摘要:
Gas-cooled nuclear reactors include circulation systems for cooling gas to remove the heat generated in the reactor core. An improved arrangement includes a plurality of steam generators in a horizontal plane located above the horizontal plane of the reactor core. The cooling gas circulates from the bottom of the reactor core to the top. Improved heat removal is accomplished in this manner as the heated cooling gas enters the steam generators after passage through the reactor core without undergoing further circulation in a horizontal or inverse vertical direction.
摘要:
A barrier system for a high temperature reactor. The reactor utilizes spherical fuel elements consisting of coated particles of a fissionable material embedded in a graphite matrix, the coating forming a first safety barrier against the release of fissionable material, and the graphite matrix a second such safety barrier. The reactor is surrounded by a prestressed concrete pressure vessel clad on the inside with a metal liner. The metal liner acts as a third safety barrier, while the concrete body of the prestressed concrete pressure vessel forms the fourth, and outermost safety barrier. A plurality of passages are located in the pressure vessel which are closed off by closure means. The closure means provide sealment between the third and fourth barriers in the area of the passages. By utilizing the concrete pressure vessel as a safety barrier in this manner, the need for a separate protective reactor housing is eliminated.
摘要:
A process and an installation for the securing against excessive pressure in a prestressed concrete pressure vessel of a gas cooled high temperature reactor and for the prevention of activity release into the environment. The process comprises three steps and in each step pressure reducing installations become effective upon the rise of pressure in the prestressed concrete pressure vessel over a predetermined value. In the first step the pressure vessel is relieved by means of the operational gas purification apparatus and a conveying blower into the storage vessels for the cooling gas. In case of a further rise in pressure, in a second step a discharge path equipped with a safety valve and a check valve is opened, which also relieves into the storage vessels while by-passing the gas purification installation. In the third step, if the pressure continues to rise over a predetermined value, a line closed during normal operation by a rupture disk, is open, said line being connected with the discharge path and opening into the air circulation installation of the nuclear reactor plant. The air circulation installation is connected by means of a filter system with an exhaust stack.
摘要:
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.
摘要:
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.
摘要:
Disclosed is a closing arrangement for large passages in a prestressed pressure vessel comprising a cover means for covering the opening of a passage in the prestressed pressure vessel, an annular structural part having an inner boundary surface surrounding the covering means at a distance and defining a space therebetween, a means for securing the annular structural part to the prestressed pressure vessel and a plurality of connecting elements disposed in the space between the annular structural part and the covering means in abutting relationship with the inner boundary surface of the annular structural part and the covering means.
摘要:
The invention concerns a roof reflector suspended from the thermal cover shield of a gas-cooled pebble-bed reactor with a plurality of passages for absorber rods arranged in a triangular lattice, and with channels for the passage of the cooling gas. The roof reflector comprises a plurality of essentially hexagonal graphite blocks arranged in several layers to form vertical, closely-adjacent columns. A process for the disassembly of the roof reflector is further provided.
摘要:
Disclosed is a nuclear reactor plant, comprising:a prestressed concrete pressure vessel;a high temperature reactor arranged in a central cavity within the vessel;a closed gas cooling circuit including at least one housed gas turbo unit arranged in a turbine duct in the wall of the vessel, said unit including a turbine and a compressor and having detachable bearings; means for exchanging heat and means for transporting gas in the cooling circuit including hot gas from the reactor to the turbine, said heat exchange means and said gas transport means being arranged in recesses in the wall of the vessel;means for forming a detachable plug-in type connection between the hot gas transport means and each turbo unit;means, positioned at the edge of the turbine duct, for connecting all remaining gas transport means to the turbo unit;means, including peripheral sealing members positioned between the inside wall of the turbine duct and the outer housing of the turbo unit, for separating each of the remaining gas transport means from each other;means for detachably connecting each turbo unit to the inside of its turbine duct;remote control means for detaching these connecting means;means, including at least one lifting device controllable from outside of the vessel through a bore in the wall of the vessel, for dismounting each turbo unit from within its turbine duct;means for detaching from outside of the vessel all connections to each turbo unit which must be removed in order for removal of the turbo unit from its turbine duct; andmeans, including a duct through the wall of said vessel, for gaining access to each bearing of each turbo unit.
摘要:
Disclosed are a method and apparatus for regulating and shutting down a gas cooled nuclear reactor having a bed of spherical fuel elements, wherein regulation of the reactor is accomplished by a first set of absorber rods in the side reflector of the reactor, partial shutdown is achieved by a second set of absorber rods movable in the top reflector and in the space above the fuel elements, and total shutdown is accomplished by a third independent set of absorber rods which can be moved downwardly into the fuel elements.
摘要:
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.