Abstract: A plenum separator system for separating the hot plenum from the cold plenum and from the reactor vessel wall in a pool-type nuclear reactor. One or more intermediate plena containing substantially stagnant and thermally stratified coolant provide axial separation of the hot and cold plena. A dual pass forced bypass flow through annuli at the upper portion of the reactor vessel wall, in conjunction with the intermediate plenum and an annular gas space adjacent the reactor vessel wall, provide radial separation of the hot plenum and the vessel wall.

Abstract: The invention relates to a secondary heat transfer circuit for a liquid metal-cooled nuclear reactor, as well as to a steam generator which can be used in such a circuit.According to the invention, a downstream buffer tank and an upstream buffer tank are arranged within the steam generator. The upstream buffer tank is annular and surrounds and communicates with an area of the generator by which the liquid metal flows downwards between the exchange zone and the discharge tube. The pressure of the neutral gas pocket in the downstream buffer tank is higher than that of the pocket of the upstream buffer tank.Application to fast neutron nuclear reactors.

Abstract: 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.

Abstract: A system for increasing the temperature of a fluid heated by a high temperature gas cooled nuclear reactor to a sufficient temperature to supply the heat of reaction for a high temperature chemical process. The system includes a secondary loop having a working fluid heated to a first temperature by the nuclear reactor, and has a heat pump connected in the secondary loop and adapted to increase and thereby augment the temperature of the working fluid in the secondary loop sufficiently to supply the heat of reaction for a high temperature chemical process such as in a reformer. The system also provides low temperature heat in the form of steam which may be used in a turbine to provide power to the compressor of the heat pump and for auxilliary apparatus.

Abstract: A device for providing protection against heat and radiation for an intermediate heat exchanger immersed in the vessel of a nuclear reactor. In its upper part, the exchanger has an inner sleeve (8a) inside which a liquid metal circulates, and an outer sleeve (8b), these sleeves being joined by a Y-shaped connector (25). A peripheral space is provided around the outer sleeve (8b), inside the passage (3) through the slab (2) covering the reactor vessel. The protection device comprises a sleeve (27) fixed under the flange (18) and carrying, in its lower part, a solid piece (30) occupying the greater part of the peripheral space around the sleeve (8b). In its upper part, under the flange (18), the sleeve (27) carries a heat insulation means (32) of annular shape. The Y-shaped connector (25) is located in the central part of the sleeve (27), between the solid piece (30) and the heat insulation means (32). The invention is applicable, in particular, to fast neutron nuclear reactors cooled by liquid sodium.

Abstract: A pressurized water nuclear reactor comprises a reactor vessel arranged in a pool made in the form of a pressure vessel, the pool being filled with a strongly neutron-absorbing liquid, for example borated water. The reactor vessel, in addition to being connected to a primary system, is provided with a lower shutdown opening, arranged below the reactor core, for pool liquid and with an upper shutdown opening, arranged above the core, for pool liquid.

Abstract: The invention relates to a secondary heat transfer circuit for a liquid metal nuclear reactor.Each loop of the main circuit has in order a steam generator, a pump, and at least one heat exchanger positioned in the reactor vessel. A downstream buffer tank is located in the pipe connecting the generator to the pump, whilst the upstream buffer tank can be positioned either in the generator, or outside the latter.Application to the generation of electric power by means of a fast neutron reactor.

Abstract: The invention relates to a fast neutron nuclear reactor in which the primary pumps and exchangers are suspended on the rigid slab sealing the vessel containing the reactor core.The slab has in its thickness housings of reduced dimensions in which are confined the heads of the exchangers and the primary pumps. The flywheels of the pumps and part of the pipes of the secondary circuits are also contained in the housings. Other housings can be provided in the slab, particularly for the handling of fuels.Application to the improvement of the safety and reliability of fast neutron reactors is taught.

