Thermal annealing of reactor pressure vessels

Mikhail A. Sokolov, William L. Server, Randy K. Nanstad

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

3 Scopus citations

Abstract

Some of the current fleet of nuclear power plants is poised to reach their end of life and will require an operating life time extension. Therefore, the main structural components, including the reactor pressure vessel (RPV), will be subject to higher neutron exposures than originally planned. These longer operating times raise serious concerns regarding our ability to manage the reliability of RPV steels at such high doses. Thermal annealing is the only option that can, to some degree, recover irradiated beltline region transition temperature shift and recover upper shelf energy properties lost during radiation exposure and extend RPV service life. This paper reviews the experience accumulated internationally with development and implementation of thermal annealing to RPV and potential perspectives for carrying out thermal annealing on US nuclear power plant RPVs.

Original languageEnglish
Title of host publicationOperations, Applications and Components
PublisherAmerican Society of Mechanical Engineers (ASME)
ISBN (Electronic)9780791857021
DOIs
StatePublished - 2015
EventASME 2015 Pressure Vessels and Piping Conference, PVP 2015 - Boston, United States
Duration: Jul 19 2015Jul 23 2015

Publication series

NameAmerican Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP
Volume7
ISSN (Print)0277-027X

Conference

ConferenceASME 2015 Pressure Vessels and Piping Conference, PVP 2015
Country/TerritoryUnited States
CityBoston
Period07/19/1507/23/15

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