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Mechanical Analysis of Underclad Cracks in Reactor Pressure Vessel Nozzles

[+] Author Affiliations
Nicolas Verdiere, François Champigny

Electricité de France, Saint-Denis Cedex, France

Henriette Churier-Bossennec

Electricité de France, Villeurbanne Cedex, France

Paper No. PVP2003-1990, pp. 59-63; 5 pages
doi:10.1115/PVP2003-1990
From:
  • ASME 2003 Pressure Vessels and Piping Conference
  • Fatigue, Fracture, and Damage Analysis
  • Cleveland, Ohio, USA, July 20–24, 2003
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 0-7918-4152-9
  • Copyright © 2003 by ASME

abstract

During the in-service inspection in 1999 in Tricastin 1 Nuclear Plant, underclad cracks had been discovered in the core shell. Following specific justification of these defects, other parts of the reactor vessel also sensitive to this kind of defects have been re-examined, and particularly RPV nozzles, which are classified as “concerned by fast fracture”. Recent assessments with large defects, superior to maximum realistic ones, have been conducted in different sections in the reactor vessel inlet and outlet nozzles: circular cracks of 10 mm in the inner radius, and 20 mm depth in the straight section. Theses assessments highlighted the verification of acceptance criteria in various, normal and emergency conditions with large margins. Fatigue analysis has also been conducted. For underclad cracks located in the inner radius of RPV inlet nozzles, a small propagation in the austenitic cladding is demonstrated but would not lead to any cladding perforation within 40 years.

Copyright © 2003 by ASME

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