zldmЗаводская лаборатория. Диагностика материаловIndustrial laboratory. Diagnostics of materials1028-68612588-0187ООО «Издательство «ТЕСТ-ЗЛ»10.26896/1028-6861-2024-90-10-56-66zldm-2314Research ArticleИССЛЕДОВАНИЕ СТРУКТУРЫ И СВОЙСТВSTRUCTURE AND PROPERTIES INVESTIGATIONИсследование характеристик ползучести корпусной стали 15Х2НМФА-А реактора типа ВВЭР при температурах 500 – 1200 °CResearch of creep parameters of VVER reactor steel 15Kh2NMFA-A AT temperatures of 500 – 1200°CТерентьевЕ. В.TerentyevE. V.

Егор Валериевич Терентьев

111250, Москва, ул. Красноказарменная, д. 14

Egor V. Terentyev

14, Krasnokazarmennaya ul., Moscow, 111250

МарченковА. Ю.MarchenkovA. Yu.

Артём Юрьевич Марченков

111250, Москва, ул. Красноказарменная, д. 14

Artem Yu. Marchenkov

14, Krasnokazarmennaya ul., Moscow, 111250

art-marchenkov@yandex.ruЛоктионовВ. Д.LoktionovV. D.

Владимир Дмитриевич Локтионов

111250, Москва, ул. Красноказарменная, д. 14

Vladimir D. Loktionov

14, Krasnokazarmennaya ul., Moscow, 111250

ЛюбашевскаяИ. В.LyubashevskayaI V.

Ирина Васильевна Любашевская

630090, г. Новосибирск, просп. Акад. Лаврентьева, д. 15

Irina V. Lyubashevskaya

15, Lavrentyev prosp., Novosibirsk, 630090

ЧупринД. В.ChuprinD. V.

Данила Владимирович Чуприн

111250, Москва, ул. Красноказарменная, д. 14

Danila V. Chuprin

15, Lavrentyev prosp., Novosibirsk, 630090

БородавкинаК. Т.BorodavkinaK. T.

Ксения Тимуровна Бородавкина

111250, Москва, ул. Красноказарменная, д. 14

Kseniya T. Borodavkina

14, Krasnokazarmennaya ul., Moscow, 111250

СвиридовГ. Б.SviridovG. B.

Георгий Борисович Свиридов

111250, Москва, ул. Красноказарменная, д. 14

Georgiy B. Sviridov

14, Krasnokazarmennaya ul., Moscow, 111250

Национальный исследовательский университет «МЭИ»РоссияNational Research University «Moscow Power Engineering Institute»Russian FederationИнститут гидродинамики им. М. А. Лаврентьева Сибирского отделения Российской академии наукРоссияLavrentyev Institute of Hydrodynamics of Siberian Branch of Russian Academy of SciencesRussian FederationНациональный исследовательский университет «МЭИ»РоссияLavrentyev Institute of Hydrodynamics of Siberian Branch of Russian Academy of SciencesRussian Federation20242210202490105666Copyright © Терентьев Е.В., Марченков А.Ю., Локтионов В.Д., Любашевская И.В., Чуприн Д.В., Бородавкина К.Т., Свиридов Г.Б., 20242024Терентьев Е.В., Марченков А.Ю., Локтионов В.Д., Любашевская И.В., Чуприн Д.В., Бородавкина К.Т., Свиридов Г.Б.Terentyev E.V., Marchenkov A.Y., Loktionov V.D., Lyubashevskaya I.V., Chuprin D.V., Borodavkina K.T., Sviridov G.B.Данная работа распространяется под лицензией Creative Commons Attribution 4.0.This work is licensed under a Creative Commons Attribution 4.0 License.https://www.zldm.ru/jour/article/view/2314

