Open AccessLong-term operation of a boiling pressure vessel and its internals
Author(s) -
Otso Cronvall
Publication year - 2019
Publication title -
rakenteiden mekaniikka
Language(s) - English
Resource type - Journals
eISSN - 1797-5301
pISSN - 0783-6104
DOI - 10.23998/rm.76141
Subject(s) - reactor pressure vessel , boiling , pressure vessel , nuclear engineering , nuclear power plant , brittleness , boiling water reactor , materials science , corium , degradation (telecommunications) , brittle fracture , fracture (geology) , environmental science , forensic engineering , mechanics , engineering , heat transfer , composite material , nuclear physics , physics , thermodynamics , telecommunications
This study concerns the long-term operation (LTO) of a boiling water reactor (BWR) reactor pressure vessel (RPV) and its internals. The main parts of this study are: survey on the susceptibility to degradation mechanisms, and computational time limited ageing analyses (TLAAs). The ageing of nuclear power plants (NPPs) emphasizes the need to anticipate the possible degradation mechanisms. The BWR survey on the susceptibility to these mechanisms uses the RPVs and significant internals of the Olkiluoto power plant units OL1 and OL2 as a pilot project. For the components that screened in, the potential to brittle, ductile or other degradation is determined. This was carried out by applying structural mechanics and fracture mechanics procedures. Only some most significant cases and results are presented here.