Abstract: The invention relates to a fast neutron nuclear reactor equipped with residual power removal devices.Each device comprises an evaporator incorporating a bundle of tubes in glove finger-like form immersed in the liquid metal contained in the reactor vessel, an adiabatic collector constituted by a pipe traversing the slab sealing the reactor vessel and a condenser in which the heat transfer fluid, such as mercury, contained in said device is condensed by heat exchange with the atmospheric air sucked in through the chimney or flue.Application to fast neutron nuclear reactors.

Abstract: 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.

Abstract: 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.