Abstract: The present invention relates to a nuclear boiler comprising a vessel whose top is closed by a dismountable cover, a cage bearing the core of the reactor and separating the vessel into an inner hot zone and an outer cold zone, at least one steam generator disposed outside the vessel and comprising a tight enclosure, a tube plate, separating the enclosure into a primary part, or water box, and a secondary part, and bearing U-shaped tubes whose ends open into two concentric zones of the water box separated by an internal structure, at least one hot connecting pipe and one cold connecting pipe respectively connecting the hot zone and the cold zone of the vessel to each of the concentric zones of the water box, wherein the tube plate, the tubes and the secondary part of the enclosure of the steam generator define a sub-assembly dismountable from the primary part of the enclosure, the hot connecting pipe being dismountably mounted between the cage and the internal structure of the water box, this strucutre itself

Abstract: Nuclear reactor exchanger which assures the transfer of heat between two streams of coolant sodium. It includes an outlet connector which channels coolant sodium leaving a bundle of exchanger tubes traversed on the inside by the sodium and immersed externally in coolant sodium, and an inner tubular jacket forming a surface of revolution about a vertical axis and an outer tubular jacket. The wall of the inner jacket has a folded portion distinguished by at least one flank in the form of a crown.

Abstract: A supporting grid for tubes comprising a central reticular structure formed of main and secondary intersecting strips, an inner annular frame formed in the same material as the strips and so designed as to receive with a tight fit the ends of said strip therein, said inner frame being higher than the reticular structure so that upper and lower projecting portions are created together with cleaning ducts, and an external annular frame formed of a different material and consisting of an external box ring and of an external cover ring capable of receiving and containing therein said projecting portions of the inner frame, axially extending and inwardly facing dogs being provided at the inner portion of said external frame; the inner frame and the external frame being assembled so that at room temperature said dogs of the external frame fit tightly to the inner cylindrical surface of said projecting portions while play exists between the external cylindrical surface of the inner frame and the internal cylindrical

Abstract: 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, t

Abstract: The apparatus comprises an annular cup (5) solid with the component (1) and surrounding its outer wall, a frusto-conical support surface (9) having as axis the vertical axis (2) of the component (1) fixed at the perimeter of its large base to the passage (4) into which the component (1) passes and a closure element (14) with rotational symmetry. The closure element (14) has an upper part (15) which rests on the support surface (9) so as to totally close the annular space (18) at the top and a part directed downwards constituted by a sleeve whose lower part goes into the cup (5). The cup (5) fills up with liquid metal (17) which condenses when the reactor is operating, which ensures sealing between the sleeve (4) and the cup (5).The invention is particularly applicable to fast neutron nuclear reactors cooled by liquid sodium.

Abstract: Integrated nuclear reactor cooled by a liquid metal and incorporating a main vessel sealed in its upper part by a slab, an inner vessel containing the core, the latter resting on a system for the positioning and supply of the core with liquid metal and which is called the support, the latter itself resting on a supporting structure bearing on the bottom of the main vessel of the reactor, wherein it comprises an inner baffle cladding the side wall and bottom of the main vessel and defining with the latter an intermediate space filled with the liquid metal, tubes for supplying a liquid metal to the intermediate space below the bottom of the main vessel and tubes for returning said liquid metal to an auxiliary exchanger in order to remove heat from the intermediate space.

Abstract: Cooling system for auxiliary systems of a nuclear installation for heat removal from heat exchangers, the heat exchangers being connected on the primary side thereof to lines which may contain radioactive liquids or gases, being disposed in a secured area of the nuclear installation, and having connections on the secondary side thereof for cooling liquid lines, including an outgoing line for the cooling liquid connected to the connections on the secondary side of the heat exchangers, a dry cooling tower having cooling elements connected to the outgoing line, a return line for the cooling liquid connected to the cooling elements, a refrigeration loop having a supplemental heat exchanger with the primary side thereof connected in the return line, a bypass line connected from the outgoing to the return line parallel to the cooling elements and supplemental heat exchanger, and a control valve connected in the bypass line.

Abstract: 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 con

Abstract: 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 supp

Abstract: A sodium-cooled fast reactor comprises at least one auxiliary heat exchanger constituted by a plurality of vertical heat-exchange modules each provided with a coolant circuit. A vertical cylindrical passage for each auxiliary heat exchanger extends through the reactor vault roof. The passage diameter is larger than the diameter of a heat-exchange module but smaller than the overall dimension of the auxiliary heat exchanger in horizontal cross-section. Each passage is closed by a shield plug after the modules have been placed in position, the modules being disposed around an axial extension of each shield plug.

Abstract: A tube-in-shell heat exchanger wherein the tube bundle has a central spine which carries a series of bracing grids for the tubes. The grids are resiliently mounted on the spine so that differential thermal expansion of one group of tubes relative to other groups of tubes and structure can be accommodated without inducing severe thermal stress.

Abstract: An intermediate heat exchanger for a liquid metal cooled nuclear reactor and method. The heat exchanger includes a plurality of thermally uncompensated tubes mounted in the heat exchanger for carrying a liquid metal heating fluid from a hot pool to a cool pool in the nuclear reactor and a shell enclosing these tubes for bringing a liquid metal heated fluid into thermal communication with both said tubes and said heating fluid. In operation the shell is heated by thermal communication with the hot pool to a temperature substantially greater than the temperature of the tubes. The elevated temperature of the shell stresses the tubes in tension and the heat exchanger is thereby capable of accommodating differential thermal expansion.

Abstract: Heat exchange apparatus for use in a liquid metal environment comprising heat exchange tubes and grid plates having complementary bearing surfaces. The tubes are of stainless steel and the complementary bearing surfaces of the grids are aluminized to reduce wear and friction.

Abstract: A secondary coolant circuit for a nuclear-reactor of the liquid-metal cooled type, said circuit comprising at least one intermediate exchanger mounted in the vessel of said reactor, outside said vessel a steam-generator for the exchange of calories between the secondary liquid-metal flowing through said secondary circuit and water-steam, at least one pump for circulating said secondary sodium and one tank for storing said secondary liquid-metal and recovering those products generated by a possible liquid-metal-water reaction in said steam-generator, said liquid-metal being likely to occupy the lowest possible level in said tank, said secondary coolant circuit being characterized in that said tank is situated at the lowest possible level in the nuclear installation, in that the lower extremity of the liquid-metal outlet duct of said steam-generator is directly dipped into said tank, in that, in said tank above the liquid-metal, is maintained an inert gas cover at such a pressure that it balances the liquid-met