Abstract: A power-generation system for a nuclear reactor includes a power unit, a reactor heat exchanger, and an auxiliary combustion system. The power unit produces compressed air that is heated by the reactor heat exchanger. The auxiliary combustion system includes an auxiliary combustor located external to the power unit and fluidly connected with the compressed air to increase the temperature of the compressed air.

Abstract: A power-generation system for a nuclear reactor includes a power unit, a heat exchanger, and a temperature control system. The power unit produces compressed air that is heated by the nuclear reactor via the heat exchanger. The temperature control system includes a heat transfer fluid and a heat exchanger fluidly connected with the compressed air to transfer heat between the compressed air and heat transfer fluid to control the power level of the power unit.

Abstract: A compressor case to blade tip clearance system comprising a rotor having blades with tips, the case including an inner case comprising at least one surface feature fluidly coupled to a distribution manifold disposed in a cooling air passageway, the at least one surface feature configured to interact with the cooling air, and a tip clearance located between the tips and the inner case; wherein the tip clearance is maintained responsive to a flow of the cooling air over the at least one surface feature.

Abstract: A turbine engine comprising a compressor section and a turbine section in serial flow arrangement defining a working air flow path with a heat exchanger in fluid communication the working air flow path, and a nuclear fuel in thermal communication with the heat exchanger and a release valve in fluid communication with the working air flow path.

Abstract: A dual-cycle heat engine employing a first cycling working fluid and a second cycling working fluid whose cycles overlap when fused into a combined working stream so as to preserve compression heat generated during compression of the first working fluid thereby yielding enhanced work extraction when complying with additional thermodynamic requirements.

Abstract: Disclosed are systems and methods for pump control of a closed thermodynamic cycle system, such as a Brayton cycle. Operational parameters such as working fluid temperature, thermal fluid temperature, stream pressure, and power generation may be the basis for controlling a thermal fluid pump rate.

Abstract: A nuclear steam supply system having a start-up sub-system for heating a primary coolant. In one embodiment, the invention can be a nuclear steam supply system comprising: a reactor vessel having an internal cavity, a reactor core comprising nuclear fuel disposed within the internal cavity; a steam generating vessel fluidly coupled to the reactor vessel; a primary coolant loop formed within the reactor vessel and the steam generating vessel, a primary coolant in the primary coolant loop; and a start-up sub-system fluidly coupled to the primary coolant loop, the start-up sub-system configured to: (1) receive a portion of the primary coolant from the primary coolant loop; (2) heat the portion of the primary coolant to form a heated portion of the primary coolant; and (3) inject the heated portion of the primary coolant into the primary coolant loop.

Abstract: A system for liquefying natural gas that includes a process and apparatus for enhancing the performance of one or more gas turbines. Gas turbine power output can be stabilized or even enhanced using the interstage cooling system configured according to one or more embodiments of the present invention. In one embodiment, partially compressed air from a lower compression stage of a gas turbine is cooled via indirect heat exchange with a primary coolant before being returned to a higher compression stage of the same gas turbine. Optionally, the interstage cooling system can employ one or more secondary coolants to remove the rejected heat from the primary coolant system.

Abstract: Methods of operating a supercritical Brayton cycle integrated with another cycle for power, cogeneration, or poly-generation using solar energy as a main source of energy. A system includes a supercritical CO2 Brayton cycle as a topping cycle and any one or more of a power cycle, a cooling cycle, a steam production cycle, and a water desalination cycle as a lower cycle. When not enough solar irradiation is available to power the combined cycle, the lower cycle is only operated or both part of the topping cycle as well as the lower cycle through the solar thermal energy and/or the stored thermal energy.

