In the summer of 2012, the detection of a large number of quasi-laminar flaw indications in the reactor vessel beltline ring forgings of two Belgian pressurized water reactors (Doel Unit 3 and Tihange Unit 2) posed a significant safety threat that led the licensee to shutdown both plants. Those indications were identified by the licensee as hydrogen flakes that developed during the fabrication of the forgings. As a prerequisite for a potential restart of the units, the Belgian Nuclear Safety Regulator, the Federal Agency for Nuclear Control (FANC), requested the licensee to provide, for each unit, a safety case demonstrating the acceptability of the reactor pressure vessel for continued operation. As the technical subsidiary of the FANC, Bel V performed a safety evaluation of the condition of the reactor pressure vessels. The paper documents the approach Bel V used in his safety evaluation and the criteria he defined to evaluate the acceptability of the hydrogen flaking damage in the reactor pressure vessels.
Skip Nav Destination
ASME 2016 Pressure Vessels and Piping Conference
July 17–21, 2016
Vancouver, British Columbia, Canada
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
978-0-7918-5035-0
PROCEEDINGS PAPER
Safety Evaluation of the Hydrogen Flaking Damage in the Doel 3 and Tihange 2 Reactor Pressure Vessels
Guy Roussel
Guy Roussel
Bel V, Brussels, Belgium
Search for other works by this author on:
Guy Roussel
Bel V, Brussels, Belgium
Paper No:
PVP2016-63231, V01AT01A055; 8 pages
Published Online:
December 1, 2016
Citation
Roussel, G. "Safety Evaluation of the Hydrogen Flaking Damage in the Doel 3 and Tihange 2 Reactor Pressure Vessels." Proceedings of the ASME 2016 Pressure Vessels and Piping Conference. Volume 1A: Codes and Standards. Vancouver, British Columbia, Canada. July 17–21, 2016. V01AT01A055. ASME. https://doi.org/10.1115/PVP2016-63231
Download citation file:
12
Views
0
Citations
Related Proceedings Papers
Related Articles
The Fabulous Nuclear Odyssey of Belgium
J. Pressure Vessel Technol (June,2009)
Extensions of the Failure Assessment Diagram Approach Semi-Elliptical Flaw in Pressurized Cylinder
J. Pressure Vessel Technol (February,1985)
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
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
Subsection NG — Core Support Structures
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 1, Third Edition