Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety

Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety PDF

Author:

Publisher:

Published: 2007

Total Pages: 0

ISBN-13:

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This report updates the IAEA's findings relevant to significant ageing mechanisms and degradation locations, as well as current practices for the assessment and management of the ageing of pressurised water reactor (PWR) pressure vessel internals (RVI's). This includes irradiated assisted stress corrosion cracking of baffle former bolts, and new operational experience and practices designed to manage these problems. The report emphasises safety aspects and also provides information on current inspections as well as on monitoring and mitigation practices for managing the ageing of PWR RVI's.

Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety

Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety PDF

Author: International Atomic Energy Agency

Publisher:

Published: 2011

Total Pages: 273

ISBN-13: 9789201214102

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At present there are over four hundred and forty operational nuclear power plants (NPPs) in IAEA Member States. With the ageing degradation of the systems, the structures of components during their operational life must be effectively managed in order to preserve the service life of the plant. From the safety perspective, this means controlling, within acceptable limits, the ageing degradation and wear-out of plant components so that adequate safety margins remain, i.e. integrity and functional capability in excess of normal operating requirements. This IAEA-TECDOC is one in a series of reports on the assessment and management of ageing of the major NPP components important to safety. The objective of this report is to update and supersede IAEA-TECDOC-981 in order to provide current ageing management guidance for PWR, WWER and CANDU steam generators to all involved in the operation and regulation of nuclear power plants.

Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety

Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety PDF

Author: International Atomic Energy Agency

Publisher: IAEA

Published: 2005

Total Pages: 128

ISBN-13:

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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 RPVs.

Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety

Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety PDF

Author: International Atomic Energy Agency

Publisher: IAEA

Published: 2005

Total Pages: 144

ISBN-13:

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This report considers significant ageing mechanisms and degradation locations, as well as current practices for the assessment and management of the ageing of boiling water reactor (BWR) pressure vessels (RPVs). The report emphasises safety aspects and also provides information on current inspections, and monitoring and mitigation practices for managing ageing of BWR RPVs.

Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety

Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety PDF

Author: International Atomic Energy Agency

Publisher: IAEA

Published: 2007

Total Pages: 65

ISBN-13: 9789201051073

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This report updates the IAEA's findings relevant to significant ageing mechanisms and degradation locations, as well as current practices for the assessment and management of the ageing of pressurised water reactor (PWR) pressure vessel internals (RVIs). This includes irradiated assisted stress corrosion cracking of baffle former bolts, and new operational experience and practices designed to manage these problems. The report emphasises safety aspects and also provides information on current inspections as well as on monitoring and mitigation practices for managing the ageing of PWR RVIs.