Исследованы особенности ползучести корпусной стали 15Х2НМФА-А в диапазоне температур 500 – 1200 °C, которые могут быть достигнуты при аварийных режимах работы реакторов типа ВВЭР. Проведен анализ кривых ползучести стали, полученных при испытаниях растяжением образцов с построением параметрической зависимости Ларсена – Миллера. Показано, что в интервале температур 600 – 850 °C обобщенная температурная зависимость Ларсена – Миллера изменяет угол наклона, вследствие чего в этом интервале возникает высокая ошибка в оценке времени до разрушения стали 15Х2НМФА-А в условиях ползучести. Для определения причин изменения сопротивления ползучести в указанном температурном диапазоне исследована микроструктура металла в исходном состоянии и после испытаний на ползучесть методами оптической и сканирующей электронной микроскопии. Установлено, что в интервале температур 600 – 700 °C происходит коагуляция карбонитридов типа V(CN), приводящая к изменению угла наклона параметрической зависимости Ларсена – Миллера. В диапазоне температур Ac1 – Ac3 характеристики ползучести скачкообразно изменяются, что связано с фазовыми превращениями. Обоснована целесообразность разделения параметрической зависимости Ларсена – Миллера на несколько участков в зависимости от температуры с учетом структурных изменений в стали 15Х2НМФА-А, что позволяет повысить точность оценки времени ее разрушения как минимум на порядок. По результатам исследования получена расчетная зависимость предела длительной прочности стали от температуры на базе шести, 24 и 120 ч.

The paper is devoted to the study of the creep characteristics of 15Kh2NMFA-A vessel steel in the temperature range of 500 – 1200 °C, which can be achieved during emergency operating conditions of VVER-type nuclear reactors. An analysis of the creep curves of the 15Kh2NMFA-A steel in the studied temperature range obtained during specimens tensile tests was carried out with the construction of the parametric Larson – Miller relationship. It is shown that in the temperature range of 600 – 850 °C the generalized Larson – Miller temperature dependence has a changed slope, resulting in a high error in estimating the time to fracture of 15Kh2NMFA-A steel under creep conditions in this temperature range. To reveal the reasons for the change in creep resistance in the specified temperature range, the studies of the metal microstructure using optical and scanning electron microscopy on specimens in the initial state and after creep testing were carried out. Studies of the microstructure of steel have shown that in the temperature range of 600 – 700 °C, coagulation of V(CN) type carbonitrides occurs, leading to a change in the slope of the Larson – Miller parametric relationship. It is shown that in the temperature range of Ac1 – Ac3 there is an abrupt change in creep characteristics associated with phase transformations. The feasibility of dividing the Larson – Miller parametric relationship into several sections depending on temperature, taking into account structural changes in the steel, is substantiated, which makes it possible to increase the accuracy of estimating the destruction time of 15Kh2NMFA-A steel by at least an order of magnitude. Based on the results of the study, a calculated dependence of the long-term strength of steel on temperature was obtained on a basis of 6,24 and 120 hours.

