A. Vorobeva, I. V. Moskovchenko, R. Mukhamadeev, Vladimir Viktorovich Sergeev, A. P. Suvorov, V. Timofeev, Eugeny Sergeevich Nizenta, Vladislav Albertovich Titarenko, O. Golosov, Nataliya Vladimirovna Glushkova
{"title":"Computational Analysis of Thermal-Hydraulic Parameters of Storage Pools of the Bilibino NPP During Long-Term Storage of Spent Nuclear Fuel","authors":"A. Vorobeva, I. V. Moskovchenko, R. Mukhamadeev, Vladimir Viktorovich Sergeev, A. P. Suvorov, V. Timofeev, Eugeny Sergeevich Nizenta, Vladislav Albertovich Titarenko, O. Golosov, Nataliya Vladimirovna Glushkova","doi":"10.26583/npe.2023.1.04","DOIUrl":"https://doi.org/10.26583/npe.2023.1.04","url":null,"abstract":"","PeriodicalId":37826,"journal":{"name":"Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika","volume":"75 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"74422059","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":"Оценка нейтронно-физических свойств активной зоны реактора ВВЭР-1000 при использовании регенерированного уран-плутониевого топлива","authors":"V. S. Viktor","doi":"10.26583/npe.2023.2.02","DOIUrl":"https://doi.org/10.26583/npe.2023.2.02","url":null,"abstract":"","PeriodicalId":37826,"journal":{"name":"Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika","volume":"86 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"81223794","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}
R. A. Kurskiy, D. Safonov, O. Zabusov, A. Frolov, D. A. Maltsev, Aleksandr Viktorovich Rozhkov, A. Shishkin
{"title":"Evolution of the Hydride Structure in Irradiated E110 Alloy in the Process of Thermomechanical Treatment Simulating Supercritical Dry Storage Conditions","authors":"R. A. Kurskiy, D. Safonov, O. Zabusov, A. Frolov, D. A. Maltsev, Aleksandr Viktorovich Rozhkov, A. Shishkin","doi":"10.26583/npe.2023.1.09","DOIUrl":"https://doi.org/10.26583/npe.2023.1.09","url":null,"abstract":"","PeriodicalId":37826,"journal":{"name":"Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika","volume":"29 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85347565","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}
The paper is devoted to refining the Lawson criterion for three scenarios of using D-3He fuel in fusion reactors (fully catalyzed and non-catalysed D-D cycles and a D-3He cycle with 3He self-supply). To this end, a new parameterization of the D + 3He → p + 4He fusion reaction cross-section and astrophysical factor has been developed based on the effective radius approximation (Landau-Smorodinsky-Bethe approximation), which is a model-free theoretical approach to investigating near-threshold nuclear reactions, including resonant reactions. In the framework of this approximation, experimental data from studies in the NACRE II and EXFOR libraries, believed to provide the most reliable results to date, have been described within the accuracy declared in the studies in question in the energy range of 0 to 1000 keV, and the fusion reactivity averaged over the Maxwell distribution has been calculated. The results obtained are in good agreement with the calculations based on the R-matrix theory and the NACRE II fusion reactivity data. For the fully catalyzed D-D cycle and the cycle with 3He self-supply, the Lawson criterion and the triple Lawson criterion have been calculated based on solving the equations of the stationary process kinetics in a fusion reactor for three fuel ions (D, 3He, and T) taking into account the potential for external supply of 3He and p and 4He impurity ions removed from the reaction zone. The parameters of the triple Lawson criterion found are as follows: nτT = 6.42∙1016 cm-3∙s∙keV (T = 54 keV) for the fully catalyzed D-D cycle, nτT = 1.03∙1017 cm-3∙s∙keV (T = 45 keV) for the cycle with 3He self-supply, and nτT = 4.89∙1016 cm-3∙s∙keV (T = 67 keV) for the non-catalyzed D-D cycle with equimolar D-3He fuel.
