Abstract: Disclosed is a plant for the production of hydrogen, preferably for the hydrogenating gasification of coal, through utilization of heat energy derived from a gas-cooled, high-temperature nuclear reactor, comprising:A. a thick-walled pressure vessel;B. a high temperature reactor contained in a centrally oriented cavity within the vessel;C. a plurality of process gas cracking reactors contained within the wall of the vessel;D. a number of steam generators corresponding to the number of the gas cracking reactors, the generators being contained in the wall of the vessel;E. a number of recuperative heat exchangers corresponding to the number of gas cracking reactors, each of the heat exchangers being contained in the wall of the vessel and being positioned closely adjacent one of the gas cracking reactors; andF. a coaxial conduit connecting said adjacent heat exchanger and gas cracking reactor pairs.

Abstract: Disclosed is plant for the production and utilization of heat energy derived from a gas-cooled, high temperature nuclear reactor, preferably to produce hydrogen in secondary reactors, comprising a thick-walled vessel; a high temperature reactor contained in a centrally oriented cavity within the vessel; a number of steam generators corresponding to the number of the secondary reactors, the generators likewise being contained in the wall of the vessel; a number of blowers corresponding to the number of the steam generators each of the blowers also being contained in the wall of the vessel and being positioned beneath one of the steam generators; conduit means for transporting hot cooling gas from the nuclear reactor to the secondary reactors and from the secondary reactors to the blowers; and conduit means for transporting the cooling gas from each of the blowers to the nuclear reactor in a manner so that the gas surrounds the nuclear reactor, the secondary reactors, the blowers and the hot gas conduit means.

Abstract: Disclosed is a nuclear power plant comprising a closed gas-cooling circuit and a plurality of identical, parallel-connected thermodynamic circuits (loops) symmetrically installed. Each of these loops constitutes a turbine assembly comprising a turbine and a compressor as well as devices for the internal and external heat exchange and is coupled with a nuclear reactor. The reactor is installed in the center of a cavern located in a vessel made of reinforced concrete, while the components comprising the circuit and the conduits connecting the various components are installed in cavities inside the reinforced concrete vessel. The turbine assemblies are located in horizontal shafts in the lower region of the vessel, and vertical shafts are provided for the gas transport pipes, which are arranged coaxially therein. These shafts and also pods for the heat exchange equipment are arranged symmetrically about the vessel axis.

Abstract: A power plant having a closed gas-cooling circuit for the production of process heat to be transferred to a secondary circuit, comprising: (a) a vessel comprising a generally solid block of material; (b) a high-temperature reactor positioned within the vessel; (c) a plurality of heat exchanger units positioned about said reactor in the reactor in the vessel, the heat exchanger units comprising each a high temperature heat exchanger and a low temperature heat exchanger coupled serially therewith, each of the heat exchanger units being removably mounted in a vertically oriented shaft in the material; (d) first means for conducting a portion of a hot gas stream leaving the reactor to each of the high temperature heat exchangers where the hot gas is partially cooled by indirect contact with a working fluid in the secondary circuit; (e) second means for conducting said cooled gas from each of the high temperature heat exchangers to said low temperature heat exchangers coupled therewith where the gas is further coo

Abstract: Disclosed is a nuclear power plant comprising a pressure-tight safety vessel surrounding the entire plant, an inner vessel of reinforced concrete, a high-temperature reactor contained in the inner vessel, a gas turbine assembly having a turbine and a high- and low-pressure compressor located in a horizontally oriented chamber below the reactor, a plurality of heat exchange units positioned in a plurality of vertically oriented pods spaced radially symmetrically about the reactor and suitable conduits for carrying the reactive gas between the system components. The conduits are arranged in generally horizontally and vertically oriented straight lines, and the conduits for carrying low-pressure gas comprise a horizontal system positioned beneath the turbine assembly having a plurality of coaxial connecting tubes, collectors and distributors as well as normal conduits, so that high pressure gas flows in the internal passage and low-pressure gas flows in the outer passage.

Abstract: The core pile of a gas-cooled nuclear reactor is controlled by a plurality of absorbent graphite rods that are inserted into the pile according to a pre-determined pattern, the pattern being such that the density of distribution of the control rods over the cross-sectional area of the core pile is radially increased in the direction of the core periphery. By this control rod arrangement an overly severe concentration in the flow of neutrons on the periphery of the cord pile is avoided, and a more even distribution of neutron flow across the diameter of the reactor is obtained.