Abstract: A multi-pressure radial turbine system including a high-pressure pump and a low-pressure pump for pressurizing liquid-phase heating media introduced therein to different pressures; a high-pressure evaporator and a low-pressure evaporator for vaporizing the liquid-phase heating media delivered from the high-pressure pump and the low-pressure pump by absorbing heat from a high-temperature heat source; one multi-pressure radial turbine that expands the gaseous heating media having different pressures and temperatures, supplied from the high-pressure evaporator and the low-pressure evaporator, to obtain output power; and a condenser for condensing the gaseous heating medium expanded in the multi-pressure radial turbine by making the medium release heat to a low-pressure heat source. A cycle circuit is formed through which the heating medium circulates while repeatedly changing its state between vapor and liquid.

Abstract: A thermal/electrical power converter includes a gas turbine with an input couplable to an output of an inert gas thermal power source, a compressor including an output couplable to an input of the inert gas thermal power source, and a generator coupled to the gas turbine. The thermal/electrical power converter also includes a heat exchanger with an input coupled to an output of the gas turbine and an output coupled to an input of the compressor. The heat exchanger includes a series-coupled super-heater heat exchanger, a boiler heat exchanger and a water preheater heat exchanger. The thermal/electrical power converter also includes a reservoir tank and reservoir tank control valves configured to regulate a power output of the thermal/electrical power converter.

Abstract: A method of storing heat includes moving a portion of a heated fluid from at least one reactor core to at least one tank having solid media, storing heat from the portion of the heated fluid in the solid media, and transferring the stored heat from the solid media to a fluid that can be used by a power plant to generate electrical energy. A system for storing heat in a nuclear power plant includes at least one tank comprising solid media structured and arranged to store heat and an arrangement structured and arranged to pass a first fluid through the at least one tank, transfer heat from the first fluid to the solid media, store the heat in the solid media, and transfer the heat from the solid media to a second fluid. This Abstract is not intended to define the invention disclosed in the specification, nor intended to limit the scope of the invention in any way.

Abstract: A jet pump sensing line support clamp may be used for sensing line repair, replacement, and damage prevention or reduction. The clamp may affix to jet pump sensing line supports and confine the individual jet pump sensing lines. The clamp may provide for further access or securing of the lines in the support through the clamp. Methods of installing the clamp may include attaching and tightening the clamp against the sensing lines.

Abstract: Disclosed is an advanced process that relates to the enhanced production of energy using the integration of multiple thermal cycles (Brayton and Rankine) that employ multiple fuels, multiple working fluids, turbines and equipment. The method includes providing a nuclear reactor, reactor working fluid, heat exchangers, compressors, and multiple turbines to drive compressors that pressurize a humidified working fluid that is combusted with fuel fired in at least one gas turbine. The turbine(s) provide for electrical energy, processes or other mechanical loads.

Abstract: Disclosed herein is a method comprising heating helium in a core of a nuclear reactor; extracting heat from the helium; superheating water to steam using the heat extracted from the helium, expanding the helium in a turbine; wherein the turbine is in operative communication with an electrical generator; and generating electricity in the electrical generator.

Abstract: A method of storing heat includes moving a portion of a heated fluid from at least one reactor core to at least one tank having solid media, storing heat from the portion of the heated fluid in the solid media, and transferring the stored heat from the solid media to a fluid that can be used by a power plant to generate electrical energy. A system for storing heat in a nuclear power plant includes at least one tank comprising solid media structured and arranged to store heat and an arrangement structured and arranged to pass a first fluid through the at least one tank, transfer heat from the first fluid to the solid media, store the heat in the solid media, and transfer the heat from the solid media to a second fluid. This Abstract is not intended to define the invention disclosed in the specification, nor intended to limit the scope of the invention in any way.

Abstract: A nuclear fusion reactor (2) or nuclear fission reactor (22) is used as a heat source. A heat exchanger (11 or 37) that contains water to be heated (15) is used for water vapor generation. A circulating pipe (10 or 26) through which a fluid for cooling the nuclear fusion reactor or nuclear fission reactor or for conducting heat exchange circulates is disposed so as to extend in the heat exchanger and be in contact with the water to be heated. Water vapor is thus generated. This water vapor is jetted toward the sky at a state of collimation through a vapor discharge pipe (12 or 36). A cloud for blocking sunlight is formed in the sky from the water vapor jetted to reduce the temperature of the earth surface. This enables a weather modification without discharging any greenhouse gas, e.g., CO2.