сталь 15Х2НМФА-Атяжелая аварияползучестьпараметр Ларсена – Миллерамикроструктуракарбидыразмер зернапредел длительной прочности15Kh2NMFA-A steelsevere accidentcreepLarson-Miller relationshipmicrostructurecarbidesgrain sizecreep-rupture strengthИсследование выполнено в ФГБОУ ВО «НИУ «МЭИ» за счет гранта Российского научного фонда № 23-79-10140, https://rscf.ru/project/23-79-10140ReferencesTheofanous T. G., Liu C., Addition S., et al. In-vessel Coolability and Retention of a Core Melt. Vol. 1. — U.S.A., Illinois: Center for risk studies and Safety, 1996. — 441 p. DOI: 10.2172/491623Theofanous T. G., Liu C., Addition S., et al. In-vessel Coolability and Retention of a Core Melt. Vol. 1. — U.S.A., Illinois: Center for risk studies and Safety, 1996. — 441 p. DOI: 10.2172/491623Theofanous T. G., Angelini S. Natural Convection for In-Vessel Retention at Prototypic Rayleigh Numbers / Nuclear Engineering and Design. 2000. Vol. 200. P. 1 – 9. DOI: 10.1016/S0029-5493(00)00239-9Theofanous T. G., Angelini S. Natural Convection for In-Vessel Retention at Prototypic Rayleigh Numbers / Nuclear Engineering and Design. 2000. Vol. 200. P. 1 – 9. DOI: 10.1016/S0029-5493(00)00239-9Rempe J. L., Knudson D. L., Condie K. G., et al. Corium retention for high power reactors by an in-vessel core catcher in combination with External Reactor Vessel Cooling / Nuclear Engineering and Design. 2004. Vol. 230. P. 293 – 309. DOI: 10.1016/j.nucengdes.2003.11.031Rempe J. L., Knudson D. L., Condie K. G., et al. Corium retention for high power reactors by an in-vessel core catcher in combination with External Reactor Vessel Cooling / Nuclear Engineering and Design. 2004. Vol. 230. P. 293 – 309. DOI: 10.1016/j.nucengdes.2003.11.031Loktionov V., Mukhtarov E., Lyubashevskaya I. Features of heat and deformation behavior of a VVER-600 reactor pressure vessel under conditions of inverse stratification of corium pool and worsened external vessel cooling during the severe accident. Part 1. The effect of the inverse melt stratification and in-vessel top cooling of corium pool on the thermal loads acting on VVER-600’s reactor pressure vessel during a severe accident / Nuclear Engineering and Design. 2018. Vol. 326. P. 320 – 332. DOI: 10.1016/j.nucengdes.2017.11.015Loktionov V., Mukhtarov E., Lyubashevskaya I. Features of heat and deformation behavior of a VVER-600 reactor pressure vessel under conditions of inverse stratification of corium pool and worsened external vessel cooling during the severe accident. Part 1. The effect of the inverse melt stratification and in-vessel top cooling of corium pool on the thermal loads acting on VVER-600’s reactor pressure vessel during a severe accident / Nuclear Engineering and Design. 2018. Vol. 326. P. 320 – 332. DOI: 10.1016/j.nucengdes.2017.11.015Loktionov V., Mukhtarov E., Lyubashevskaya I. Features of heat and deformation behavior of a VVER-600 reactor pressure vessel under conditions of inverse stratification of corium pool and worsened external vessel cooling during the severe accident. Part 2. Creep deformation and failure of the reactor pressure vessel / Nuclear Engineering and Design. 2018. Vol. 327. P. 161 – 171. DOI: 10.1016/j.nucengdes.2017.12.018Loktionov V., Mukhtarov E., Lyubashevskaya I. Features of heat and deformation behavior of a VVER-600 reactor pressure vessel under conditions of inverse stratification of corium pool and worsened external vessel cooling during the severe accident. Part 2. Creep deformation and failure of the reactor pressure vessel / Nuclear Engineering and Design. 