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Brittle fracture strength analysis for reactor pressure vessel of VVER-1000 reactor unit

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Заглавие Brittle fracture strength analysis for reactor pressure vessel of VVER-1000 reactor unit
 
Автор Ovsenev, Alexander Evgenievich
Permikin, Anton Andreevich
Balachkov, Maxim Mikhailovich
Belyavskiy, S. V.
 
Тематика ANSYS
brittle fracture strength
VVER-1000
 
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.
 
Дата 2020-06-30T09:26:56Z
2020-06-30T09:26:56Z
2020
 
Тип Article
Journal article (info:eu-repo/semantics/article)
Published version (info:eu-repo/semantics/publishedVersion)
 
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
 
Язык en
 
Связанные ресурсы Journal of Economics and Social Sciences. 2020. № 16
 
Права Open access (info:eu-repo/semantics/openAccess)
Attribution-NonCommercial 4.0 International
https://creativecommons.org/licenses/by-nc/4.0/
 
Формат application/pdf
 
Издатель Tomsk Polytechnic University
 
Источник Journal of Economics and Social Sciences