Long-Term Operation of BWR RPV and Its Internals

Article PVP2018-84541

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

Abstract

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 susceptibility to degradation mechanisms, and computational time limited ageing analyses (TLAAs). The ageing of nuclear power plants (NPPs) emphasises the need to anticipate the possible degradation mechanisms. The BWR survey on susceptibility to these uses the OL1/OL2 RPVs and significant internals as a pilot project. It is not necessary to carry out the TLAAs for all components. Some components were excluded from the TLAAs with a screening process. To do this, it was necessary to determine the component specific load induced stresses, strains and temperature distributions as well as cumulative usage factor (CUF) values. For the screened-in components, the TLAAs covered all significant time dependent degradation mechanisms. These include (but are not limited to): • irradiation embrittlement, • fatigue, • stress corrosion cracking (SCC), and • irradiation accelerated SCC (IASCC). For the components that were screened-in, the potential to brittle, ductile or other degradation was determined. Only some of the most significant cases and results are presented. According to the analysis results, the operational lifetime of the OL1/OL2 RPVs and internals can safely be extended from 40 to 60 years.

Original languageEnglish
Title of host publicationASME 2018 Pressure Vessels and Piping Conference
PublisherAmerican Society of Mechanical Engineers ASME
PagesV007T07A016
Number of pages12
ISBN (Electronic)978-0-7918-5170-8
DOIs
Publication statusPublished - 20 Jul 2018
MoE publication typeNot Eligible
EventASME 2018 Pressure Vessels and Piping Conference, PVP2018 - Hotel Hilton, Prague, Czech Republic
Duration: 15 Jul 201820 Jul 2018
Conference number: 52

Conference

ConferenceASME 2018 Pressure Vessels and Piping Conference, PVP2018
Abbreviated titlePVP2018
CountryCzech Republic
CityPrague
Period15/07/1820/07/18

Fingerprint

Boiling water reactors
Pressure vessels
Aging of materials
Degradation
Stress corrosion cracking
Irradiation
Embrittlement
Nuclear power plants
Loads (forces)
Screening
Temperature distribution
Fatigue of materials

Cite this

Cronvall, O. (2018). Long-Term Operation of BWR RPV and Its Internals: Article PVP2018-84541. In ASME 2018 Pressure Vessels and Piping Conference (pp. V007T07A016). [PVP2018-84541] American Society of Mechanical Engineers ASME. https://doi.org/10.1115/PVP2018-84541
Cronvall, Otso. / Long-Term Operation of BWR RPV and Its Internals : Article PVP2018-84541. ASME 2018 Pressure Vessels and Piping Conference. American Society of Mechanical Engineers ASME, 2018. pp. V007T07A016
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Cronvall, O 2018, Long-Term Operation of BWR RPV and Its Internals: Article PVP2018-84541. in ASME 2018 Pressure Vessels and Piping Conference., PVP2018-84541, American Society of Mechanical Engineers ASME, pp. V007T07A016, ASME 2018 Pressure Vessels and Piping Conference, PVP2018, Prague, Czech Republic, 15/07/18. https://doi.org/10.1115/PVP2018-84541

Long-Term Operation of BWR RPV and Its Internals : Article PVP2018-84541. / Cronvall, Otso.

ASME 2018 Pressure Vessels and Piping Conference. American Society of Mechanical Engineers ASME, 2018. p. V007T07A016 PVP2018-84541.

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

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Cronvall O. Long-Term Operation of BWR RPV and Its Internals: Article PVP2018-84541. In ASME 2018 Pressure Vessels and Piping Conference. American Society of Mechanical Engineers ASME. 2018. p. V007T07A016. PVP2018-84541 https://doi.org/10.1115/PVP2018-84541