2018. Vol. 327. P. 161 – 171. DOI: 10.1016/j.nucengdes.2017.12.018Fil N. S., Borisov L. N., Kurbaev S. S., et al. Analysis of WWER-1000 Core Melt Scenarious using Different Computer Codes / Proceedings of the 10th International Topical Meeting On Nuclear Reactor Thermal Hydraulics (nureth-10), 2003.Fil N. S., Borisov L. N., Kurbaev S. S., et al. Analysis of WWER-1000 Core Melt Scenarious using Different Computer Codes / Proceedings of the 10th International Topical Meeting On Nuclear Reactor Thermal Hydraulics (nureth-10), 2003.Sorokin Yu. S., Shchekoldin V. V., Borisov L. N., Fil N. S. Analysis of typical WWER-1000 Severe Accident scenarios / Proceedings of the 2004 International Congress on Advances in Nuclear Power Plants, 2004. P. 1096 – 1105.Sorokin Yu. S., Shchekoldin V. V., Borisov L. N., Fil N. S. Analysis of typical WWER-1000 Severe Accident scenarios / Proceedings of the 2004 International Congress on Advances in Nuclear Power Plants, 2004. P. 1096 – 1105.Zvonarev Yu. A., Volchek A. M., Kobzar V. L., Budaev M. A. ASTEC application for in-vessel melt retention modeling in VVER plants / Nuclear Engineering and Design. 2014. Vol. 272. P. 224 – 236. DOI: 10.1016/j.nucengdes.2013.06.044Zvonarev Yu. A., Volchek A. M., Kobzar V. L., Budaev M. A. ASTEC application for in-vessel melt retention modeling in VVER plants / Nuclear Engineering and Design. 2014. Vol. 272. P. 224 – 236. DOI: 10.1016/j.nucengdes.2013.06.044Carénini L., Fichot F., Seignour N. Modelling issues related to molten pool behaviour in case of In-Vessel Retention Strategy / Annals of Nuclear Energy. 2018. Vol. 118. P. 363 – 374. DOI: 10.1016/j.anucene.2018.04.032Carénini L., Fichot F., Seignour N. Modelling issues related to molten pool behaviour in case of In-Vessel Retention Strategy / Annals of Nuclear Energy. 2018. Vol. 118. P. 363 – 374. DOI: 10.1016/j.anucene.2018.04.032Gencheva R., Stefanova A., Groudev P., et al. Study of invessel melt retention for VVER-1000/v320 reactor / Nuclear Engineering and Design. 2016. Vol. 298. P. 208 – 217. DOI: 10.1016/j.nucengdes.2015.12.031Gencheva R., Stefanova A., Groudev P., et al. Study of invessel melt retention for VVER-1000/v320 reactor / Nuclear Engineering and Design. 2016. Vol. 298. P. 208 – 217. DOI: 10.1016/j.nucengdes.2015.12.031Mao J. F., Zhu J. W., Bao S. Y., et al. Study on structural failure of RPV with geometric discontinuity under severe accident / Nuclear Engineering and Design. 2016. Vol. 307. P. 354 – 363. DOI: 10.1016/j.nucengdes.2016.07.027Mao J. F., Zhu J. W., Bao S. Y., et al. Study on structural failure of RPV with geometric discontinuity under severe accident / Nuclear Engineering and Design. 2016. Vol. 307. P. 354 – 363. DOI: 10.1016/j.nucengdes.2016.07.027Matejovic P., Barnak M., Bachraty M., et al. Adoption of in-vessel retention concept for VVER440/V213 reactors in Central European Countries / Nuclear Engineering and Design. 2017. Vol. 314. P. 93 – 109. DOI: 10.1016/j.nucengdes.2017.01.015Matejovic P., Barnak M., Bachraty M., et al. Adoption of in-vessel retention concept for VVER440/V213 reactors in Central European Countries / Nuclear Engineering and Design. 2017. Vol. 314. P. 93 – 109. DOI: 10.1016/j.nucengdes.2017.01.015Sarkar A., Sunil S., Kumawat B., et al. High temperature creep behavior of a low alloy Mn-Mo-Ni reactor pressure vessel steel / Journal of Nuclear Materials. 2021. Vol. 557. N 153293. DOI: 10.1016/j.jnucmat.2021.153293Sarkar A., Sunil S., Kumawat B., et al. High temperature creep behavior of a low alloy Mn-Mo-Ni reactor pressure vessel steel / Journal of Nuclear Materials. 