of the fuel components in water.\u0000 Conclusion. The findings can be applied to justify fire and explosion safety of underwater handling techniques for the damaged spent nuclear fuel with the considered fuel compositions (the spent fuel from reactors AM, AMB, EGP-6, etc.), e.g., to justify underwater preparations of the AMB spent fuel for reprocessing.","PeriodicalId":100969,"journal":{"name":"Nuclear Energy and Technology","volume":"135 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2021-09-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"86191433","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}
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