Nuclear industry

 

Studies on the pressurized water reactors of the French fleet:

• Update of a record of manufacture of instrumentation valves.

• Update the manufacturing record of the core part flow instrumentation system.

• Study of a sealing system repair device.

• Update of the spare parts file for EDF.

• Consideration of the REX elements with respect to the risk related to the inclusion cleanliness.

• Study of the Fessenheim 2 RIS valves surge justification.     

• Study of the Bugey 5 RIS valves surge justification.

• Study of the Bugey 3 RIS valves surge justification.

• Study of the Bugey 4 RIS valves surge Justification.

• Creation of a faucets expertise specification.

• Creation of a faucets vibratory test procedure.

• Study of a sealing system installation feasibility on thermocouples columns.

• Expertise and tests of a glass level indicators for an accumulators.

• Study of the Fessenheim 1 RIS valves surge justification.

• Drafting of the requisition of the valve TEP455VP - VD2 1300MWe -.

• Study of the Bugey 2 RIS valves surge justification.

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Studies on the Flamanville EPR reactor:   

• Calculation of the actions on the valves of the ARE ARE circuit.

 

Studies on the Olkiluoto EPR reactor:     

• Preparation of the files for the update justification of 9 lines subjected to hydraulic breaks and management of the subcontracted and internally performed calculations.     

• Realization of the update justification of the line UJA-JNG-11 subjected to hydraulic breaks.  

 

Tishan EPR reactor studies:     

• Supply specification for flow restrictors "DI".     

• Equipment insulation supply Specification .

• Technical specification and requisition of Q2 and Q3 "DI" Flow Limiters.   

• Supply specification for KD flow sensors.

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Studies on the waste treatment:

• Calculation of the support of a bubbler and a valve subjected to the earthquake. 

• Thermal calculations of CBFC2 packaging subjected to standardized fires.

• Thermal calculations of an EMEM packaging subjected to standardized fires.

• Thermal calculations of CEFE packaging subjected to standardized fires.

• Thermal calculations of an EMEM packaging in its overpack all subject to standardized fires.

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Studies on the ASTRID fast breeder reactor:     

• Sensitivity study of the lyres of a Sodium Gas Heat Exchanger (ECSG).     

• Feasibility study audit.     

• Study of the inspection implementation of the primary vessel lid.     

• Study of the preliminary implantation of the bar mechanisms.

• Study of the design orientation of the bar mechanisms.

• Preliminary encryption of the bar mechanisms.

• Preliminary analysis of the instrumentation on the bar mechanisms.

• Study of the inspection implementation of the decking support.

• Study of the inspection implementation of the primary circuit vessel.

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Dismantling studies of a fast breeder reactor:

• Mechanical justification of pump supports subjected to earthquake .

• Documentary research on the laser cutting.

• The largest shopping center Study on the dismantling of the Buget 1 reactor.

 

Qualification analysis of a mechanical calculation software.

 

Preparation and implementation of a mechanical training from the design to the manufacturing.

 

Material supply specifications.

 

Koeberg Pressurized Water Reactor in South Africa:

• ASME calculation of an immersion sleeve.

• RCC-M code reconciliation to ASME of a valve.

 

Krsko pressurized water reactor in Slovenia:

• Preparation of the offer of the RIC flux replacement.

• Study of the installation of the RIC flux system.

 

Nuclear fuel:

• Study of the FBFC site review on the lifting units topic.

• Study of the FBFC site review on the safety criticality topic .

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