Abstract: A junction device between the delivery duct of a primary pump and a duct joined to the core support of a liquid metal cooled fast neutron nuclear reactor comprises a frusto-conical sleeve (6) widening out towards the inlet (2) of the duct joined to the core support, a connecting member (7) joined to the sleeve (6), a sealing device (18) interposed between the outlet end of the sleeve (6) and the inlet (2) of the duct joined to the core support, and an elastic means (6) interposed between the outlet end of the sleeve (6) and a support member joined to the core support. In its central portion the connecting member (7) carries the movable portion (14) of an articulated connection element the fixed portion (16) of which is carried by the pump. On its periphery this member (7) is connected sealingly and articulatedly to the delivery duct of the pump at the level of a spherical surface (9).

Abstract: The annular space (19) delimited by the main vessel (3) and an internal shell (16) is in communication with the zone (15) of the reactor vessel, in which the cold primary liquid is located. The annular space (20) delimited by the shell (16) and by an internal shell (17) is in communication with the lower part of the core (7) via tubes (31). Thus, the cold primary liquid is injected into the space (20), where it circulates from bottom to top, and flows into the space (19), where it circulates from top to bottom while at the same time cooling the main vessel (3).The invention applies, in particular, to fast fission nuclear reactors cooled by liquid sodium.

Abstract: A nuclear reactor of the type which uses liquid metal as primary and secondary coolants, and wherein the reactor vessel contains a core and a plurality of vertically extending cylindrical intermediate heat exchangers for carrying out heat exchange between the primary and secondary coolants; primary coolant circulation pumps disposed outside of the reactor vessel; a pipe for conducting to the circulation pump the primary coolant which has passed through the intermediate heat exchangers after leaving the core; and a pipe for guiding the primary coolant discharged from the circulation pump to the core through the reactor vessel.

Abstract: The present invention relates to a device providing anti-seismic support for an apparatus immersed in the bath of liquid alkali metal surrounding a fast neutron nuclear reactor, and abutting by a flange on a slab traversed by the apparatus and resistant to the load that it constitutes, wherein the flange for supporting the apparatus is connected to a sleeve for elastically taking up the horizontal displacements of its top part, independently of an inner envelope of the apparatus and on which a framework for supporting the apparatus whose bottom part is connected to the inner envelope, is fixed at a level determined as a function of the most dangerous earth tremor frequencies.

Abstract: A liquid metal cooled nuclear reactor of the kind wherein a fuel assembly is supported on a diagrid and submerged in a pool of coolant. The diagrid comprises a plenum supported on a load bearing undershell and has an array of resilient spikes upstanding from the upper face of the plenum each for locating a fuel sub-assembly. The load of the fuel assembly is distributed over the upper face plate of the plenum and transmitted to the undershell by an array of strut members.

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: Apparatus for insulating hot sodium in a reactor vessel in a pool-type nuclear reactor. The apparatus includes a flow isolated plenum in the reactor vessel for holding a stagnant quantity of sodium. The flow isolated plenum is located between a second plenum for holding hot sodium and the structural load bearing members of the reactor. The flow isolated plenum forms a thermally insulating field barrier between the hot sodium and the structural members.

Abstract: A liquid metal cooled fast breeder nuclear reactor of the pool kind has an intermediate heat exchange module comprising a tube-in-shell heat exchanger and an electromagnetic flow coupler in the base region of the module. Primary coolant is flowed through the heat exchanger being driven by electromagnetic interaction with secondary liquid metal coolant flow effected by a mechanical pump.

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

Abstract: A pool type nuclear fission reactor has a core, with a plurality of core elements and a redan which confines coolant as a hot pool at a first end of the core separated from a cold pool at a second end of the core by the redan. A fuel handling system for use with such reactors comprises a core element storage basket located outside of the redan in the cold pool. An access passage is formed in the redan with a gate for opening and closing the passage to maintain the temperature differential between the hot pool and the cold pool. A mechanism is provided for opening and closing the gate. A lifting arm is also provided for manipulating the fuel core elements through the access passage between the storage basket and the core when the redan gate is open.