Dealing with cracks and leaks in a primary circuit
This paper presents a study performed by the European Clearinghouse on Operating Experience for Nuclear Power Plants, in cooperation with GRS and IRSN, assessing events related to leaks and cracks in the reactor coolant pressure boundary.
The objective was to provide lessons learned from events and recommendations in order to prevent the recurrence of similar events and to mitigate their impact on NPP operation.
This study summarizes the analysis of more than 400 events related to leaks and cracks reported to different databases. To help identify generic lessons learned and recommendations, these events were classified into families according to the type of component affected: piping, vessels, valves, steam generators, pumps, flange connections and safety and relief valves.
This paper presents the main findings, recommendations and conclusions raised by this study.
SANDA Radian;
PEINADOR VEIRA Miguel;
WENKE Rainer;
NEGRI Patrice;
2014-06-04
WILMINGTON PUBL
JRC89618
0029-5507,
https://publications.jrc.ec.europa.eu/repository/handle/JRC89618,
Additional supporting files
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