Abstract: Disclosed herein is a method comprising heating helium in a core of a nuclear reactor; extracting heat from the helium; superheating water to steam using the heat extracted from the helium, expanding the helium in a turbine; wherein the turbine is in operative communication with an electrical generator; and generating electricity in the electrical generator.

Abstract: Disclosed herein is a method comprising heating helium in a core of a nuclear reactor; extracting heat from the helium; superheating water to steam using the heat extracted from the helium; expanding the helium in a turbine; wherein the turbine is in operative communication with an electrical generator; and generating electricity in the electrical generator.

Abstract: In a nuclear power plant making use of a high temperature gas cooled reactor, it is necessary, prior to commencing power generation and connection of a generator to an electrical distribution grid, to condition the power generation circuit of the plant. This involves creating stable conditions within the power generation circuit. To this end, the plant includes a start-up blower system for circulating working fluid, typically helium, around the power generation circuit until the desired conditions are satisfied. The start-up blower system typically includes a normally open in-line valve, at least one blower connected in parallel with the in-line valve and a normally closed isolation valve connected in series with the blower. Conditioning the power generation circuit will typically include stabilizing the pressure in the circuit at between 10 bar and 50 bar.

Abstract: In a nuclear power plant making use of a high temperature gas cooled reactor, it is necessary, prior to commencing power generation and connection of a generator to an electrical distribution grid, to condition the power generation circuit of the plant. This involves creating stable conditions within the power generation circuit. To this end, the plant includes a start-up blower system for circulating working fluid, typically helium, around the power generation circuit until the desired conditions are satisfied. The start-up blower system typically includes a normally open in-line valve, at least one blower connected in parallel with the in-line valve and a normally closed isolation valve connected in series with the blower. Conditioning the power generation circuit will typically include stabilizing the pressure in the circuit at between 10 bar and 50 bar.

Abstract: Passive emergency cooling in response to a loss of coolant accident (LOCA) in a PWR, having an integral reactor pressure vessel incorporating the steam generators and housed in a small high pressure containment vessel, is provided by circulating cooling water through the steam generators and heat exchangers in an external tank to cool the reactor vessel at a rate sufficient to lower the pressure in the reactor vessel below that in containment to reverse mass flow out of the reactor vessel and keep the reactor core covered without the addition of makeup water. Suppression tanks inside the small high pressure containment structure limit peak blowdown pressure in containment and provide flood-up water and gravity fed makeup water to cool the core. Diverse cooling is provided by natural circulation of air, and if needed, water, over the spherical containment structure.

Abstract: The subject of the present invention is to provide a nuclear reactor plant of which is a direct cycle nuclear reactor using a carbon dioxide as a coolant such that a heat evacuation for liquefying coolant is reduced while a compressive work is reduced by using a condensation capability of a carbon dioxide for enhancing a cycle efficiency. The nuclear reactor plant is comprised of a nuclear reactor 1, a turbine 2, and wherein, the coolant of supper critical state is heated by a heat of a nuclear reactor to directly drive a turbine, a gaseous coolant discharged from said turbine is chilled and compressed after said turbine is driven for keeping in a critical state, and then said coolant is circulated again into said nuclear reactor, and wherein, a carbon dioxide is used as said coolant, and a predetermined ratio of gaseous coolant discharged from said turbine is liquefied for being compressed in a liquid state while a rest of gaseous coolant is compressed in a gaseous state.

