The Reactor Pressure Vessel (RPV) is an essential component, which is liable to limit the lifetime duration of PWR plants. The assessment of defects in RPV subjected to pressurized thermal shock (PTS) transients made at an European level generally does not necessarily consider the beneficial effect of the load history (Warm Pre-stress, WPS). The SMILE project — Structural Margin Improvements in aged embrittled RPV with Load history Effects — aims to give sufficient elements to demonstrate, to model and to validate the beneficial WPS effect. It also aims to harmonize the different approaches in the national codes and standards regarding the inclusion of the WPS effect in a RPV structural integrity assessment. The project includes significant experimental work on WPS type experiments with C(T) specimens and a PTS type transient experiment on a large component. This paper deals with the results of the PTS type transient experiment on a component-like specimen subjected to WPS- loading, the so called Validation Test, carried out within the framework of work package WP4. The test specimen consists of a cylindrical thick walled specimen with a thickness of 40mm and an outer diameter of 160mm, provided with an internal fully circumferential crack with a depth of about 15mm. The specified load path type is Load-Cool-Unload-Fracture (LCUF). No crack initiation occurred during cooling (thermal shock loading) although the loading path crossed the fracture toughness curve in the transition region. The benefit of the WPS-effect by final reloading up to fracture in the lower shelf region, was shown clearly. The corresponding fracture load during reloading in the lower shelf region was significantly higher than the crack initiation values of the original material in the lower shelf region. The post test fractographic evaluation showed that the fracture mode was predominantly cleavage fracture also with some secondary cracks emanating from major crack.
Skip Nav Destination
ASME 2005 Pressure Vessels and Piping Conference
July 17–21, 2005
Denver, Colorado, USA
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
0-7918-4191-X
PROCEEDINGS PAPER
SMILE: Validation of the Warm-Pre-Stress Effect With a Cylindrical Thick-Walled Specimen
Klaus Kerkhof,
Klaus Kerkhof
University of Stuttgart, Stuttgart, Germany
Search for other works by this author on:
Eberhard Roos,
Eberhard Roos
University of Stuttgart, Stuttgart, Germany
Search for other works by this author on:
Georges Bezdikian,
Georges Bezdikian
Electricite´ de France, Saint-Denis Cedex, France
Search for other works by this author on:
Dominique Moinereau,
Dominique Moinereau
Electricite´ de France, Moret-sur-Loing Cedex, France
Search for other works by this author on:
Nigel Taylor
Nigel Taylor
Joint Research Centre (JRC), Petten, The Netherlands
Search for other works by this author on:
Klaus Kerkhof
University of Stuttgart, Stuttgart, Germany
Eberhard Roos
University of Stuttgart, Stuttgart, Germany
Georges Bezdikian
Electricite´ de France, Saint-Denis Cedex, France
Dominique Moinereau
Electricite´ de France, Moret-sur-Loing Cedex, France
Nigel Taylor
Joint Research Centre (JRC), Petten, The Netherlands
Paper No:
PVP2005-71364, pp. 311-320; 10 pages
Published Online:
July 29, 2008
Citation
Kerkhof, K, Roos, E, Bezdikian, G, Moinereau, D, & Taylor, N. "SMILE: Validation of the Warm-Pre-Stress Effect With a Cylindrical Thick-Walled Specimen." Proceedings of the ASME 2005 Pressure Vessels and Piping Conference. Volume 6: Materials and Fabrication. Denver, Colorado, USA. July 17–21, 2005. pp. 311-320. ASME. https://doi.org/10.1115/PVP2005-71364
Download citation file:
5
Views
Related Proceedings Papers
Related Articles
Investigation on Constraint Effect of a Reactor Pressure Vessel Subjected to Pressurized Thermal Shocks
J. Pressure Vessel Technol (February,2015)
Safety Assessment of Reactor Pressure Vessel Integrity for Loss of Coolant Accident Conditions
J. Pressure Vessel Technol (February,2012)
Related Chapters
Trends in High Temperature Structural Integrity Assessment
Fatigue and Fracture Mechanics: 35th Volume
A Fracture Mechanics Method for an Advanced Evaluation of Inclusions and the Prediction of Fatigue Life of Rolling Element Bearings
Bearing and Transmission Steels Technology
Subsection NCA—General Requirements for Division 1 and Division 2
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 1, Third Edition