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|Title:||Brittle fracture strength analysis for reactor pressure vessel of VVER-1000 reactor unit|
|Authors:||Ovsenev, Alexander Evgenievich|
Permikin, Anton Andreevich
Balachkov, Maxim Mikhailovich
Belyavskiy, S. V.
|Keywords:||ANSYS; brittle fracture strength; VVER-1000|
|Publisher:||Tomsk Polytechnic University|
|Citation:||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.].|
|Abstract:||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.|
|Appears in Collections:||Journal of Economics and Social Sciences|
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