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Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety: BWR Pressure Vessel Internals

IAEA TECDOC No. 1471
English IAEA-TECDOC-1471 92-0-109205-9
116 15.00 2005

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Description

The objective of this report is to identify significant ageing mechanisms and degradation locations, as well as to document current practices for the assessment and management of the ageing of boiling water reactor (BWR) pressure vessel internals (RPVIs). The report emphasizes safety aspects and also provides information on current inspections as well as on monitoring and mitigation practices for managing ageing of BWR RPVIs.

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