Hochtemperatur-reaktorbau Gmbh

Hans-Georg Schwiers

Josef Schoening

Claus Elter

Wilfried Stracke

Reinhold Koerdt

Hans-Juergen Kolodzey

Josef Schoning

Rolf Fritz

Karl-Friedrich Kissel

Guenter Kissling

Reinhard Mauersberger

Paul Mitterbacher

Jurgen Kolodzey

Walter Nickel

Juergen Kolodzey

Gerhard Noll

A gas cooled high temperature reactor with spherical fuel elements surrounded by a reflector utilizes at least one ceramic tube and at least one metal tube for removal of pebbles from the core of the reactor. Each cermaic tube is surrounded directly by a ring of graphite columns wherein a plurality of recesses house a number of rod-shaped boron bodies. Additional plate-shaped boron bodies may advantageously be located in the bottom layes of the reflector.

Gas cooled high temperature reactor charged with spherical fuel elements

Process for the construction of a nuclear reactor having a reinforced concrete pressure vessel, comprising utilization of a corset frame to support the cavity liner, closing off the reactor cavity and installing the reactor components under 'clean conditions', simultaneous to the layer-by-layer pouring of the walls and top of the reinforced concrete pressure vessel. The erection of the supporting corset substantially reduces the overall assembly time of the nuclear power station without involving additional expense.

Process for the construction of a nuclear reactor with a reinforced

A passage through a reinforced concrete pressure vessel is provided, wherein the tolerance ranges required for the fastening of the components in the passage may be produced safely and without excessive expenditures. This is achieved by an arrangement including a lining having a first, outer tube resting against the concrete and a second tube arranged within the first tube.

Passage through the wall of a reinforced concrete pressure vessel

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.

Gas cooled high temperature reactor

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.

Bottom shield for a gas cooled high temperature nuclear reactor

A closure for a prestressed high-pressure vessel comprises an anchoring ring surrounding the opening of the prestressed concrete pressure vessel, a plurality of axial stressing cables and a plurality of cover stressing cables. The cover is separately prestressed and simultaneously anchored to the prestressed concrete pressure vessel. The anchoring rings on the concret need for releasing the axial stressing cables of the prestressed concrete pressure vessel.

Concrete cover for high pressure vessels

A pressure vessel for a nuclear reactor comprises a reinforced concrete vessel with at least one open area located in the wall of the concrete vessel, a lining means anchored on the inside surface of the concrete vessel and the opea area for protection of the surfaces and at least one expansion space in the concrete vessel immediately adjacent the lining means to permit movement of the lining means and distribution of the stresses in the lining means under various reactor conditions.

Reinforced concrete pressure vessels for nuclear reactor installations

A support structure for a nuclear power station having a prestressed cylindrical vessel comprising an annular ring of supports on a support wall and foundation wherein the prestressed cylindrical vessel rests on the ring of supports is disclosed. The supports, through their defined distances from each other, provide a constant cooling flow of the supports and a constant temperature over the entire operating period of the power station. This results in supports that are maintenance-free. The supports are constructed of plastic washers with steel inserts and are of sufficient height such that in the case of earthquakes, maximum vibrations of the reinforced concrete pressure vessel may be absorbed within an accurately set terminal boundary of the annular support wall.

Support structure for a prestressed cylindrical pressure vessel

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.

Support structure for a core of a high temperature reactor

A supporting floor for the core of a nuclear reactor utilizes a plurality of independent support columns forming the floor of the reactor and resting on the bottom layers of the reactor. The support columns are surrounded by a side reflector which is in turn surrounded by a thermal side shield. Between the thermal side shield and the side reflector are disposed retaining means for maintaining the columns close together and preventing the formation of large gaps during operation.

Supporting floor for the core of a nuclear reactor

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.

Differential pressure flowmeter for a gas cooled high temperature

A mounting for power conductor and instrument lead penetrations in nuclear reactors provides a device that is simple, compact and at the same time easily installed, repaired or replaced. The mounting comprises a cylinder like, stepped housing which is to pass through the pressure vessel wall of the nuclear reactor and house at least one and preferably a plurality of electrical conductors.

Mounting of power conductor and instrument lead penetrations for nuclear

The invention concerns a vaulted cover to close a vertical recess in a pressure vessel with a plurality of fittings welded to the cover for the passage of steam pipes and with heat insulation applied to the inside of the cover consisting of a thermally insulating material and a plurality of rectangular cover plates arranged on the thermally insulating material, wherein the cover plates are fastened to the cover by means of holding bolts penetrating the entire insulation.

Vaulted cover assembly to close a vertical recess in a pressure vessel

The leakage of gases in gas cooled nuclear reactors is detected by an arrangement utilizing a flexible material to cover areas of potential leakage and create detection cavities inside the concrete vessel of a nuclear power plant. The detection cavities are connected to the gas collector housed within the concrete vessel by means of gas-tight connecting conduits or lines. A negative pressure is applied to the gas collection device connecting conduits and detection cavities to extract any gas leakage within the power plant. Gas measuring devices and display devices are included in the system to identify, quantify or locate gas leakage.

Leak detection installation

A vaulted cover for an opening in a pressure vessel comprising a vaulted center piece and an annular rim surrounding thermal insulation material of a cover flange. The rim is assembled of two coaxially arranged cylindrical sections. Expansion gaps and sealing disks are provided about pipe fittings in said vaulted cover in a manner that permits release of pressure through gaps formed by said sealing disks.

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Ketsch, Germany

Hans-Georg Schwiers