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

IAEA TECDOC No. 1470
English IAEA-TECDOC-1470 92-0-109305-5
128 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 vessels (RPVs). 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 RPVs.

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