Abstract: A power conversion system for converting thermal energy from a heat source to electricity is provided. The system includes a chamber including an inner shroud having an inlet and an outlet and defining an internal passageway between the inlet and the outlet through which a working fluid passes. The chamber also includes an outer shroud substantially surrounding the inner shroud. The chamber includes a source heat exchanger disposed in the internal passageway, the source heat exchanger being configured to receive a heat transmitting element associated with the heat source external to the chamber, and to transfer heat energy from the heat transmitting element to the working fluid. The system also includes a compressor disposed adjacent the inlet of the inner shroud and configured to transfer energy from the compressor to the working fluid, and an expander disposed adjacent the outlet of the inner shroud.

Abstract: Power conversion systems for converting thermal energy from a heat source to electricity are disclosed. In one exemplary embodiment, the power conversion system may include a substantially sealed chamber having an inner shroud having an inlet and an outlet and defining an internal passageway between the inlet and the outlet through which a working fluid passes. The sealed chamber may also include an outer shroud substantially surrounding the inner shroud, such that the working fluid exiting the outlet of the inner shroud returns to the inlet of the inner shroud in a closed-loop via a return passageway formed between an external surface of the inner shroud and an internal surface of the outer shroud. The power conversion system may further include a source heat exchanger disposed in the internal passageway of the inner shroud, the source heat exchanger being configured to at least partially receive a heat transmitting element.

Abstract: An energy regeneration device which can regenerate energy of a working fluid discharged from an actuator while controlling a flow rate of the working fluid, and a work machine including the device. The regeneration device includes a boom cylinder, an inertial fluid container, an oil tank, an accumulator, a low-pressure-side opening/closing device, and a high-pressure-side opening/closing device. A calculation unit calculates an opening area of each of the low-pressure-side opening/closing device and the high-pressure-side opening/closing device in accordance with a desired flow rate of a hydraulic fluid discharged from the boom cylinder.

Abstract: An energy-saving gas supply boiler system, comprising: a steam boiler, a flue gas pipeline, a heat exchanger, a steam generator and an ejector. The steam boiler comprises a body, a combusting apparatus, a flue gas outlet, a water outlet and a high pressure steam outlet. The heat exchanger comprises a high temperature flue gas inlet, a medium temperature flue gas outlet, a cooling water inlet and a hot water outlet. Cooling water undergoes heat exchange with flue gas and flows out from the hot water outlet. The steam generator comprises a generator body, a hot water inlet and a low pressure steam outlet. The ejector comprises a high pressure steam inlet, a mixing steam outlet and a low pressure steam inlet. The high pressure steam inlet delivers high pressure steam to the ejector. The low pressure steam inlet delivers low pressure steam to the ejector.

Abstract: Provided is an apparatus for generating electricity, mechanical energy, and/or process and district heat using a gas propellant chamber fueled with fissile material and enclosed in a sealed containment vessel which also contains an operating gas. The system allows for the operating gas to be compressed as it enters the nuclear fuel chamber where it is heated. As the operating gas exits the nuclear fuel chamber, the kinetic energy of the gas is converted to rotational energy by a variety of methods. The rotational energy is further converted to electricity, mechanical energy, and/or process and district heat. The operating gas circulates in the containment vessel and is cooled prior to re-entering the gas propellant chamber. The apparatus thereby provides a simpler and safer design that is both scalable and adaptable. The apparatus is easily and safely transportable and can be designed to be highly nuclear-proliferation-resistant.

Abstract: Provided is an apparatus for generating electricity, mechanical energy, and/or process and district heat using a gas propellant chamber fueled with fissile material and enclosed in a sealed containment vessel which also contains an operating gas. The system allows for the operating gas to be compressed as it enters the nuclear fuel chamber where it is heated. As the operating gas exits the nuclear fuel chamber, the kinetic energy of the gas is converted to rotational energy by a variety of methods. The rotational energy is further converted to electricity, mechanical energy, and/or process and district heat. The operating gas circulates in the containment vessel and is cooled prior to re-entering the gas propellant chamber. The apparatus thereby provides a simpler and safer design that is both scalable and adaptable. The apparatus is easily and safely transportable and can be designed to be highly nuclear-proliferation-resistant.

