Commissariat a L'energie Atomique

Michel Aubert

Robert Artaud

Charley Renaux

Guy Lemercier

Paul Lambert

Antoine Bret

Richard Elbeze

Patrick Jogand

Philippe Verriere

Michel Sauvage

Andre Teytu

Henri Jacques Gollion

Jean-Denis Montmayeur

Gilbert Chevallier

Fast neutron nuclear reactor, which comprises a vessel containing a liquid cooling metal, a core immersed in this metal, the vessel having a flooring on which rests a structure for the core, said core being constituted by a juxtapositioning of assemblies fixed into the structure, the liquid cooling metal circulating in an upwards manner in the core, the liquid metal being called 'cold liquid metal' before its circulation in the core and 'hot liquid metal' after it has passed into the latter, wherein it comprises a fuel element storage structure, which is independent of the core structure and is arranged concentrically with respect to the latter and rests on the flooring, a circulation of cold liquid metal being ensured in the assembly by recovering leaks of the core structure.

East neutron reactor having a storage structure independent of the core

A steam generator for transferring the heat carried by a liquid metal to a water - steam circuit. It comprises a drainage tank directly suspended at the lower end of the envelope. A drainage tube connected to the bottom of the envelope is disposed within the tank and carries a burster disk at its end. This disk is placed behind a detachable observation window, fixed to the drainage tank and permitting the replacement thereof.

Steam generator for a liquid metal-cooled reactor

Liquid metal-cooled nuclear reactor incorporating a main vessel sealed by a slab and containing the reactor core, an inner vessel placed within the main vessel and defining in the latter a hot zone filled with relatively hot liquid metal and a cold zone filled with relatively cold liquid metal, at least one pump for circulating the liquid metal between the cold zone and the hot zone across the core and at least one heat exchanger disposed between the hot zone and the cold zone, wherein the inner vessel comprises two truncated cone-shaped ferrules opposed by their large bases and a small diameter cylindrical ferrule extending the small base of the upper truncated cone-shaped ferrule, the reactor core resting on the small base of the lower truncated cone-shaped ferrule by means of a support structure, the hot zone being formed within the inner vessel, while the cold zone is formed between the main vessel and the inner vessel.

Fast neutron nuclear reactor

Installation for handling the assemblies of a fast neutron nuclear reactor comprising a core located in a vertically axed vessel and constituted by a group of assemblies positioned in a supporting grid, a horizontal slab over the vessel, a large rotary plug in the slab, a small rotary plug in the large rotary plug and off-centered with respect to the latter, and a handling pot or container making it possible to remove the fuel elements from the vessel, wherein the small rotary plug has a handling poker and the large rotary plug positioned coaxially with respect to the core has a handling arm, the poker making it possible to reach a fraction of assemblies, particularly those in the central part of the core and to transfer them into a take-up station of the supporting grid, the assemblies placed in the take-up station, as well as those in the peripheral area downwardly accessible to the handling arm being deposited by the latter in the handling pot or container.

Handling process and installation for the assemblies of a neutron

The invention relates to a nuclear reactor cooled by a liquid metal contained in a vessel obturated by upper closing means, said latter essentially being constituted by a slab and rotating plugs. The upper closing means comprise at least one circuit for circulation of a cooling gas or liquid, this circuit being provided with means for maintaining the closing means at a homogeneous temperature at least equal to 100.degree. C. and preferably close to 120.degree. C. The invention is applicable to the production of less cumbersome and less expensive fast neutron nuclear reactors.

Fast neutron nuclear reactors

Heat exchanger for a nuclear reactor of the type in which the main vessel is sealed by an upper slab, comprises a plurality of substantially straight exchange tubes mounted between on the one hand an upper annular tube plate associated with a secondary fluid discharge chamber and on the other a lower annular tube plate associated with a supply chamber, a ferrule surrounding the said tubes and provided with a discharge orifice for the primary fluid, a central shaft which communicates with the supply chamber, and a supply manifold and a discharge manifold for the secondary fluid, wherein it comprises a supporting ferrule fixed to the periphery of the upper tube plate and sealed at its upper end by a dome, said ferrule having on its outer periphery a supporting flange by the said slab, the manifolds being superimposed in the supporting ferrule and fixed to a horizontal plate, which is itself fixed to the supporting ferrule, the supply manifold being connected by at least one pipe to the upper end of the shaft, the discharge manifold being connected to the discharge chamber also by means of a pipe, whereby the pipes are positioned in the supporting ferrule.