Abstract: A steam generator which finds particular application as a superheater and reheater for transfer of heat from the gas coolant of a nuclear power reactor to a secondary fluid medium. The lower pressure reheater is located inside of the nuclear pressure vessel containing a reactor core, as is the high pressure main steam tube bundle which is comprised of an economizer/ evaporator tube bundle stage and an initial superheater tube bundle stage. The remaining superheater tube bundles which comprise the intermediate superheater and the finishing superheater are located outside of the nuclear pressure vessel, where they are heated regeneratively by reheat steam which is emerging from the nuclear pressure vessel at a temperature higher than required by the reheat turbine, The main steam system can be designed for either subcritical or supercritical pressure operation.

Abstract: A throttle valve having defined characteristics controls flow of gas from a gas heater to a turbine in a closed cycle gas turbine system. The gas heater may be a nuclear reactor fueled by fission material preferably having a negative temperature coefficient of reactivity whereby the reactor automatically ceases heat production upon closing of the throttle valve.

Abstract: In a power station installation which is designed as a combined installation, i.e. consists of a gas turbine group (2, 3, 4, 5, 6, 8) and of a steam cycle (13, 16, 17, 18, 19, 20) downstream of the gas turbine group, the steam rate being generated in a waste heat boiler (13) by heat exchange with the exit gases from the gas turbine (5), a heat exchanger (7), which is a component of a closed cycle, with a high-temperature reactor (12) as the heat source is placed downstream of the last compressor (4) of the gas turbine group and upstream of the combustion chamber (8). In this heat exchanger (7), the compressed air undergoes vigorous caloric processing before it flows into the downstream combustion chamber (8) in which the final caloric processing of the hot gases for charging the gas turbine (5) is accomplished. The essential point here is that the pollutant emissions of any type, in particular CO.sub.

Abstract: A system for improving the performance of nuclear power plant feedwater control systems and simplifying steam generator low water level reactor protection logic includes a plurality of water level channels for measuring steam generator water level and generating a plurality of signals representative thereof. The median steam generator water level signal is selected from among the plurality of steam generator water level signals. The median steam generator water level signal is then communicated to the feedwater control system through an output interface.

Abstract: A high temperature reactor has a downflow type nuclear reactor provided at the top portion thereof with a gas inlet and a plurality of steam generators provided around the nuclear reactor. The steam generator has a heat insulation tube provided vertically from the bottom portion of the nuclear reactor to a level higher than the top gas inlet of the reactor, a heat exchanger provided in a descending gas flow path formed around the heat insulation tube, and a gas circulator provided at the bottom portion thereof for feeding a gas coolant to the gas inlet of the nuclear reactor, whereby said gas coolant, after being used for cooling the reactor core, delivered from the bottom portion of the reactor, flows into the heat insulation tube, flows upward to the top portion of the tube, is reversed in direction at the top end of the tube, then flows downward through the descending gas flow where the heat exchanger is provided, and is then recycled to the gas inlet flow path of the reactor by the gas circulator.

Abstract: A nuclear reactor using gas as a primary coolant and a liquid as a moderator and/or reflector. Gas coolant flows through inlet passages around the outlet plenum to a distributor plate. The gas is directed between fuel element housing thimbles and fuel elements therein, through the fuel elements, and into the reactor outlet plenum. Fins on the thimble housings conduct heat to the gas from a liquid moderator circulating in the core. The use of a liquid moderator enhances safety, allows the fissile material and reactor mass to be reduced and eliminates problems associated with cooling of a solid moderator.

Abstract: A nuclear power plant that is of a walk-away type with an encapsulated reaction core in a glass matrix pool having a reactive Thorium/U.sup.233 composition in a containment structure that radiates thermal energy for use in a closed gas cycle with a split path having a common compressor with an output that divides into a first path communicating with the thermal source and a second path communicating with an intercooler, the two paths combining in a turbine with an expander that discharges to a common collector for return to the compressor.

