Brittle fracture strength analysis for reactor pressure vessel of VVER-1000 reactor unit
Электронный архив ТПУ
Информация об архиве | Просмотр оригиналаПоле | Значение | |
Заглавие |
Brittle fracture strength analysis for reactor pressure vessel of VVER-1000 reactor unit
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Автор |
Ovsenev, Alexander Evgenievich
Permikin, Anton Andreevich Balachkov, Maxim Mikhailovich Belyavskiy, S. V. |
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Тематика |
ANSYS
brittle fracture strength VVER-1000 |
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Описание |
At the moment, 11 nuclear power plants (NPP) are under operation in the Russian Federation. More than half of the reactor units used are VVER-1000 reactors. NPP is a complex engineering structure consisting of plenty of complex equipment. Equipment operates under severe conditions: hard radiation, high temperatures, and high pressure. Nuclear reactor has a finite lifespan of 30 years. Most nuclear power plants based on VVER-1000 reactors have almost exhausted their lifespan. Therefore, these reactors require a life extension analysis. This paper demonstrates an analysis of brittle fracture strength for VVER-1000 reactor pressure vessel. According to the findings, calculated parameters do not outreach the 10 % limit.
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Дата |
2020-06-30T09:26:56Z
2020-06-30T09:26:56Z 2020 |
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Тип |
Article
Journal article (info:eu-repo/semantics/article) Published version (info:eu-repo/semantics/publishedVersion) |
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Идентификатор |
Brittle fracture strength analysis for reactor pressure vessel of VVER-1000 reactor unit / A. E. Ovsenev, A. A. Permikin, M. M. Balachkov, S. V. Belyavskiy // Journal of Economics and Social Sciences. — 2020. — № 16. — [6 p.].
2312-2978 http://earchive.tpu.ru/handle/11683/62043 |
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Язык |
en
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Связанные ресурсы |
Journal of Economics and Social Sciences. 2020. № 16
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Права |
Open access (info:eu-repo/semantics/openAccess)
Attribution-NonCommercial 4.0 International https://creativecommons.org/licenses/by-nc/4.0/ |
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Формат |
application/pdf
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Издатель |
Tomsk Polytechnic University
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Источник |
Journal of Economics and Social Sciences
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