Abstract: Provided is an apparatus for generating electricity, mechanical energy, and/or process and district heat using a gas propellant chamber fueled with fissile material and enclosed in a sealed containment vessel which also contains an operating gas. The system allows for the operating gas to be compressed as it enters the nuclear fuel chamber where it is heated. As the operating gas exits the nuclear fuel chamber, the kinetic energy of the gas is converted to rotational energy by a variety of methods. The rotational energy is further converted to electricity, mechanical energy, and/or process and district heat. The operating gas circulates in the containment vessel and is cooled prior to re-entering the gas propellant chamber. The apparatus thereby provides a simpler and safer design that is both scalable and adaptable. The apparatus is easily and safely transportable and can be designed to be highly nuclear-proliferation-resistant.

Abstract: Provided is an apparatus for generating electricity, mechanical energy, and/or process and district heat using a gas propellant chamber fueled with fissile material and enclosed in a sealed containment vessel which also contains an operating gas. The system allows for the operating gas to be compressed as it enters the nuclear fuel chamber where it is heated. As the operating gas exits the nuclear fuel chamber, the kinetic energy of the gas is converted to rotational energy by a variety of methods. The rotational energy is further converted to electricity, mechanical energy, and/or process and district heat. The operating gas circulates in the containment vessel and is cooled prior to re-entering the gas propellant chamber. The apparatus thereby provides a simpler and safer design that is both scalable and adaptable. The apparatus is easily and safely transportable and can be designed to be highly nuclear-proliferation-resistant.

Abstract: Open-loop thermal management systems and open-loop thermal management processes are disclosed. The process includes providing an open-loop thermal management system, saturating a reactor of the system with gas while a flow control unit prevents flow of the gas from the reactor, and maintaining a gas dissociation pressure range of the gas within the reactor. The system includes the reactor being arranged to receive a heat load. The reactor contains metal hydrides, metal organic framework, or a combination thereof. The reactor includes at least one venting line extending from the reactor. Also, the flow control unit is configured to adjustably control the flow of gas from the reactor to maintain the gas dissociation pressure range.

Abstract: An offshore, floating, moored, nuclear power generating and multi-purpose platform is disclosed. In a preferred embodiment, the invention is a spar platform with multi-purpose, topside decks, attached to a submerged dry tank that further includes: reactor generator deck(s), power plant main control deck, and central plant deck, that are all integrated within a watertight ballast hull. The invention further includes cells that are modular for facilitating factory assembly and ultimate construction in a shipyard environment. Reactor vessels are typical naval nuclear reactor having a time tested outstanding safety record. A plurality of reactor generator modules operate independently and collectively. Multipurpose topside decks house vessel command, crew, and any ancillary and co-generation equipment. The present invention, constructed in a multi-path manufacturing process, provides exceptional economic, environmental, sustainability, security, safety, and operational benefits to users.

Abstract: A method for buffering the voltage of an electric system that undergoes transient voltage changes includes the step of placing a new load upon the electric system by electrically connecting at least one electrochemical device to the electric system so that electrical current flows from the electric system to the electrochemical device. Also included are the steps of causing at least one electrochemical reaction to occur within the at least one electrochemical device; varying the new load placed upon the electric system as transient voltage changes in the electric system occur; and changing the electrical current from the electric system to the electrochemical device in a manner that retards transient voltage changes in the electric system that would occur in the absence of the steps of placing, causing, and varying.

