Aging management based on in-service fatigue analyses
Creators
- 1. Technischer Ueberwachungs-Verein Bayern Sachsen e.V., Muenchen (Germany)
Description
For components of the primary loop of PWRs, in-service monitoring and determination of actual degree of fatigue was done on the basis of measured loads. The degree of fatigue extrapolated to a service period of 20 years is given for all primary loop components. Operating results have shown that austenitic pipework exhibits high susceptibility to fatigue effects. Austenite and ferrite are compared for their fatigue resistance. The determination of incipient cracking probabilities as a function of degree of fatigue is explained. The paper gives data on incipient cracking probabilities in austenite as a function of degree of fatigue in order to show the value of information that can be derived from calculated fatigue data with respect to aging management, as e.g. reasonable planning of non-destructive testing programmes. (orig./DG)
Abstract (German)
Fuer Komponenten des Primaerkreises von Druckwasserreaktoren wurden betriebsbegleitend auf der Basis von gemessenen Belastungen aktuelle Ermuedungsgrade ermittelt. Die auf eine Betriebszeit von 20 Jahren umgerechneten Ermuedungsgrade werden fuer alle Primaerkeiskomponenten angegeben. Die Betriebserfahrung zeigte, dass bei Ermuedungsschaeden haeufig austenitische Leitungen betroffen waren. Austenit und Ferrit werden hinsichtlich ihrer Dauerlastwechselfestigkeit verglichen. Die Ermittlung von Anrisswahrscheinlichkeiten als Funktion von Ermuedungsgraden wird beschrieben. Um zu zeigen, was aus berechneten Ermuedungsgraden fuer das Alterungsmanagement abzuleiten ist, z.B. Ermittlung eines sinnvollen Umfangs an Zerstoerungsfreien Pruefungen, werden fuer Austenit Anrisswahrscheinlichkeiten als Funktion der Ermuedungsgrade dargestellt. (orig./DG)Additional details
Additional titles
- Original title (German)
- Alterungsmanagement auf der Basis von betriebsbegleitend durchgefuehrten Ermuedungsanalysen
Publishing Information
- ISBN
- 3-89429-721-2
- Imprint Title
- Aging management in nuclear power plants
- Imprint Pagination
- 519 p.
- Journal Page Range
- p. 221-236.
- ISSN
- 0937-4442
- Report number
- BfS-KT--13/96
Conference
- Title
- Aging management in nuclear power plants.
- Original Conference Title
- 4. KT/KTA-Winterseminar: Alterungsmanagement in Kernkraftwerken
- Acronym
- 4. KT/KTA Winter seminar
- Dates
- 25-26 Jan 1996.
- Place
- Salzgitter (Germany).
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 28042877
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- AUSTENITIC STEELS; BWR TYPE REACTORS; CRACK PROPAGATION; FATIGUE; FERRITIC STEELS; IN-SERVICE INSPECTION; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR SAFETY; SERVICE LIFE; STRESS INTENSITY FACTORS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; INSPECTION; IRON ALLOYS; IRON BASE ALLOYS; LIFETIME; MECHANICAL PROPERTIES; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; STEELS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:Alterungsmanagement in Kernkraftwerken.