Heat exchanger for nuclear reactor

Apparatus for homogenizing the circumferential temperatures of the vertically axes ferrule of a component passing through the upper slab of a nuclear reactor, wherein it comprises at least one assembly forming a heat pipe describing the entire circumference of said ferrule in order to ensure the homogenization of the temperatures of said ferrule level with the assembly, means for fixing the assembly or assemblies forming the heat pipe on the inner face of the ferrule and means for ensuring a thermal contact between the assembly or assemblies forming the heat pipe and the said ferrule.

Temperature homogenization apparatus

The invention relates to an assembly for passage through a containment slab for transferring irradiated nuclear fuel, comprising a sleeve passing through the slab and fast therewith and a guide ramp passing through the sleeve and in which moves a handling pot carrying the fuel, wherein said assembly further comprises a device for evacuating the residual heat dissipated by the fuel, this device comprising a bundle of caloducts disposed parallel to the ramp over a length at least equal to that of the sleeve, and means for evacuating the flow of heat directed above the slab by the caloducts.

Assembly for passage through a containment slab for transferring

Fast neutron nuclear reactor cooled by a liquid metal, comprising a main vessel sealed by an upper slab and within said main vessel at least one heat exchanger between the said liquid metal and a second fluid, at least one pump for circulating the liquid metal, a cylindrical inner vessel with a vertical axis and placed on flooring resting on the bottom of the main vessel, the inner vessel containing the reactor core which rests on a support bearing against the bottom of the main vessel by means of the said flooring, the liquid metal circulating from bottom to top through the reactor core, wherein the said inner vessel incorporates an internal baffle which revolves about the vertical axis of the inner vessel, said baffle comprising an upper cylindrical part adjacent to the inner vessel and arranged above the core, and a lower cylindrical part surrounding the core and having a smaller diameter than the upper part, said lower part being connected to the upper part by a frustum-shaped part, whereby the baffle confines the 'hot' liquid metal leaving the core and at least one pipe is arranged between the frustum-shaped part of the baffle and at least one heat exchanger for connecting the intake of the latter to the inner volume defined by the baffle.

Fast neutron reactor

Heat exchanger of a nuclear reactor, whose vessel is sealed by a slab, the exchanger being of the type which has within a vertically axed outer ferrule a plurality of heat exchange modules with substantially straight tubes, each of the said modules having a secondary fluid inlet chamber and a secondary fluid outlet chamber and means for introducing and removing the primary fluid with respect to the exchange modules, wherein it comprises a base plate peripherally fixed to the said outer ferrule, means for supporting the outer ferrule by the slab, supporting ferrules for the modules, each ferrule traversing the base plate and being connected on the one hand to the upper end of the module and on the other to the said base plate, a plurality of pipes for the supply and removal of the secondary fluid sealingly traversing the base plate, a supply manifold and a discharge manifold for the secondary fluid positioned within the outer ferrule above the base plate, said manifolds being respectively connected to the supply and discharge pipes of the secondary fluid, means for supporting the manifolds and a plurality of biological protection plates positioned within the outer ferrule above the base plate and level with the slab, said protection plates being supported by the manifold supporting means and permitting the passage of the secondary fluid and discharge pipes.

Semi-modular heat exchanger for nuclear reactors

A first annular space is formed between a cylindrical baffle and the reactor vessel and a second annular space is formed between the baffle and a counter-baffle. The level of liquid metal coolant is free within the two annular spaces which are separated by the baffle. The top edge of the baffle has a profile such that they supply of 'cold' liquid metal which overflows into the discharge space takes place without breaking away from the baffle wall.

Nuclear reactor

Heat-insulating panels applied against a bearing wall and extending parallel to the wall to be protected are supported by means of a device comprising a yoke rigidly fixed to the wall to be protected and fitted with a cross-pin, the link of a panel-supporting element being mounted freely around the cross-pin. A second yoke secured to the bearing wall is supported by means of a second cross-pin on which the last link of the supporting element is freely mounted.

Supporting device for heat-insulating panels

A nuclear reactor, especially a sodium-cooled fast reactor in which the coolant is confined at least partially within a vertical primary tank containing the reactor core and surrounded by a main tank containing vertical heat exchangers and pumps for heat removal and continuous circulation of coolant from one tank to the other. Each heat exchanger is provided with inlet and outlet windows respectively at the upper and lower end for the admission and discharge of coolant derived from the primary tank and is surrounded by an outer shell which penetrates together with the heat exchanger into the region located between the primary tank and the main tank. The outer shell delimits with the heat exchanger an annular space which is joined at the level of the inlet windows to one end of at least one elbowed duct, the other end of which extends into the coolant within the primary tank. The annular space is connected to a pump for producing a variable negative pressure within said space and thus priming the siphon formed by the primary tank, the elbowed duct and the annular space.

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Manosque, France

Michel Aubert