Assessment and management of ageing of major nuclear power plant components important to safety : BWR pressure vessels
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Assessment and management of ageing of major nuclear power plant components important to safety : BWR pressure vessels
（IAEA-TECDOC, 1470）
International Atomic Energy Agency, 2005
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Includes bibliographic references
IAEA-TECDOC-1470
Description and Table of Contents
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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