Abstract: Provided is a small nuclear power generator which restores steam to water by applying pressure to the inside of a condenser using a pressurizer disposed over the condenser without condensing steam using cooling water. The small nuclear power generator includes: a nuclear reactor generating high-temperature heat by nuclear fission of a nuclear fuel; a steam generator converting internal water into steam by the high-temperature heat generated in the nuclear reactor; a turbine/generator including a steam turbine rotated by steam generated in the steam generator and a generator connected to an axis of the steam turbine and together rotating to produce electricity; and a condenser restoring steam to water by applying pressure to steam discharged after rotating the steam turbine using two or more pressurizers, again supplying the water into the steam generator, and formed of a titanium (Ti) or an alloy thereof.

Abstract: A vehicular battery system includes an oxygen reservoir having a first outlet and a first inlet, a multistage compressor supported by the vehicle and having a second inlet and a second outlet, the second outlet operably connected to the first inlet, a cooling system operably connected to the multistage compressor and configured to provide a coolant to the multistage compressor to cool a compressed fluid within the multistage compressor, and a vehicular battery system stack including at least one negative electrode including a form of lithium, the vehicular battery system stack having a third inlet removably operably connected to the first outlet, and a third outlet operably connected to the second inlet.

Abstract: A vehicular battery system includes a vehicular battery system stack including at least one negative electrode including a form of lithium, an oxygen reservoir having a first outlet operably connected to the vehicular battery system stack, a multistage compressor having a first inlet operably connected to the vehicular battery system stack, and a second outlet operably connected to a second inlet of the oxygen reservoir, and a cooling system operably connected to the multistage compressor and configured to provide a coolant to the multistage compressor to cool a compressed fluid within the multistage compressor.

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: Methods for producing a radioisotope by a charged particle irradiation of a fluid target matrix are provided. A method of producing a radioisotope includes irradiating a fluid target matrix comprising a compound of a target isotope with a charged particle beam to transform at least a portion of the target isotope to the radioisotope, and isolating the radioisotope from the irradiated fluid target matrix. The target isotope may be an isotope of cadmium, an isotope of thallium, an isotope of zinc, an isotope of gallium, an isotope of tellurium, an isotope of molybdenum, an isotope of rhodium, an isotope of selenium, an isotope of nickel, an isotope of yttrium, an isotope of strontium, an isotope of bismuth, an isotope of tungsten, and an isotope of titanium, provided that the target isotope is not Mo-100.

Abstract: A method and apparatus for conditioning water is disclosed. Water is flowed past a probe, wherein the water may include impurities. The probe is energized to excite the water and a presence of electrons in the excited water is reduced to produce positively charged water downstream of the probe that causes the impurities to dissociate from the water. The excited water may be deposited on a soil for crop production. The excited water may be further deposited on the soil to flush impurities in the soil to a depth away from a root of a crop planted in the soil to reclaim the soil for crop production. The excited water may further be used to descale pipes, such as used in irrigation, heat exchangers, cooling systems, etc. In yet another embodiment, the probe may be energized at a frequency selected to destroy organism, thereby protecting ecosystems.

Abstract: Nuclear reactor systems and methods are described having many unique features tailored to address the special conditions and needs of emerging markets. The fast neutron spectrum nuclear reactor system may include a reactor having a reactor tank. A reactor core may be located within the reactor tank. The reactor core may include a fuel column of metal or cermet fuel using liquid sodium as a heat transfer medium. A pump may circulate the liquid sodium through a heat exchanger. The system may include a balance of plant with no nuclear safety function. The reactor may be modular, and may produce approximately 100 MWe.

Abstract: Disclosed is an offshore, manned, scalable, modular, floating, moored, nuclear power generating plant and multipurpose platform. The present invention is comprised of a Main Plant Control Deck, Central Plant Deck, and submerged Reactor-Generator Deck(s) integrated into the structure of a Spar or Cell Spar Platform. The Reactor-Generator decks are comprised of a plurality of modular, Naval Nuclear Pressurized Water Reactor Modules. Electricity generated is transmitted via submarine High Voltage Direct Current Cables to shore. Ancillary, co-generated services, e.g. desalinated water, are transmitted to shore via submarine pipelines. Multipurpose Topside Decks house vessel command, crew, and any ancillary and co-generation equipment. The present invention, constructed in a multi-path manufacturing process, provides exceptional economic, environmental, sustainability, security, safety, and operational advantages over the current art of power generation.