2021. Vol. 557. N 153293. DOI: 10.1016/j.jnucmat.2021.153293Nikulin S. A., Rogachev S. O., Belov V. A., et al. Structure and properties of steels for manufacture of core catcher vessel of nuclear reactor / Izv. Vuzov. Cher. Met. 2023. Vol. 66. N 3. P. 356 – 366 [in Russian]. DOI: 10.17073/0368-0797-2023-3-356-366Nikulin S. A., Rogachev S. O., Belov V. A., et al. Structure and properties of steels for manufacture of core catcher vessel of nuclear reactor / Izv. Vuzov. Cher. Met. 2023. Vol. 66. N 3. P. 356 – 366 [in Russian]. DOI: 10.17073/0368-0797-2023-3-356-366Volkov I. A., Igumnov L. A., Tarasov I. S., et al. Evaluating long-term strength of structural elements subjected to thermal-mechanical loading / Problems of Strength and Plasticity. 2018. Vol. 80. N 4. P. 495 – 512 [in Russian]. DOI: 10.32326/1814-9146-2018-80-4-494-512Volkov I. A., Igumnov L. A., Tarasov I. S., et al. Evaluating long-term strength of structural elements subjected to thermal-mechanical loading / Problems of Strength and Plasticity. 2018. Vol. 80. N 4. P. 495 – 512 [in Russian]. DOI: 10.32326/1814-9146-2018-80-4-494-512Gao Z., Lu C., He Y., et al. Influence of phase transformation on the creep deformation mechanism of SA508 Gr. 3 steel for nuclear reactor pressure vessels / Journal of Nuclear Materials. 2019. Vol. 519. P. 292 – 301. DOI: 10.1016/j.jnucmat.2019.04.006Gao Z., Lu C., He Y., et al. Influence of phase transformation on the creep deformation mechanism of SA508 Gr. 3 steel for nuclear reactor pressure vessels / Journal of Nuclear Materials. 2019. Vol. 519. P. 292 – 301. DOI: 10.1016/j.jnucmat.2019.04.006Tardif N., Coret M., Combescure A. Experimental study of the fracture kinetics of a tubular 16MnNiMo5 steel specimen under biaxial loading at 900 and 1000°C. Application to the rupture of a vessel bottom head during a core meltdown accident in a pressurized water reactor / Nuclear Engineering and Design. 2011. Vol. 241. P. 755 – 766. DOI: 10.1016/j.nucengdes.2011.01.026Tardif N., Coret M., Combescure A. Experimental study of the fracture kinetics of a tubular 16MnNiMo5 steel specimen under biaxial loading at 900 and 1000°C. Application to the rupture of a vessel bottom head during a core meltdown accident in a pressurized water reactor / Nuclear Engineering and Design. 2011. Vol. 241. P. 755 – 766. DOI: 10.1016/j.nucengdes.2011.01.026Xie L. J., Ning D., Yang Y. Z. Experimental study on creep characterization and lifetime estimation of RPV material at 723 – 1023 K / Journal of Materials Engineering and Performance. 2017. Vol. 26. P. 644 – 652. DOI: 10.1007/s11665-016-2498-1Xie L. J., Ning D., Yang Y. Z. Experimental study on creep characterization and lifetime estimation of RPV material at 723 – 1023 K / Journal of Materials Engineering and Performance. 2017. Vol. 26. P. 644 – 652. DOI: 10.1007/s11665-016-2498-1Markov S. I., Balikoyev A. G., Dub V. S., et al. The complex research aimed at developing high-strength steels for hull prospective nuclear power, including supercritical coolant parameters / Tyazh. Mashinostr. 2016. N 7 – 8. P. 2 – 8 [in Russian].Markov S. I., Balikoyev A. G., Dub V. S., et al. The complex research aimed at developing high-strength steels for hull prospective nuclear power, including supercritical coolant parameters / Tyazh. Mashinostr. 2016. N 7 – 8. P. 2 – 8 [in Russian].Timofeev M. N., Galyatkin S. N., Fomenko A. V., Shubin O. V. Analysis of the experience in manufacturing the reactor body and the upper block of the VVER-TOI from 15Cr2NiMoVA class 1 and 15Cr2MoVA-A mod. A steels / Tyazh. Mashinostr. 2021. N 9. P. 9 – 17 [in Russian].Timofeev M. N., Galyatkin S. N., Fomenko A. V., Shubin O. V. Analysis of the experience in manufacturing the reactor body and the upper block of the VVER-TOI from 15Cr2NiMoVA class 1 and 15Cr2MoVA-A mod. A steels / Tyazh. Mashinostr. 