Abstract: An improved design for shielding the component parts of a gas turbine power plant from radiation in a gas transport conduit is disclosed. The radiation shield and shielded gas conduit utilize a shielding arrangement comprising a displacement body arranged centrally within the conduit and a shielding annulus surrounding the displacement body. A shielding device provides for a first annular flow path for reactor cooling gas between the displacement body and shielding annulus and a second annular flow path for reactor cooling gas between the shielding annulus and the conduit housing. The shielding device provides protection against radiation without significantly disrupting the flow of the cooling gas in the conduits.

Abstract: Disclosed is an angled gas conduit for a gas flowing under high pressure and at an elevated temperature which comprises a first conduit part and second conduit part connected at an angle forming an area of deflection for gas flowing within said conduit parts, an apertured plate arranged at an oblique angle within said conduit in the area of deflection, the apertured plate having a plurality of circular passages for directing the flow of gas in the conduit. A mounting arrangement for the apertured plate is also disclosed.

Abstract: The drive for an absorber rod for a nuclear reactor has a drive piston guided in a cylinder combined with the absorber rod forming an absorber unit. In order to compensate the forces exerted by the medium of the pressure vessel on the absorber unit and tending to pressure the absorber rod axially outward, an equalizing surface is arranged in the absorber unit. The equalizing surface is exposed on one side to the medium of the pressure vessel and/or the cooling medium of the absorber rod, so that an equalizing force is acting on the absorber unit. In the event of a failure of the drive medium acting on the drive piston of the absorber unit or during fluctuations and changes of the internal pressure in the pressure vessel, the absorber unit remains in its existing position, i.e. no unintentional withdrawal of the absorber rod from the pressure vessel takes place.

Abstract: A plurality of graphite blocks forms a side reflector with an area of each block that allows a certain amount of radiation induced wear in a predefined zone facing the core of the reactor and an area separate from the wear zone for carrying the load bearing function of the side reflector. Most critical is the area of the upper range of the reactor core where radiation induced wear is greatest. The wear is taken into consideration in the design layout of the side reflector in the form of an increment to the thickness of the wall. The load bearing areas of each block provide the load bearing area for the entire side reflector. The side reflector is particularly suitable for high temperature gas-cooled reactors of the pebble bed type.

Abstract: A gas-cooled high temperature reactor is equipped with a supporting structure for the reactor core having a gas conduit passing through the support structure from a hot gas collecting space beneath the supporting structure. The supporting structure itself rests on a floor plate in a columnar arrangement. The floor plate also rests on support columns and possesses a disk-like center portion indirectly supporting the reactor core and an outer annular portion supporting a lateral thermal shield around the reactor core.