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: 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: Method and devices for development of nuclear particle detectors, meant to operate in wide temperature range, with and without cooling that can be integrated in various arrays, able to identify radiation type and provide information on it's parameters as position, mass, energy, direction. The device will operate by enhancing the radiation detection by using materials that generates fission, transmutation and/or directly converting the energy of radiation into photonic or pressure waves, or into electricity, device acting on a plurality of conductor insulator junction making it able to identify radiation type, spectrum, direction and position usable for a large range of electronics from detectors to complex imagers. The method relies on an assembly of three components with generic function as generator, insulator and absorber, in different aggregation states, dimensioned by calculating the effective length for the specific moving entity i.e.

Abstract: The invention describes a product and a method for generating electrical power directly from nuclear power. More particularly, the invention describes the use of a liquid semiconductor as a means for efficiently converting nuclear energy, either nuclear fission and/or radiation energy, directly into electrical energy. Direct conversion of nuclear energy to electrical energy is achieved by placing nuclear material in close proximity to a liquid semiconductor. Nuclear energy emitted from the nuclear material, in the form of fission fragments or radiation, enters the liquid semiconductor and creates electron-hole pairs. By using an appropriate electrical circuit an electrical load is applied and electrical energy generated as a result of the creation of the electron-hole pairs.

Abstract: The invention describes a product and a method for generating electrical power directly from nuclear power. More particularly, the invention describes the use of a liquid semiconductor as a means for efficiently converting nuclear energy, either nuclear fission and/or radiation energy, directly into electrical energy. Direct conversion of nuclear energy to electrical energy is achieved by placing nuclear material in close proximity to a liquid semiconductor. Nuclear energy emitted from the nuclear material, in the form of fission fragments or radiation, enters the liquid semiconductor and creates electron-hole pairs. By using an appropriate electrical circuit an electrical load is applied and electrical energy generated as a result of the creation of the electron-hole pairs.

Abstract: Methods and apparatuses are provided for the removal and transportation of thermal energy from a heat source to a distant complex for use in thermochemical cycles or other processes. In one embodiment, an apparatus includes a hybrid heat pipes/thermosyphon intermediate heat exchanger (HPTIHX) system that is divided into three distinct sections, namely: an evaporation chamber, a condensation chamber, and a working fluid transport section of liquid and vapor counter-current flows.

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 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: A high temperature superconductor (HTS) transmission line for transporting electricity includes a plurality of HTS wires coupled to receive and transport electricity. A cooling system is thermally coupled to the plurality of HTS wires and includes a plurality of joint coaxial cooling arrangements each including a thermoelectric (TE) cooler radially outside a inner liquid nitrogen (LN2) cooler. The TE coolers are powered by electricity flowing along the plurality of HTS wires. The TE cooler cools the outer portion of the joint coaxial cooling arrangement to an intermediate temperature that is above a target controlled temperature, and the LN2 cooler cools from the intermediate temperature to a temperature at or below the target controlled temperature. A system for generating and transporting nuclear power includes a nuclear power plant including a turbine for generating electricity, and a HTS transmission line cooled by a plurality of joint coaxial cooling arrangements for transporting the electricity.

Abstract: The Seafloor Power Station is one or more unmanned electric power generating Units (2) sending power to and operated from existing coastal sites by a manned facility (1) by connecting lines and hoses (3) delivering power to a grid by lines (4). Each Unit's hull (11) maintained in a vacuum, contains both nuclear steam and electricity generating systems. The hull functions as overpressure containment and as condenser in the event of a loss of coolant accident or other steam release. The Units operate submerged in very cold water, with depth set by remotely controlled vertical mooring systems, mounted on gravity mats (27). A Unit must be surfaced by its mooring system to refuel the reactor, an action both conspicuous and public, enabling international oversight of the fuel disposition.

