Patent Number: 053923243
Section: claims

1. In a fast-neutron nuclear reactor comprising a vessel containing a reactor fuel core and a system for cooling said core in which a liquid metal circulates and on which is placed at least one steam generator including a substantially cylindrical casing having a vertical axis, in which the liquid metal circulates, water-feed means and means for heat exchange between the liquid metal and the feed water, a device for removing residual power from said reactor at shutdown and/or under accident conditions, including, around said casing of said at least one steam generator, a tubular unit for recovering heat and for guiding a cooling gas including a metal shell covered on the outside by a layer of thermally insulating material and carrying, on its internal surface, a plurality of fins placed longitudinally of the shell and means for causing the cooling gas to flow in an annular space between said tubular unit and said casing of said at least one steam generator constituted by a vertical chimney connected to an upper part of said annular space via a pipe and at least one air inlet port in said annular space, at a lower part of said tubular unit, wherein said tubular unit is connected to a support structure of the steam generator by means of a bellows. 2. Device according to claim 1, wherein an expansion bellows is interposed on the pipe linking said tubular unit to said chimney.