Nikolay M. Barbin, S. Titov, Dmitry I. Terentiev, A. Kobelev
The paper presents the results from a thermodynamic analysis of the behavior of Sr and Ca radionuclides in the process of heating radioactive graphite in an air atmosphere. The TERRA software package was used for the thermodynamic analysis in a temperature range of 300 to 3600 K to determine the possible composition of the ionized, gaseous and condensed phases. It has been found that strontium is in the form of condensed SrCl2(c) and gaseous SrCl2 in a temperature range of 300 to 1600 K, and in the form of gaseous SrCl2, SrO, SrCl and Sr and ionized SrCl+, Sr+ and SrO+ when the temperature is increased from 1600 to 3600 K. Calcium is in the form of condensed CaCl2(c), CaUO4(c), CaO(c) and gaseous CaCl2 in the temperature interval between 300 and 2100 K, and in the form of gaseous Ca, CaCl and CaO and ionized Ca+, CaO+ and CaCl+ when the temperature is increased from 2100 to 3600 K. The paper determines the key reactions within individual phases and among condensed, gaseous and ionized phases. The equilibrium constants of their reactions have been calculated. Based on the results obtained, dependence plots are presented for the Sr and Ca radionuclide distribution by phases.
本文介绍了在空气环境中加热放射性石墨过程中 Sr 和 Ca 放射性核素行为的热力学分析结果。热力学分析使用了 TERRA 软件包，温度范围为 300 至 3600 K，以确定电离相、气相和凝聚相的可能组成。研究发现，在 300 至 1600 K 的温度范围内，锶以冷凝态 SrCl2(c) 和气态 SrCl2 的形式存在；当温度从 1600 K 升至 3600 K 时，锶以气态 SrCl2、SrO、SrCl 和 Sr 以及电离态 SrCl+、Sr+ 和 SrO+ 的形式存在。在 300 至 2100 K 的温度区间内，钙以凝结 CaCl2(c)、CaUO4(c)、CaO(c) 和气态 CaCl2 的形式存在；当温度从 2100 K 升至 3600 K 时，钙以气态 Ca、CaCl 和 CaO 以及离子化 Ca+、CaO+ 和 CaCl+ 的形式存在。计算了它们反应的平衡常数。根据所获得的结果，给出了各相 Sr 和 Ca 放射性核素分布的依存图。
{"title":"Computer Simulation of Thermal Processes Involving Sr and Ca Radionuclides in the Process of Heating Radioactive Graphite in an Air Atmosphere","authors":"Nikolay M. Barbin, S. Titov, Dmitry I. Terentiev, A. Kobelev","doi":"10.26583/npe.2023.3.09","DOIUrl":"https://doi.org/10.26583/npe.2023.3.09","url":null,"abstract":"The paper presents the results from a thermodynamic analysis of the behavior of Sr and Ca radionuclides in the process of heating radioactive graphite in an air atmosphere. The TERRA software package was used for the thermodynamic analysis in a temperature range of 300 to 3600 K to determine the possible composition of the ionized, gaseous and condensed phases. It has been found that strontium is in the form of condensed SrCl2(c) and gaseous SrCl2 in a temperature range of 300 to 1600 K, and in the form of gaseous SrCl2, SrO, SrCl and Sr and ionized SrCl+, Sr+ and SrO+ when the temperature is increased from 1600 to 3600 K. Calcium is in the form of condensed CaCl2(c), CaUO4(c), CaO(c) and gaseous CaCl2 in the temperature interval between 300 and 2100 K, and in the form of gaseous Ca, CaCl and CaO and ionized Ca+, CaO+ and CaCl+ when the temperature is increased from 2100 to 3600 K. The paper determines the key reactions within individual phases and among condensed, gaseous and ionized phases. The equilibrium constants of their reactions have been calculated. Based on the results obtained, dependence plots are presented for the Sr and Ca radionuclide distribution by phases.","PeriodicalId":37826,"journal":{"name":"Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika","volume":"94 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139345676","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}
V. Smykov, V. Z. Andrey, Kristina Gennad’evna Legkikh, V. V. Alekseev, P. Z. Victor
{"title":"Reprocessing of Primary and Secondary Coolants During the BN-350 Reactor Decommissioning","authors":"V. Smykov, V. Z. Andrey, Kristina Gennad’evna Legkikh, V. V. Alekseev, P. Z. Victor","doi":"10.26583/npe.2023.3.16","DOIUrl":"https://doi.org/10.26583/npe.2023.3.16","url":null,"abstract":"","PeriodicalId":37826,"journal":{"name":"Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika","volume":"28 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139344121","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}
Artur V. Lyubarskiy, Gennady V. Tokmachev, Irina B. Kuzmina
The paper considers the implementation of the “practical elimination” principle in the design of the Akkuyu NPP with VVER1200 reactors being under construction in Turkey. The “practical elimination” principle is defined as follows: for accident sequences or phenomena that contribute or lead to unacceptable radiological consequences for the public or the environment, it shall be shown with a high level of confidence that their occurrence is highly unlikely. “Practical elimination” is proved predominantly by results of a Level 2 probabilistic safety assessment. The implementation of the “practical elimination” principle was considered at the level of accident sequences leading to a large radioactive release. It has been shown that each accident sequence leading to an unacceptable release has the probability of occurrence below 4.45Е–8 per reactor per year, while their total probability not exceeding the value of 6.17Е–7 per reactor per year. For the phenomena inside the containment area during severe accidents, including hydrogen detonation, a large thermal explosion, direct containment heating, overpressure in the containment volume, and the containment damage at later stages due to the basement melting