Abstract: Disclosed is an offshore fixed, moored, or mobile energy carrier production plant. The plant's energy source for the energy intensive processes of producing an energy carrier is nuclear in nature and the resulting energy carriers of the plant range from hydrogen to hydrocarbons such as methanol and jet fuel. The offshore energy carrier production plant will be able to produce energy carriers at a reduced cost, increased sustainability and scalability, increased safety, and with fewer environmental and social impacts than heretofore possible. The resulting energy carrier products can then be transported by marine vessels, pipelines, and other transportation means or any combination of transportation means thereof to be distributed to end use energy carrier consuming devices and products such as fuel cell applications in a variety of industries as well as internal combustion engines.

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: A fullerene molecule having one or more free thermal neutrons trapped within the fullerene molecule and a method for trapping and storing neutrons within a fullerene molecule are described.

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: Problem-Solution The prior art propelling motor vehicles uses the internal combustion engine blamed for the damage to the environment and global warming. The solution lies in my invention which replaces the internal combustion engine but still using hydrogen as choice fuel and all fossil fuels. The technological invention is called CONDECAST EV-2 named after me, an inertial guided thermonuclear magnetic perfumagnetron fusion reactor. Hydrogen with an energy content of 2 gallon is equal to 2600 gallons and fossils are fed in the form of vapor fumes and burned in the reactor simulating lightning arc and thunder in the skies. Using hydrogen you get 26,000 miles per gallon. For fossils—300 to 500 miles per gallon, depending on how fast you drive.

Abstract: In the method, a set of limits applicable to a test rod pattern design are defined, and a sequence strategy for positioning one or more subsets of the test rod pattern design is established. Reactor operation on a subset of the test rod pattern design, which may be a subset of fuel bundles in a reactor core for example, is simulated to produce a plurality of simulated results. The simulated results are compared against the limits, and data from the comparison is provided to indicate whether any of the limits were violated by the test rod pattern design during the simulation. A designer or engineer may use the data to determine which operator parameters need to be adjusted (e.g., control blade notch positions for example) in order to create a derivative rod pattern design for simulation, and eventually perfect a rod pattern design for a particular core.

Abstract: The Seafloor Power Station is one or more unmanned electric power generating Units (2) sending power to and operated from existing coastal sites by a manned facility (1) by connecting lines and hoses (3) delivering power to a grid by lines (4). Each Unit's hull (11) maintained in a vacuum, contains both nuclear steam and electricity generating systems. The hull functions as overpressure containment and as condenser in the event of a loss of coolant accident or other steam release. The Units operate submerged in very cold water, with depth set by remotely controlled vertical mooring systems, mounted on gravity mats (27). A Unit must be surfaced by its mooring system to refuel the reactor, an action both conspicuous and public, enabling international oversight of the fuel disposition.

Abstract: A team turbine control device. A main steam system runs between a nuclear reactor and a steam turbine and includes a main stream isolation valve (MSIV), a main steam control valve, and a turbine by-pass system with a turbine by-pass valve. A calculating means generates a main steam pressure control signal and a reactor dome pressure control signals. A pressure control single changeover means changes a pressure control signal from the reactor dome pressure signal to the main steam pressure signal when the MSIV closes to restrain the abrupt decrease of stream in the main steam system effectively.

Abstract: Described are a process and an apparatus for the remote measurement of uranium or plutonium in radioactive materials. in which the sample of the material to be analyzed is to be handled as little as possible. To attain that object it is proposed that the laser beam of a laser is focussed by means of a focussing unit onto the sample to be analyzed, so that a light-emitting plasma is generated, an image of the emission spectrum of the plasma is formed in a spectrograph by means of an imaging unit, and finally it is analyzed by means of an analyzing unit.

