Abstract: The invention relates to a gas cooled high temperature reactor located in the cavity of a pressure vessel, with spherical fuel elements, and removal apparatus for fuel elements. The latter is made of at least one ceramic pebble outlet tube extending through the graphite structural parts of the nuclear reactor (bottom reflector, bottom layers) and a number of metal pebble outlet tubes installed through the bottom of the pressure vessel. They are arranged coaxially in the liner of the passage through the vessel. To be able to dismantle the metal pebble outlet tubes, they are constructed of several releasably interconnected tube segments. Between the uppermost tube segment and the corresponding ceramic pebble outlet tube a compensating tube is provided and connected with the tube segment by means of a sliding joint. The other end of the compensating tube is fastened to the thermal bottom shield.

Abstract: A support structure for a nuclear reactor is disclosed comprising a primary support element connected with the roof of the pressure vessel and a secondary support element joined with the primary support element. The thermal roof shield and the roof reflector are connected to the secondary support element.

Abstract: It is desirable to being able to vary the temperature of a loop exposed to a flow of hot gases in gas cooled nuclear reactor installations without thereby affecting the gas temperature in the other loops. It should be possible in an extreme case to take the affected loop out of service. This is achieved by arranging under the heat absorbing components in the hot gas channel a means for mixing gas connected with a cold gas line.

Abstract: A gas cooled, high temperature nuclear reactor is provided with a base plate arranged under the reactor core and over the bottom of the prestressed concrete pressure vessel serving as the bottom shield. The bottom shield comprises at least two plates arranged coaxially with respect to each other, one above the other. Each plate comprises several partially interconnected parts with the lower plate being placed at an axial and vertical distance from the bottom liner of the prestressed concrete pressure vessel and also from the upper plate.

Abstract: A support structure for the core of a gas cooled high temperature reactor utilizes a plurality of compression members arranged in an annular space between a plurality of graphite blocks forming the roof, bottom and cylindrical side walls of a reflector surrounding the reactor core and a thermal shield surrounding the reflector. Each compression member comprises a compression body, a first bolt part having the configuration of a threaded rod, a threaded area on the inner surface of the compression body for receiving the threaded bolt part, a second bolt part having the configuration of a piston, a sliding area on the inner surface of the compression body for receiving the piston bolt part, and means for producing a compressive force between the piston bolt part and the compression body. The plurality of compression members are attached to the reflector and thermal shield by way of a plurality of ball-and-socket joints.

Abstract: An apparatus for measuring the flow of gas in a blower of a gas cooled high temperature nuclear reactor comprising a blower, a blower shield communicating with the blower, an inlet conduit in the blower shield for conducting gas flow to the blower, an exit conduit in the blower shield for conducting gas flow from the blower and means for measuring the flow of gas in the exit conduit. The measuring means includes a venturi tube having a narrowed area in the exit conduit, a first measuring channel in communication with the gas flow in the narrowed area, a second measuring channel in communication with the gas flow in the exit conduit upstream from the narrowed area, and means for comparing the relative gas flow in the first and second measuring channels. A transducer connected to the first and second measuring channels performs the comparing and measuring steps.

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: 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.