through, their “practical elimination” has been demonstrated. The paper also considers specific hard-to-assess scenarios of beyond design basis accidents, for which the applicability of the “practical elimination” principle is assessed as well: a major positive reactivity insertion, a rupture of the reactor pressure vessel and other largescale components, damage of fuel elements in the spent fuel pool, severe accidents with the containment bypass or containment failure, and severe accidents accompanied the means for mitigating with their consequences being unavailable. Criteria have been developed and used for the “practical elimination” assessment. A sensitivity analysis was undertaken as part of the Level 2 probabilistic safety assessment which has shown that estimated values slightly depend on the analytical assumptions, as well as on the random change in the parameters that the affect the progression of severe accidents.
{"title":"«Practical Elimination» Principle in the Akkuyu Nuclear Power Plant Design","authors":"Artur V. Lyubarskiy, Gennady V. Tokmachev, Irina B. Kuzmina","doi":"10.26583/npe.2023.3.02","DOIUrl":"https://doi.org/10.26583/npe.2023.3.02","url":null,"abstract":"The paper considers the implementation of the “practical elimination” principle in the design of the Akkuyu NPP with VVER1200 reactors being under construction in Turkey. The “practical elimination” principle is defined as follows: for accident sequences or phenomena that contribute or lead to unacceptable radiological consequences for the public or the environment, it shall be shown with a high level of confidence that their occurrence is highly unlikely. “Practical elimination” is proved predominantly by results of a Level 2 probabilistic safety assessment. The implementation of the “practical elimination” principle was considered at the level of accident sequences leading to a large radioactive release. It has been shown that each accident sequence leading to an unacceptable release has the probability of occurrence below 4.45Е–8 per reactor per year, while their total probability not exceeding the value of 6.17Е–7 per reactor per year. For the phenomena inside the containment area during severe accidents, including hydrogen detonation, a large thermal explosion, direct containment heating, overpressure in the containment volume, and the containment damage at later stages due to the basement melting through, their “practical elimination” has been demonstrated. The paper also considers specific hard-to-assess scenarios of beyond design basis accidents, for which the applicability of the “practical elimination” principle is assessed as well: a major positive reactivity insertion, a rupture of the reactor pressure vessel and other largescale components, damage of fuel elements in the spent fuel pool, severe accidents with the containment bypass or containment failure, and severe accidents accompanied the means for mitigating with their consequences being unavailable. Criteria have been developed and used for the “practical elimination” assessment. A sensitivity analysis was undertaken as part of the Level 2 probabilistic safety assessment which has shown that estimated values slightly depend on the analytical assumptions, as well as on the random change in the parameters that the affect the progression of severe accidents.","PeriodicalId":37826,"journal":{"name":"Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika","volume":"64 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139345623","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}
A.V. Panov, L.N. Komarova, R. L. Elena, Anzhelika Aleklsandrovna Mel’nikova
{"title":"Peculiarities of the exposure dose formation on the population in the most affected regions of russia after the chernobyl NPP accident","authors":"A.V. Panov, L.N. Komarova, R. L. Elena, Anzhelika Aleklsandrovna Mel’nikova","doi":"10.26583/npe.2023.3.06","DOIUrl":"https://doi.org/10.26583/npe.2023.3.06","url":null,"abstract":"","PeriodicalId":37826,"journal":{"name":"Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika","volume":"11 10 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139346951","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}
A. Shmelev, N. Geraskin, V. Apse, G. G. Kulikov, E. G. Kulikov, Vasily B. Glebov
The paper presents the estimates for the possibility for large-scale production of 238 Pu in the core of a VVER-1000 power reactor. The Np-fraction of minor actinides extracted from transuranic radioactive waste is proposed to be used as the starting material. The irradiation device with NpO 2 fuel elements is installed at the reactor core center. The NpO 2 fuel lattice pitch is varied and the irradiation device is surrounded by a heavy moderator layer to create the best possible spectral conditions for large-scale production (~ 3 kg/year) of conditioned plutonium with the required isotopic composition (not less than 85% of 238 Pu and not more than 2 ppm of 236 Pu). Plutonium with such isotopic composition can be used as the thermal source in thermoelectric radioisotope generators and in cardiac pacemakers. It has been demonstrated that the estimated scale of the 238 Pu production in a VVER-type power reactor exceeds considerably the existing scale of its production in research reactors.