Abstract: A device for generating direct current by neutron activation of a plurality of series-connected beta-emitter (nuclear decay electron) cells, located in the out-of-core region of a light water nuclear reactor. The device can be used as either a current source, or preferably configured as a DC voltage source, capable of powering low-power, radiation-hardened, high-temperature integrated circuitry contained in the reactor vessel. As such, the device acts like a DC battery that is activated by (n, .gamma.) reactions, both thermal and epithermal (by resonance capture). The device is not operable until exposed to a substantial neutron flux, so it has unlimited shelf-life and is not radioactive during manufacture In the preferred embodiment, an isotope of the metallic rare-earth element dysprosium is configured in a "sandwich" geometry to generate sufficient current that a useful steady voltage can be generated by means of a simple voltage regulation circuit.

Abstract: A stand-alone low-voltage direct current power supply, for use as a battery, which is energized by the decay of a radioactive isotope in response to neutron capture. During this decay, either .alpha.- or .beta.-particles are emitted. The emitting radioactive isotope should have adequate half-life and no .gamma.-emission. The preferred .beta.-emitting radioisotope is thallium, which decays directly to the ground state of Pb.sup.204 by 763-keV .beta.-decay with no .gamma.-emission. The resulting .beta.-particles are collected to form a current which can be used for various purposes inside a reactor. The preferred .alpha.-emitting radioisotope is americium.

Abstract: A method and apparatus for improving the efficiency and performance of a nuclear electrical generation system that comprises the addition of steam handling equipment to an existing plant that results in a surprising increase in plant performance. More particularly, a gas turbine electrical generation system with heat recovery boiler is installed along with a micro-jet high pressure and a low pressure mixer superheater. Depending upon plant characteristics, the existing moisture separator reheater (MSR) can be either augmented or done away with. The instant invention enables a reduction in T.sub.hot without a derating of the reactor unit, and improves efficiency of the plant's electrical conversion cycle. Coupled with this advantage is a possible extension of the plant's fuel cycle length due to an increased electrical conversion efficiency. The reduction in T.sub.hot further allows for a surprising extension of steam generator life.

Abstract: The lower tie plate grid includes cylindrical bosses and webs interconnecting the bosses for supporting nuclear fuel rods and defining flow openings through the grid. Coolant flows through the flow openings for flow upwardly about the fuel rods. The grid includes upper and lower portions and a screen is disposed between the upper and lower grid portions upon assembly with the bosses and webs of the respective upper and lower grid portions in registry with one another. The grid portions are welded to one another whereby the apertured screen serves to separate debris from the coolant flowing through the flow openings. The screen has openings in registry with the openings defined by the bosses for receiving the end plugs of the fuel rods.

Abstract: Provided herein is a process for producing methanol which was developed to reduce the emission of carbon dioxide which is responsible for global warming. The process involves the steps of generating steam by the use of nuclear heat of a high-temperature gas-cooled nuclear reactor, decomposing the steam into hydrogen by means of a steam electrolyzer, and synthesizing methanol from this hydrogen and carbon dioxide obtained from a carbon dioxide source. The process also involves the steps of converting carbon dioxide and hydrogen into carbon monoxide and steam by means of a reverse shift reactor, forming hydrogen and carbon monoxide of almost the same composition as the conventional one, and reacting said hydrogen and carbon monoxide into methanol by means of a methanol synthesis column. The process permits the use of an existing methanol production facility.

Abstract: A method and apparatus for improving the efficiency and performance a of nuclear electrical generation system that comprises the addition of steam handling equipment to an existing plant that results in a surprising increase in plant performance. More particularly, a gas turbine electrical generation system with heat recovery boiler is installed along with a high pressure and a low pressure mixer superheater. Depending upon plant characteristics, the existing moisture separator reheater (MSR) can be either augmented or done away with. The instant invention enables a reduction in T.sub.hot without a derating of the reactor unit, and improves efficiency of the plant's electrical conversion cycle. Coupled with this advantage is a possible extension of the plant's fuel cycle length due to an increased electrical conversion efficiency. The reduction in T.sub.hot further allows for a surprising extension of steam generator life.