2021. N 9. P. 9 – 17 [in Russian].Zemzin V. N. Heat resistance of welded joints. — Leningrad: Mashinostroenie, 1972. — 272 p. [in Russian].Zemzin V. N. Heat resistance of welded joints. — Leningrad: Mashinostroenie, 1972. — 272 p. [in Russian].Kucharova K., Sklenicka V., Kvapilova M., Svoboda M. Creep and microstructural processes in a low-alloy 2.25%Cr1.6%W steel (ASTM Grade 23) / Materials Characterization. 2015. Vol. 109. P. 1 – 8. DOI: 10.1016/j.matchar.2015.08.008Kucharova K., Sklenicka V., Kvapilova M., Svoboda M. Creep and microstructural processes in a low-alloy 2.25%Cr1.6%W steel (ASTM Grade 23) / Materials Characterization. 2015. Vol. 109. P. 1 – 8. DOI: 10.1016/j.matchar.2015.08.008Getsov L. B., Semenov A. S., Golubovsky E. R., et al. Features and uniform description of I, II, and III stages of the creep in single-crystal superalloys / Industr. Lab. Mater. Diagn. 2020. Vol. 86. N 3. P. 44 – 54 [in Russian]. DOI: 10.26896/1028-6861-2020-86-3-44-54Getsov L. B., Semenov A. S., Golubovsky E. R., et al. Features and uniform description of I, II, and III stages of the creep in single-crystal superalloys / Industr. Lab. Mater. Diagn. 2020. Vol. 86. N 3. P. 44 – 54 [in Russian]. DOI: 10.26896/1028-6861-2020-86-3-44-54Kim V. A., Lysenko V. V., Afanaseva A. A., Turkmenov Kh. I. Study of the structural degradation of steel 15Kh5M upon continuous duty / Industr. Lab. Mater. Diagn. 2020. Vol. 86. N 1. P. 38 – 43 [in Russian]. DOI: 10.26896/1028-6861-2020-86-1-38-43Kim V. A., Lysenko V. V., Afanaseva A. A., Turkmenov Kh. I. Study of the structural degradation of steel 15Kh5M upon continuous duty / Industr. Lab. Mater. Diagn. 2020. Vol. 86. N 1. P. 38 – 43 [in Russian]. DOI: 10.26896/1028-6861-2020-86-1-38-43Radchenko V. P., Afanas’eva E. A., Saushkin M. N. Prediction of creep and long-term strength of material using a leader sample under ductile fracture conditions / Journal of Applied Mechanics and Technical Physics. 2023. Vol. 64. N 6. P. 199 – 209 [in Russian]. DOI: 10.15372/PMTF202315261Radchenko V. P., Afanas’eva E. A., Saushkin M. N. Prediction of creep and long-term strength of material using a leader sample under ductile fracture conditions / Journal of Applied Mechanics and Technical Physics. 2023. Vol. 64. N 6. P. 199 – 209 [in Russian]. DOI: 10.15372/PMTF202315261Claesson E., Magnusson H., Kohlbrecher J., et al. Carbide Precipitation during Processing of Two Low-Alloyed Martensitic Tool Steels with 0. 11 and 0. 17 V/Mo Ratios Studied by Neutron Scattering, Electron Microscopy and Atom Probe / Metals. 2022. Vol. 12. N 5. P. 758. DOI: 10.3390/met12050758Claesson E., Magnusson H., Kohlbrecher J., et al. Carbide Precipitation during Processing of Two Low-Alloyed Martensitic Tool Steels with 0. 11 and 0. 17 V/Mo Ratios Studied by Neutron Scattering, Electron Microscopy and Atom Probe / Metals. 2022. Vol. 12. N 5. P. 758. DOI: 10.3390/met12050758Gladshtein V. I. The Impact of Metal Micro-Damages on the Lifetime of Cast Casing of the Valve / Industr. Lab. Mater. Diagn. 2017. Vol. 83. N 8. P. 46 – 52 [in Russian].Gladshtein V. I. The Impact of Metal Micro-Damages on the Lifetime of Cast Casing of the Valve / Industr. Lab. Mater. Diagn. 2017. Vol. 83. N 8. P. 46 – 52 [in Russian].Kvapilová M., Ohanková M., Král P., et al. Characterization of creep properties and the microstructure of a service-exposed low alloy CrMoV steel steam pipe / Materials Science and Engineering A. 2022. Vol. 853. P. 143684. DOI: 10.1016/j.msea.2022.143684Kvapilová M., Ohanková M., Král P., et al. Characterization of creep properties and the microstructure of a service-exposed low alloy CrMoV steel steam pipe / Materials Science and Engineering A. 2022. Vol. 853. P. 143684. DOI: 10.1016/j.msea.2022.143684Epishin A. I., Alymov M. I. Determination of the volume fraction of the microporosity in nickel-based superalloy single crystals / Industr. Lab. Mater. Diagn. 