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

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

Opis bibliograficzny
Parent link:Journal of Economics and Social Sciences: electronic scientific journal/ Institute of Humanities, Social Sciences and Technologies.— .— Tomsk: TPU, 2012-2021.— 2312-2978
№ 16.— 2020.— [6 p.]
Kolejni autorzy: Ovsenev A. E. Alexander Evgenievich, Permikin A. A. Anton Andreevich, Balachkov M. M. Maxim Mikhailovich, Belyavskiy S. V.
Streszczenie:Title screen
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.
Język:angielski
Wydane: 2020
Seria:Экономические науки
Hasła przedmiotowe:
труды учёных ТПУ
электронный ресурс
ANSYS
brittle fracture strength
VVER-1000
Dostęp online:http://earchive.tpu.ru/handle/11683/62043
Format: Elektroniczne Rozdział
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=585417

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