Hochtemperatur-reaktorbau Gmbh

Gerhard Becker

Josef Schoening

Claus Elter

Josef Schoning

Johannes Henssen

Hans-Gunter Gross

H Guenter Gross

A heat insulation system may protect surfaces along which a hot gas stream is conducted. The insulation may be several plies of slightly compressed ceramic fiber mats, separated by intermediate plates. Cover plates are attached to the hot side. The cover plates are mounted by holding bolts on the support structure carrying the insulation. The support structure may be the liner of a nuclear reactor pressure vessel. Thickness and size of the cover plates are optimized with regard to the stresses occurring at the edges of the holes provided for the holding bolts to ensure dimensional stability of the fiber mats and the functional capability of the metallic mounting system during a long period of time. Several sealing sleeves may be arranged on each holding bolt. In a first solution, some intermediate plates exhibit lug-shaped points stamped out of the plates on both sides in vertical areas of the heat insulation system. The lug-shaped points which transfer the forces of the fiber mats to the intermediate plates. In a second solution, the function of these intermediate plates may be taken over by layers of expanded metal arranged between the fiber mats.

Heat insulation system for surfaces along which a hot gas stream is

A nuclear power plant with a gas cooled high temperature reactor, installed in a prestressed concrete pressure vessel with the operational and decay heat removal systems. The prestressed concrete pressure vessel has a thermal protection system, with a thermal insulating layer and a liner cooling system. The liner cooling system, which is includes water carrying cooling pipes, which along with intermediate heat exchangers and cooling water pumps make up a closed intermediate cooling loop used for removal of the decay heat in case a failure of the decay heat removal systems. The elements of the invention assure an adequate water flow for the removal of decay heat in the liner cooling system in any situation, i.e. such that the decay heat may also be removed by natural convection. These element insure a sufficient driving pressure differences and minimize pressure losses in the intermediate cooling loop.

Nuclear power plant with a gas cooled high temperature reactor

A concrete reactor pressure vessel for a low capacity, gas cooled nuclear reactor is provided. To assure the safe containment of the cooling gas in an economical manner and to remove the heat generated in the reactor core, the pressure vessel is equipped with reinforcing or prestressing elements. Cooling gas transfers its heat to a heat exchanger means consisting of the liner of the pressure vessel and cooling pipes mounted on the concrete side of the liner with water flowing through the cooling pipes. The heat exchanger comprises on the secondary side at least two mutually independent systems, each provided with collector pipe means located outside the reactor pressrue vessel for the forerunnings and afterrunnings of the cooling water. Each cooling pipe is connected by means of an inlet and a drain line with the corressponding collector pipe means.

Concrete reactor pressure vessel for a gas cooled nuclear reactor of low

A cost-effective configuration of a metal liner for a reinforced concrete pressure vessel is disclosed wherein only stud shear connectors and cooling tubes of the liner cooling system are used to anchor the liner and the passages provided in the liner and the wall of the vessel. In the areas of the introduction of forces, stud connectors of different stud rigidities are used. In the anchoring of loads which is again effected by stud connectors only, further transmission is obtained by means of reinforcing rods.

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Mannheim, Germany

Gerhard Becker