Abstract: In methods and devices for removing a blower from a gas-cooled nuclear reactor, removal bells have previously been used which require considerable free space above the blower in the case of vertically extending blower configurations. In order to achieve a lower structural height according to the invention, the periphery of the connection location between the blower housing and the steam generator housing is overlapped by a flange ring attached to the steam generator housing. The blower housing performs a vertical moving maneuver within the range of the height of the flange ring, during which a sealing cover and a transport cover are inserted through a lateral opening in the flange ring. The sealing cover is deposited on the edge of the opening of the steam generator housing and the transport cover is coupled to the bottom region of the blower housing. The blower housing is then removed together with the blower.

Abstract: A single loop nuclear power plant with a helium cooled high temperature reactor for generation of electric current, designed for a capacity of 1-5 MWe. The plant, which in addition to the high temperature reactor includes a gas turbine assembly and a heat exchange apparatus, is housed in two pressure vessels located above each other and connected in a releasable manner. The lower pressure vessel contains the high temperature reactor and is charged with the primary gas. The other circulation components are located in the upper pressure vessel which is filled with a protective gas. The gas turbine, the radiators, the high temperature compressor, the intermediate radiators, and the low pressure compressor, are arranged above each other in this sequence and aligned with the high temperature reactor. the recuperator is laterally arranged. A generator may also be located in the upper pressure vessel or in a container set upon the upper pressure vessel.

Abstract: A nuclear reactor plant housed in a steel pressure vessel with a small high temperature reactor, together with a steam generator arranged over said reactor and with at least two circulating blowers connected in parallel with each other and following the steam generator in line and is provided with a decay heat removal system located in the primary loop. This system is arranged above the steam generator and a shut-off device is provided between the two component. The shut-off device, which may actuated both passively--by difference pressure--and actively, by means of a drive, is designed so that in normal operation no hot gas may enter the decay heat removal system. In the decay heat removal mode the hot gas is conducted into the decay heat removal system and the steam generator is closed off the hot gas. Simultaneously, the cold gas coming from the decay heat removal system is returned through the steam generator or a gas conduit parallel to it, to the reactor core.

Abstract: A nuclear reactor plant housed in a steel pressure vessel comprises a small high temperature reactor and a He/He heat exchanger located above the reactor, preferably followed by two circulating blowers connected in parallel. The installation further comprises at least one decay heat removal system, following in line the He/He heat exchanger in the direction of flow and with the entire flow of primary helium constantly flowing through it. In a preferred embodiment, the He/He heat exchanger is made up of two concentrically arranged coil bundles connected in succession, through which both the primary and the secondary helium are flowing in opposing directions.

Abstract: A unit for guiding the flow of cold gas from the annular chamber that is disposed between the pressure tank wall and the steam generator wall to the circulation fan of a steam generator of a high-temperature reactor, with hot gas being adapted to be supplied to the steam generator wall via a hot gas guide mechanism. The cold gas flows into a riser through a plurality of cold gas channels that pass through the upper end of compensating tube bundles that are associated with the steam generator wall. From the riser, the cold gas is supplied to the circulation fan, with the riser being disposed in that portion of the hot gas guide mechanism that extends parallel to the central axis of the pressure tank.

Abstract: A heat exchanger for heat exchange between a hot gas and a flowing medium that is conveyed in tube bundle heat transfer surfaces, especially a steam generator. The heat exchanger includes a pressure tank, the heat exchanger vessel in which are disposed tube bundles, and a hot gas conduit that is connected with a gas inlet of the heat exchanger wall. Also included are a gas guidance tube, a gas outlet to a circulation fan, and inlets and outlets for the flowing medium. The gas guiding tube opens into the heat exchanger from the side, and an annular channel is disposed after the gas inlet in the heat exchanger wall. The annular channel is delimited inwardly by a riser that forms the gas outlet and is disposed concentrically relative to the walls of the pressure tank and the heat exchanger. The gas from this annular chamber enters the tube bundles and, after being deflected, enters the riser that leads to the circulation fan.