{"title":"Lawson Criterion for Different Scenarios of Using D-3 He Fuel in Fusion Reactors","authors":"A. I. Godes, V. L. Shablov","doi":"10.26583/npe.2023.2.11","DOIUrl":"https://doi.org/10.26583/npe.2023.2.11","url":null,"abstract":"The paper is devoted to refining the Lawson criterion for three scenarios of using D-3He fuel in fusion reactors (fully catalyzed and non-catalysed D-D cycles and a D-3He cycle with 3He self-supply). To this end, a new parameterization of the D + 3He → p + 4He fusion reaction cross-section and astrophysical factor has been developed based on the effective radius approximation (Landau-Smorodinsky-Bethe approximation), which is a model-free theoretical approach to investigating near-threshold nuclear reactions, including resonant reactions. In the framework of this approximation, experimental data from studies in the NACRE II and EXFOR libraries, believed to provide the most reliable results to date, have been described within the accuracy declared in the studies in question in the energy range of 0 to 1000 keV, and the fusion reactivity averaged over the Maxwell distribution has been calculated. The results obtained are in good agreement with the calculations based on the R-matrix theory and the NACRE II fusion reactivity data. For the fully catalyzed D-D cycle and the cycle with 3He self-supply, the Lawson criterion and the triple Lawson criterion have been calculated based on solving the equations of the stationary process kinetics in a fusion reactor for three fuel ions (D, 3He, and T) taking into account the potential for external supply of 3He and p and 4He impurity ions removed from the reaction zone. The parameters of the triple Lawson criterion found are as follows: nτT = 6.42∙1016 cm-3∙s∙keV (T = 54 keV) for the fully catalyzed D-D cycle, nτT = 1.03∙1017 cm-3∙s∙keV (T = 45 keV) for the cycle with 3He self-supply, and nτT = 4.89∙1016 cm-3∙s∙keV (T = 67 keV) for the non-catalyzed D-D cycle with equimolar D-3He fuel.","PeriodicalId":37826,"journal":{"name":"Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika","volume":"97 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"77330435","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":"Verification of the Possibility to Use the Variational Method for Estimating Nuclear Concentration Uncertanties in a Burnup Problem","authors":"Valerij Vasil’evich Kolesov, A. N. Pisarev","doi":"10.26583/npe.2023.1.13","DOIUrl":"https://doi.org/10.26583/npe.2023.1.13","url":null,"abstract":"","PeriodicalId":37826,"journal":{"name":"Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika","volume":"131 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79014128","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}
Artem Zuferovich Gaiazov, Oleg Z. Gaiazov, Viacheslav Yu. Kozlov, Sergey V. Pavlov, Aleksandr A. Samsonov
One of the safety requirements regarding the shipping cask for spent nuclear fuel is that its leak-tightness should be maintained by preserving the cask body structural integrity and the sealing system tightness under normal and accident transportation conditions. The cask under design has a cylindrical process penetration (port) in its bottomб which is sealed using a plug with a radial seal composed of two rubber O-rings. The cask sealing assembly design was justified by the ANSYS LS-DYNA code calculation results. In particular, the strains of the cask components were calculated when dropped from a height of 1 m with the sealing assembly hitting a vertical bar. The cask was concluded to be leak-tight or leaky based on the strain nature and amount. To verify the adequacy of the results, computer-aided and realistic simulations were undertaken with a 1/2.5 scale mockup cask dropped on a bar from a height of 1 m. The computational and experimental results show a good agreement in terms of the impact response accelerations (overloads) for the mockup cask and bar collision and in terms of the plastic strains for the key components of the mockup bottom port sealing assembly. This proves the adequacy of the numerical cask model that has been developed and the efficiency of the LS-DYNA simulations. The inner rubber O ring compression is reduced by the plastic strains in the cask’s bottom port area, leading to a loose inner radial seal, as shown by the calculations. But the outer seal remains leak-tight, ensur - ing so the mockup cask tightness. The physical test results have also confirmed that the mockup cask remains leak-tight.
{"title":"Calculation and Experimental Studies for the Spent Nuclear Fuel Shipping Cask Sealing Assembly","authors":"Artem Zuferovich Gaiazov, Oleg Z. Gaiazov, Viacheslav Yu. Kozlov, Sergey V. Pavlov, Aleksandr A. Samsonov","doi":"10.26583/npe.2023.2.07","DOIUrl":"https://doi.org/10.26583/npe.2023.2.07","url":null,"abstract":"One of the safety requirements regarding the shipping cask for spent nuclear fuel is that its leak-tightness should be maintained by preserving the cask body structural integrity and the sealing system tightness under normal and accident transportation conditions. The cask under design has a cylindrical process penetration (port) in its bottomб which is sealed using a plug with a radial seal composed of two rubber O-rings. The cask sealing assembly design was justified by the ANSYS LS-DYNA code calculation results. In particular, the strains of the cask components were calculated when dropped from a height of 1 m with the sealing assembly hitting a vertical bar. The cask was concluded to be leak-tight or leaky based on the strain nature and amount. To verify the adequacy of the results, computer-aided and realistic simulations were undertaken with a 1/2.5 scale mockup cask dropped on a bar from a height of 1 m. The computational and experimental results show a good agreement in terms of the impact response accelerations (overloads) for the mockup cask and bar collision and in terms of the plastic strains for the key components of the mockup bottom port sealing assembly. This proves the adequacy of the numerical cask model that has been developed and the efficiency of the LS-DYNA simulations. The inner rubber O ring compression is reduced by the plastic strains in the cask’s bottom port area, leading to a loose inner radial seal, as shown by the calculations. But the outer seal remains leak-tight, ensur - ing so the mockup cask tightness. The physical test results have also confirmed that the mockup cask remains leak-tight.","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":"83056061","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}