2022. Vol. 88. N 11. P. 32 – 40 [in Russian]. DOI: 10.26896/1028-6861-2022-88-11-32-40Epishin A. I., Alymov M. I. Determination of the volume fraction of the microporosity in nickel-based superalloy single crystals / Industr. Lab. Mater. Diagn. 2022. Vol. 88. N 11. P. 32 – 40 [in Russian]. DOI: 10.26896/1028-6861-2022-88-11-32-40Loktionov V., Lyubashevskaya I., Terentyev E. The regularities of creep deformation and failure of the VVER’s pressure vessel steel 15Kh2NMFA-A in air and argon at temperature range 500 – 900 °C / Nuclear Materials and Energy. 2021. Vol. 28. N 101019. DOI: 10.1016/j.nme.2021.101019Loktionov V., Lyubashevskaya I., Terentyev E. The regularities of creep deformation and failure of the VVER’s pressure vessel steel 15Kh2NMFA-A in air and argon at temperature range 500 – 900 °C / Nuclear Materials and Energy. 2021. Vol. 28. N 101019. DOI: 10.1016/j.nme.2021.101019Loktionov V., Lyubashevskaya I., Terentyev E. Regularities of the creep deformation and failure of 15Kh2NMFA-A steel within the temperature range of 900 – 1200°C / International Journal of Pressure Vessels and Piping. 2022. Vol. 199. N 104745. DOI: 10.1016/j.ijpvp.2022.104745Loktionov V., Lyubashevskaya I., Terentyev E. Regularities of the creep deformation and failure of 15Kh2NMFA-A steel within the temperature range of 900 – 1200°C / International Journal of Pressure Vessels and Piping. 2022. Vol. 199. N 104745. DOI: 10.1016/j.ijpvp.2022.104745Loktionov V., Lyubashevskaya I., Sosnin O., Terentyev E. Short-term strength properties and features of high-temperature deformation of VVER reactor pressure vessel steel 15Kh2NMFA-A within the temperature range 20 – 1200°C / Nuclear Engineering and Design. 2019. Vol. 352. N 110188. DOI: 10.1016/j.nucengdes.2019.110188Loktionov V., Lyubashevskaya I., Sosnin O., Terentyev E. Short-term strength properties and features of high-temperature deformation of VVER reactor pressure vessel steel 15Kh2NMFA-A within the temperature range 20 – 1200°C / Nuclear Engineering and Design. 2019. Vol. 352. N 110188. DOI: 10.1016/j.nucengdes.2019.110188Dudko V., Yuzbekova D., Gaidar S., et al. Tempering behavior of novel low-alloy high-strength steel / Metals. 2022. Vol. 12. N 2177. DOI: 10.3390/met12122177Dudko V., Yuzbekova D., Gaidar S., et al. Tempering behavior of novel low-alloy high-strength steel / Metals. 2022. Vol. 12. N 2177. DOI: 10.3390/met12122177Lu C. Y., He Y. M., Yang J. G., et al. An investigation of phase transition on the microstructural characteristic and creep behavior for the SA508 Gr. 3 steel used for nuclear reactor pressure vessels / Materials Science and Engineering A. 2017. Vol. 711. P. 659 – 669. DOI: 10.1016/j.msea.2017.11.073Lu C. Y., He Y. M., Yang J. G., et al. An investigation of phase transition on the microstructural characteristic and creep behavior for the SA508 Gr. 3 steel used for nuclear reactor pressure vessels / Materials Science and Engineering A. 2017. Vol. 711. P. 659 – 669. DOI: 10.1016/j.msea.2017.11.073Baker T. N. Processes, microstructure and properties of vanadium microalloyed steels / Materials Science and Technology. 2009. Vol. 25. P. 1083 – 1107. DOI: 10.1179/174328409X453253Baker T. N. Processes, microstructure and properties of vanadium microalloyed steels / Materials Science and Technology. 2009. Vol. 25. P. 1083 – 1107. DOI: 10.1179/174328409X453253

The authors declare that there are no conflicts of interest present.