Abstract: In order to reduce any loss of primary water coolant from around a reactor core of a water cooled nuclear reactor caused by any failure of a pressure vessel, an inner vessel is positioned within and spaced from the pressure vessel. The reactor core and main portion of the primary water coolant circuit and a heat exchanger are positioned within the inner vessel to maintain some primary water coolant around the reactorcore and to allow residual decay heat to be removed from the reactor core by the heat exchanger. In a second embodiment an aperture at the upper region of the inner vessel is dimensioned configured and arranged to prevent steam from a steam space of an integral pressurized water cooled nuclear reactor for a ship entering the main portion of the primary water coolant circuit in the inner vessel if the longitudinal axis of the nuclear reactor is displaced from its normal substantially vertical position to an abnormal position at an angle to the vertical direction.

Abstract: A method of providing a nuclear steam supply system that is constructed to include a barge or flotation base as an integrated portion thereof. The system is tested for operability and safety at the factory and then towed along navigable coastal or inland waterways, or overseas to foreign locations, to a prepared foundation site at its point of use. The overall unit is so constructed and arranged as to permit the removal of top and side portions to permit passage under low bridges and through narrow locks without requiring disassembly of safety class piping and wiring. The method further provides for a complete nuclear power plant constructed on multiple barges at a separate factory site in parallel with plant site preparation, i.e., in estuaries or caves.

Abstract: A heat radiator useful for expelling waste heat from a power generating system aboard a space vehicle is disclosed. Liquid to be cooled is passed to the interior of a rotating bubble membrane radiator, where it is sprayed into the interior of the bubble. Liquid impacting upon the interior surface of the bubble is cooled and the heat radiated from the outer surface of the membrane. Cooled liquid is collected by the action of centrifical force about the equator of the rotating membrane and returned to the power system. Details regarding a complete space power system employing the radiator are given.

Abstract: A pressurized water nuclear reactor has a reactor vessel arranged in a pool, which is filled with a neutron absorbing liquid, for example borated water. The reactor vessel is closed except for tubes connecting it with a tray above it. The coolant in the circuit rises from the vessel to the tray, gives up its heat by flashing, and flows back to the bottom of the vessel, driven by natural circulation. The tray is separated from the pool by a vapor-filled bell, which surrounds it. In the bell the vapor gives up its useful heat to a condenser. The relatively low boron content of the cooling circuit, compared to the pool, is achieved by continuous dilution of the condensate from vapor additionally generated out of the pool water. The dilution process is an equilibrium with continuous inflow of the pool water. The inflow is automatically controlled by the pool level, which rises when the pool water is pressed out from below the bell by overproduction of vapor.

Abstract: A nuclear power plant (heating plant) with a helium cooled high temperature reactor with spherical fuel elements, located in a cylindrical prestressed concrete pressure vessel, suitable for supplying heat (for local or remote heating or the generation of process steam) with a capacity of approximately 50 to 300 MWth. The high temperature reactor core is located out of center in the prestressed concrete pressure vessel, with at least two heat exchangers installed adjacent and offset in the upward direction relative to it. The heat exchangers are each connected on the secondary side to an intermediate circulation loop including an intermediate heat exchanger and circulating pump, and have an auxiliary circulation loop with a recooling system connected in parallel with them for the removal of decay heat. The auxiliary loops are closed in normal operation.

Abstract: This invention relates to a control system for heat supply as hot water from nuclear power plants equipped with condensation units. This leads to the increased efficiency of the nuclear power plant on the basis of heat extraction from the turbine and its utilization for district heating with hot water as agent. The system requires a turbine nonadjustable bleeding through which a steam flow is extracted. A flow nozzle for steam flow measurement is provided on the steam transport line, a pressure transducer which sends a signal to a comparing and control unit which receives also a signal from another pressure transducer located on the turbine first stage. The comparing and control unit actuates the motorized steam and condensate valves, performing the turbine protection in case that the steam flow extracted at the nonadjustable bleeding exceeds the allowed limit.