Seismic sensor unit and according emergency shutdown system of a nuclear power plant
FR2919917A1
Method of making orifices in the secondary envelopes of a steam generator of a pressurized water nuclear reactor
FR2917228A1
Method for determining a uncertainty component relating to power distribution in the heart of a nuclear reactor
FR2917154A1
Method for dismantling the reuse of the elements of the pressure envelope of a steam generator using a nuclear power plant.
FR2915619A1
Device and method for capturing an orifice of a beam envelope of a steam generator of a pressurized water nuclear reactor
FR2915580A1
Method of estimating a moment of flexion on a solid area of a piping of a nuclear reactor
FR2915020A1
Device and method for automatically and remotely connecting the guiding ducts of a thermocouple of internal equipment exceeding a nuclear reactor
FR2910912A1
METHOD FOR THE HEAT TREATMENT OF ENVIRONMENTALLY ASSISTED CRACKING DISENSIBILIZATION OF A NICKEL-BASED ALLOY AND PART PRODUCED THEREBY THUS PROCESSED
FR2910690A1
Method for estimating the concentration in a chemical element in the primary cooling liquid of a nuclear reactor
FR2910171A1
Fixed cluster i.e. plug cluster, for pressurized water nuclear reactor core, has support elements projecting from fins beyond mounting system in direction vertically oriented towards top, when cluster is arranged on fuel assembly
FR2910170A1
Lower cap with an anti-debris device for chican nuclear fuel assembly and corresponding assembly
FR2909798A1
Designing fuel assembly, useful for light-water nuclear reactor comprising structural components of zirconium alloy, comprises calculating uniaxial constraints using traction/compression and choosing the alloys
FR2909388A1
Corrosion resistant zirconium alloy for fuel assembling component for boiling water reactor, component produced thereby, fuel assembly and use thereof.
FR2908338A1
Orbital machine for machining a revolution metal wall
FR2908061A1
Automatic welding device and method for carrying on a surface of a welding seal.
FR2907223A1
Method and device for detecting structural anomalies in a spherical particle, in particular in a nuclear fuel particle for reactors at high temperature or very high temperature.
FR2905031A1
Transport container for nuclear fuel assemblies and use of such container.
FR2904421A1
Non-destructive characterization method, notammently for nuclear fuel particles for high temperature reactor
FR2902569A1
Process for repairing a tank penetration of a nuclear reactor
FR2901401A1
Controlling operating parameters of a nuclear reactor core in pressurized water, comprises evaluating the actual values of operating parameters according to the acquired quantities of operating conditions of the reactor core
