Assessment and management of ageing of major nuclear power plant components important to safety : BWR pressure vessel internals
Author(s)
Bibliographic Information
Assessment and management of ageing of major nuclear power plant components important to safety : BWR pressure vessel internals
(IAEA-TECDOC, 1471)
International Atomic Energy Agency, 2005
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  Aomori
  Iwate
  Miyagi
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  Yamagata
  Fukushima
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  Toyama
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  Okinawa
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Note
Includes bibliographic references
IAEA-TECDOC-1471
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 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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