Gleb Vladislavovich Karpovich, Yurij Alekseevich Kazansky, A. B. Kirill, Kirill Alekseevich Isanov, Nikita Olegovich Kushnir
{"title":"Влияние библиотек оцененных ядерных данных на результаты расчёта выгорания топлива с минорными актинидами в реакторе ВВЭР","authors":"Gleb Vladislavovich Karpovich, Yurij Alekseevich Kazansky, A. B. Kirill, Kirill Alekseevich Isanov, Nikita Olegovich Kushnir","doi":"10.26583/npe.2023.2.05","DOIUrl":"https://doi.org/10.26583/npe.2023.2.05","url":null,"abstract":"","PeriodicalId":37826,"journal":{"name":"Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika","volume":"37 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"78910429","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. Ekidin, V. Povarov, S. Rosnovskiy, L. V. Sizova, M. Pyshkina, A. Vasilyev, Maksim Evgenievich Vasyanovich, E. Nazarov, Anton Viktorovich Pudovkin, V. Kozhemyakin
{"title":"Improvement of the System of Dosimetric Control of Neutron Exposure of Staff of Novovoronezh Nuclear Power Plant","authors":"A. Ekidin, V. Povarov, S. Rosnovskiy, L. V. Sizova, M. Pyshkina, A. Vasilyev, Maksim Evgenievich Vasyanovich, E. Nazarov, Anton Viktorovich Pudovkin, V. Kozhemyakin","doi":"10.26583/npe.2023.1.07","DOIUrl":"https://doi.org/10.26583/npe.2023.1.07","url":null,"abstract":"","PeriodicalId":37826,"journal":{"name":"Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika","volume":"40 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"84743846","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. M. Arkhangelsky, Yuliya S. Daichenkova, Mikhail A. Kalugin, Dmitry S. Oleynik, D. Shkarovsky, Georgy Tikhomirov
The paper considers a computational study of the importance function effect on the accuracy of calculating the effec - tive fraction of delayed neutrons, β eff , and generation time of instantaneous neutrons using the MCU Monte Carlo code based on the example of three criticality experiments from the ICSBEP handbook. In the MCU code, the importance function has a piecewise constant form: the computational model is broken down into a finite number of registration objects
{"title":"The Effect of the Importance Function Resolution on the Accuracy of Calculating the Functionals of the Neutron Kinetics in Water Critical Assemblies by Monte Carlo Method","authors":"D. M. Arkhangelsky, Yuliya S. Daichenkova, Mikhail A. Kalugin, Dmitry S. Oleynik, D. Shkarovsky, Georgy Tikhomirov","doi":"10.26583/npe.2023.2.01","DOIUrl":"https://doi.org/10.26583/npe.2023.2.01","url":null,"abstract":"The paper considers a computational study of the importance function effect on the accuracy of calculating the effec - tive fraction of delayed neutrons, β eff , and generation time of instantaneous neutrons using the MCU Monte Carlo code based on the example of three criticality experiments from the ICSBEP handbook. In the MCU code, the importance function has a piecewise constant form: the computational model is broken down into a finite number of registration objects","PeriodicalId":37826,"journal":{"name":"Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika","volume":"1127 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"87195849","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}
The paper presents a correlation model of high-temperature zirconium alloy oxidation in a mixture of gases (steam, nitrogen and oxygen) for the weight gain calculation of the oxidized sample. The essence of the model consists in using the linear interpolation between the kinetic constants of oxidation in pure gases to describe the oxidation kinetics in gas mixtures. The approach allows one to describe the oxygen weight gain with different contents of gases in steam, nitrogen and oxygen mixtures. The model was validated against experimental data on oxidation in an air-steam mixture in a proportion of 50% to 50% of the volume. For temperatures of 1200 °C and 1400 °C, prior to the 625th second, the deviation between the experimental data and the simulation results is not more than 18%; for 800 °C, prior to the 14th hour, the deviation between the experimental data and the simulation results is not more than 40%. Besides the air-steam mixture, the paper presents the results of the weight gain calculation using the proposed model for oxidation in an oxygen-nitrogen mixture and in a steam-oxygen mixture at 800 °C and 1400 °C.
{"title":"Simulation of High-Temperature Zirconium Alloy Oxidation in a Nitrogen, Oxygen and Steam Mixture","authors":"Aleksey Pavlovich Dolgodvorov","doi":"10.26583/npe.2023.1.12","DOIUrl":"https://doi.org/10.26583/npe.2023.1.12","url":null,"abstract":"The paper presents a correlation model of high-temperature zirconium alloy oxidation in a mixture of gases (steam, nitrogen and oxygen) for the weight gain calculation of the oxidized sample. The essence of the model consists in using the linear interpolation between the kinetic constants of oxidation in pure gases to describe the oxidation kinetics in gas mixtures. The approach allows one to describe the oxygen weight gain with different contents of gases in steam, nitrogen and oxygen mixtures. The model was validated against experimental data on oxidation in an air-steam mixture in a proportion of 50% to 50% of the volume. For temperatures of 1200 °C and 1400 °C, prior to the 625th second, the deviation between the experimental data and the simulation results is not more than 18%; for 800 °C, prior to the 14th hour, the deviation between the experimental data and the simulation results is not more than 40%. Besides the air-steam mixture, the paper presents the results of the weight gain calculation using the proposed model for oxidation in an oxygen-nitrogen mixture and in a steam-oxygen mixture at 800 °C and 1400 °C.","PeriodicalId":37826,"journal":{"name":"Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika","volume":"295 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2023-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"75892300","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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