Abstract: The invention concerns a steam generator heated by the cooling gas of a nuclear reactor and arranged in the reactor pressure vessel within a vertical shaft. A blower associated with the steam generator is installed above it. The hot gas is conducted to the steam generator in the form of a helical bundle in the downward direction, with the hot gas being conducted initially downward through an annular channel and entering the bundle of heat exchanger tubes at a uniform velocity. The annular channel is sealed in upward direction by means of a sliding seal, which also serves as an earthquake support. In order to provide access to the feed water and live steam lines in view of the blower arranged on top, the two lines are conducted laterally out of and through the reactor pressure vessel. By means of the special fixation of the individual tubes of the heat exchanger bundle in vertical plates and the presence of an expansion zone for the recycling pipes, differential thermal expansion may be kept small.

Abstract: A nuclear reactor plant with a small high temperature reactor, principal heat exchangers located above the small high temperature reactor and housed in a steel pressure vessel, and a plurality of decay heat exchangers also located in the steel pressure vessel and connected on the cooling water side with an external recooling heat exchanger each, in a geodetically higher location. The object of the invention is to obtain a high degree of availability of the decay heat removal installations. This object is attained by the specific layout and connection of the components of the plant, which permits the operation of the decay heat exchangers both on the primary gas and the water side by natural convection only. The decay heat exchangers and their secondary circulation loops are active during power operations, so that potential failures and leaks are detected immediately. No special actuating measures are necessary to activate the decay heat removal operation.

Abstract: An improved gas circulator for a gas-cooled nuclear reactor system is disclosed which includes a stator, a rotor having a rotor shaft, and an impeller attached to one end thereof. A radial active magnetic bearing and a radial backup bearing are positioned proximate each end of the rotor shaft. An axial active magnetic bearing is also located between the ends of the rotor shaft, as is an axial backup bearing, with two of the backup bearings enclosed within a sealed chamber that may contain a lubricant, for example, a solid lubricant or a liquid lubricant. Preferably, the gas circulator is installed in a nuclear reactor system with the rotor shaft in a substantially vertical orientation and the sealed chamber near the bottom of the rotor shaft. The lower radical backup bearing and the axial backup bearing are advantageously located within the sealed chamber.

Abstract: Disclosed is a nuclear power plant comprising a high-temperature pebble bed reactor contained in a cylindrical steel pressure vessel in which an upper part of the cylindrical steel pressure vessel, which contains a heat utilization system, is retracted and equipped with a cover upon which circulating blowers are placed. The heat utilization system comprises, in a known manner, a single steam generator. The steam generator comprises at least two sub-systems independent of one another, with their own distributors and collectors, and with their own inlet and outlet lines. A first shut-down arrangement comprises a plurality of absorber rods insertable into bores of the side reflector from above and comprises rod drives arranged outside the steel pressure vessel in the area of its retracted upper part. A second shut-down arrangement comprises small absorber spheres for introducing into the core of the reactor, and several storage containers and annular conduits for said spheres.

Abstract: A system for increasing the temperature of a fluid heated by a high temperature gas cooled nuclear reactor to a sufficient temperature to supply the heat of reaction for a high temperature chemical process. The system includes a secondary loop having a working fluid heated to a first temperature by the nuclear reactor, and has a heat pump connected in the secondary loop and adapted to increase and thereby augment the temperature of the working fluid in the secondary loop sufficiently to supply the heat of reaction for a high temperature chemical process such as in a reformer. The system also provides low temperature heat in the form of steam which may be used in a turbine to provide power to the compressor of the heat pump and for auxilliary apparatus.

Abstract: Device for the post-accident cooling of the confinement enclosure of a pressurized water nuclear reactor, wherein it comprises in series a turbine supplied by the hot, humid air contained in the enclosure, a condenser in which the air from the turbine is dried and cooled by thermal contact with an external cooling fluid, and a compressor actuated by the turbine, and which returns the dried air into the enclosure.

