The brittle failure assessment for five pressurized water reactor pressure vessels (RPV) of German nuclear power plants (NPP) has been revisited according to an advanced state of the art. Besides of recent innovation in fracture toughness curves and reference temperatures being already in the codes, also the effect of loss of constraint had to be considered when fracture toughness values determined from deep cracks in fracture toughness specimen with high multi-axial state of stress were transferred to crack configurations in the component. Thus, the available concepts were compared for their fitness for purpose, i.e. for their ability to give a fracture toughness representative to the crack configuration or flaw postulate in the component. The results of the investigation reveal a significant lower constraint in the component resulting in increased fracture toughness and showing that the brittle failure assessment based on the high constraint fracture toughness from the standard specimens can be very conservative. For consideration of the constraint conditions in the component besides the deterministic T-stress parameter also probabilistic local approach concepts based on the Weibull model were used which have the advantage of considering both the local stress strain field and the material volume under high loading. The loss of constraint was determined for several flaw postulates in the leading situations on the RPV being the coolant inlet nozzle corner and the flange joint. A considerable loss of constraint was demonstrated for flaw postulates with broken clad in the ferritic nozzle corner. Also in the flange joint the loss of constraint is evident for small flaws. In addition, for flaw postulates under the intact cladding the loss of constraint is remarkably higher than with broken postulated cladding. In summary, with the measured material toughness and the significant loss of constraint a considerable inherent margin against brittle failure can be demonstrated for the investigated load cases.
Skip Nav Destination
ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference
July 18–22, 2010
Bellevue, Washington, USA
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
978-0-7918-49255
PROCEEDINGS PAPER
Integrity Assessment of a German PWR RPV Considering Loss of Constraint
Dieter Siegele,
Dieter Siegele
Fraunhofer-Institut fu¨r Werkstoffmechanik, Freiburg, Germany
Search for other works by this author on:
Igor Varfolomeev,
Igor Varfolomeev
Fraunhofer-Institut fu¨r Werkstoffmechanik, Freiburg, Germany
Search for other works by this author on:
Jo¨rg Hohe,
Jo¨rg Hohe
Fraunhofer-Institut fu¨r Werkstoffmechanik, Freiburg, Germany
Search for other works by this author on:
Volker Hardenacke,
Volker Hardenacke
Karlsruher Institute fu¨r Technologie, Karlsruhe, Germany
Search for other works by this author on:
Gerhard Nagel
Gerhard Nagel
E.ON Kernkraft, Hannover, Germany
Search for other works by this author on:
Dieter Siegele
Fraunhofer-Institut fu¨r Werkstoffmechanik, Freiburg, Germany
Igor Varfolomeev
Fraunhofer-Institut fu¨r Werkstoffmechanik, Freiburg, Germany
Jo¨rg Hohe
Fraunhofer-Institut fu¨r Werkstoffmechanik, Freiburg, Germany
Volker Hardenacke
Karlsruher Institute fu¨r Technologie, Karlsruhe, Germany
Gerhard Nagel
E.ON Kernkraft, Hannover, Germany
Paper No:
PVP2010-25615, pp. 153-159; 7 pages
Published Online:
January 10, 2011
Citation
Siegele, D, Varfolomeev, I, Hohe, J, Hardenacke, V, & Nagel, G. "Integrity Assessment of a German PWR RPV Considering Loss of Constraint." Proceedings of the ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference. ASME 2010 Pressure Vessels and Piping Conference: Volume 6, Parts A and B. Bellevue, Washington, USA. July 18–22, 2010. pp. 153-159. ASME. https://doi.org/10.1115/PVP2010-25615
Download citation file:
14
Views
Related Proceedings Papers
Related Articles
Brittle Failure Assessment of a PWR-RPV for Operating Conditions and Loss of Coolant Accident
J. Pressure Vessel Technol (August,2008)
Safety Assessment of Reactor Pressure Vessel Integrity for Loss of Coolant Accident Conditions
J. Pressure Vessel Technol (February,2012)
Application of the Failure Assessment Diagram to the Evaluation of Pressure-Temperature Limits for a Pressurized Water Reactor
J. Pressure Vessel Technol (May,1985)
Related Chapters
Subsection NG—Core Support Structures
Companion Guide to the ASME Boiler & Pressure Vessel Codes, Volume 1 Sixth Edition
Czech and Slovakian Codes
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 3, Third Edition
Lessons Learned: NRC Experience
Continuing and Changing Priorities of the ASME Boiler & Pressure Vessel Codes and Standards