Tractebel Engineering (TRACTEBEL)
Tractebel Engineering, a division of SUEZ-Tractebel, is an Architect-Engineer and Consulting Engineer. It is active in the fields of power generation, transmission and distribution. The activities cover the full range of engineering, from feasibility studies to engineering, procurement and construction contracts, including operational support services and consultancy, in the domains of fossil-fired power generation plants, nuclear power stations and installations, power networks and energy services.
Tractebel Engineering is providing day-to-day assistance and engineering support to the operation teams of the Belgian nuclear power plants as well as to Belgian companies in charge of radwaste management and fuel cycle activities. This close contact with the utility ensures a good information on operational and ageing problems.
Tractebel Engineering is coordinating, in an integrated team with the utility Electrabel, the plant life management of the Belgian nuclear units (“Ageing” project). More specifically in the fields of interest for the present project, Tractebel Engineering is in charge of the follow-up of the pressure vessels of the Belgian units and carries out the various studies that are part of a comprehensive Reactor Pressure Vessel integrity assessment. It also coordinates the evaluations, inspections and repair programs on the baffle-former bolts of the internal structures. Tractebel Engineering also manages a significant research program sponsored by the Utility Electrabel and by the SUEZ group at the Belgian nuclear research centre SCK.CEN in the field of RPV material degradation and Irradiation Assisted Stress Corrosion Cracking.
Tractebel experts participated to the preparation or the execution of various TACIS or PHARE projects related to the VVER Reactor Pressure Vessels and in several European networks or projects.
The main task attributed to Tractebel Engineering will be the coordination of the User Group WP 3-2 on Internals. Tractebel Engineering will also participate in the Users Group WP 3-1 on reactor pressure vessels.
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