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 system for producing process heat which employs a high temperature gas cooled nuclear reactor and is adapted to provide process heat at temperatures higher than the reactor core temperature. The system includes a closed secondary loop having a working fluid heated to a first temperature by the coolant of the reactor core in an intermediate heat exchanger, and has a heat pump connected in the secondary loop which increases the temperature of the working fluid to a temperature above the core coolant temperature. Steam in an independent closed nuclear steam supply circuit is heated directly by the core coolant in a steam generator and provides steam for make-up driving power to the heat pump in the secondary loop. The steam supply circuit also supplies additional steam to generate electric power and process steam. The size of the intermediate heat exchanger is minimized to enable maximum utilization of the steam supply circuit.

Abstract: Cooling system for auxiliary systems of a nuclear installation for heat removal from heat exchangers, the heat exchangers being connected on the primary side thereof to lines which may contain radioactive liquids or gases, being disposed in a secured area of the nuclear installation, and having connections on the secondary side thereof for cooling liquid lines, including an outgoing line for the cooling liquid connected to the connections on the secondary side of the heat exchangers, a dry cooling tower having cooling elements connected to the outgoing line, a return line for the cooling liquid connected to the cooling elements, a refrigeration loop having a supplemental heat exchanger with the primary side thereof connected in the return line, a bypass line connected from the outgoing to the return line parallel to the cooling elements and supplemental heat exchanger, and a control valve connected in the bypass line.

Abstract: A nuclear divisional reactor including a reactor core having side and top walls, a heat exchanger substantially surrounding the core, the heat exchanger including a plurality of separate fluid holding and circulating chambers each in contact with a portion of the core, control rod means associated with the core and external of the heat exchanger including control rods and means for moving said control rods, each of the chambers having separate means for delivering and removing fluid therefrom, separate means associated with each of the delivering and removing means for producing useable energy external of the chambers, each of the means for producing useable energy having separate variable capacity energy outputs thereby making available a plurality of individual sources of useable energy of varying degrees.

Abstract: A core energy plant with closed working gas circuit, in which within an or safety container there are arranged a reactor core of pre-stressed concrete for heating the working gas, a working gas driven turbo-set with generator, and other components of the working gas circuit such as heat exchanger and gas storage means. The reactor core is separated from the turbo-set and other components and is arranged in a separate reactor chamber with walls of pre-stressed concrete, while the other components are respectively arranged in separate chambers, within an inner concrete container which has chambers for receiving the turbo-set with generator and the remaining components of the working gas circuit and which has its outer wall arranged adjacent the vertical inner wall of the outer safety container there is provided a recess for a pre-stressed concrete container for receiving the reactor core.

Abstract: The cavity within a pressure vessel for a gas-cooled nuclear reactor is divided into chambers by an intermediate support floor, with the reactor core thereabove and heat-exchangers therebelow. Separate heat-exchange units are connected to separate circulators which discharge the repressurized primary gas coolant through an annular passageway along the inner surface of the pressure vessel cavity. The heat extraction system includes a separate secondary gas coolant circuit connected to each heat-exchange unit, which coolant may be heated to about 850.degree. C. at which it is suitable to provide process heat. Emergency cooling is effected by a heat dump which is connected into each secondary circuit to promptly provide low-temperature secondary gaseous coolant which then indirectly removes the reactor core heat.

Abstract: The invention is directed to a nuclear reactor plant having a primary medium circuit including a nuclear reactor for generating a flow of heated primary working medium and a heat exchanger having a primary side to receive the flow of heated primary working medium. In accordance with the invention, a compressor is connected to the secondary side of the heat exchanger to receive a flow of secondary working medium therefrom which has been heated in heat exchange relation by the primary working medium for compression to a given temperature. By exchanging the heat at a lower temperature and subsequently pumping up the exchanged heat, a thermally highly stressed heat exchanger is replaced by a thermally highly stressed compressor.