{"title":"Assessment of the possibility for large-scale 238Pu production in a VVER-1000 power reactor","authors":"A. Shmelev, N. Geraskin, V. Apse, G. G. Kulikov, E. G. Kulikov, Vasily B. Glebov","doi":"10.26583/npe.2023.3.10","DOIUrl":"https://doi.org/10.26583/npe.2023.3.10","url":null,"abstract":"The paper presents the estimates for the possibility for large-scale production of 238 Pu in the core of a VVER-1000 power reactor. The Np-fraction of minor actinides extracted from transuranic radioactive waste is proposed to be used as the starting material. The irradiation device with NpO 2 fuel elements is installed at the reactor core center. The NpO 2 fuel lattice pitch is varied and the irradiation device is surrounded by a heavy moderator layer to create the best possible spectral conditions for large-scale production (~ 3 kg/year) of conditioned plutonium with the required isotopic composition (not less than 85% of 238 Pu and not more than 2 ppm of 236 Pu). Plutonium with such isotopic composition can be used as the thermal source in thermoelectric radioisotope generators and in cardiac pacemakers. It has been demonstrated that the estimated scale of the 238 Pu production in a VVER-type power reactor exceeds considerably the existing scale of its production in research reactors.","PeriodicalId":37826,"journal":{"name":"Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika","volume":"48 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139345751","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":"Key Technical Solutions for the BN-350 Power Unit That Have Influenced the BN Reactor Design Evolution","authors":"A. K. Aleksey","doi":"10.26583/npe.2023.3.12","DOIUrl":"https://doi.org/10.26583/npe.2023.3.12","url":null,"abstract":"","PeriodicalId":37826,"journal":{"name":"Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika","volume":"20 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"139347046","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}
Renat Ramil’yevich Rayzapov, Aleksey Yevgen’yevich Sobornov, S. Dmitriev, Nikita Vladimirovich Matsin, A. Kotin
{"title":"Experimental Studies into the Non-Isothermal Mixing of Incompressible Liquid Counterflows in a Y-junction","authors":"Renat Ramil’yevich Rayzapov, Aleksey Yevgen’yevich Sobornov, S. Dmitriev, Nikita Vladimirovich Matsin, A. Kotin","doi":"10.26583/npe.2023.1.05","DOIUrl":"https://doi.org/10.26583/npe.2023.1.05","url":null,"abstract":"","PeriodicalId":37826,"journal":{"name":"Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika","volume":"32 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"75254863","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}
A. D. Pavel, N. K. Sergey, A. K. Andrey, S. Sergey, S. Pavel, A. B. Aleksey, D. A. Lukyanov, V. K. Yury, M. S. Aleksandr, V. S. Aleksey, K. Maksim, I. I. Mikhail, S. Andrey, I. D. Vadim
{"title":"Development of a Method for Nondestructive Control of the Helium Concentration in Fuel Elements for Advanced Nuclear Power Plants","authors":"A. D. Pavel, N. K. Sergey, A. K. Andrey, S. Sergey, S. Pavel, A. B. Aleksey, D. A. Lukyanov, V. K. Yury, M. S. Aleksandr, V. S. Aleksey, K. Maksim, I. I. Mikhail, S. Andrey, I. D. Vadim","doi":"10.26583/npe.2023.2.06","DOIUrl":"https://doi.org/10.26583/npe.2023.2.06","url":null,"abstract":"","PeriodicalId":37826,"journal":{"name":"Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika","volume":"1 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"73619475","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":"Emergencies at Nuclear Power Plants for the Period 1952 – 2012, Evaluated According to the International Scale of Nuclear Events INES","authors":"S. Titov, N. M. Barbin","doi":"10.26583/npe.2023.1.08","DOIUrl":"https://doi.org/10.26583/npe.2023.1.08","url":null,"abstract":"","PeriodicalId":37826,"journal":{"name":"Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika","volume":"26 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"87942709","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}
O. Vlasov, I. Zvonova, N. V. Shchukina, Sergey Yurievich Chekin
{"title":"Radioecological Simulation of the 131I Activity Dynamics in the Pasture Vegetation of Mazovia in the Year of the Chernobyl Accident: Reconstruction, Verification, Reliability Assessments","authors":"O. Vlasov, I. Zvonova, N. V. Shchukina, Sergey Yurievich Chekin","doi":"10.26583/npe.2023.2.09","DOIUrl":"https://doi.org/10.26583/npe.2023.2.09","url":null,"abstract":"","PeriodicalId":37826,"journal":{"name":"Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika","volume":"16 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"89079706","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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