Abstract: A power generation system and related method for repowering a fossil-fueled power plant using a carbon-free nuclear steam supply system (NSSS) which replaces the existing fossil plant steam generator which burns fossil fuel such as coal, oil, or natural gas. The existing fossil plant energy conversion system including the turbine-generator (turbogenerator) and auxiliary components of the Rankine cycle is retained. The NSSS may include a small modular reactor (SMR) unit comprising a reactor vessel with nuclear fuel core and steam generator which receives heated primary coolant from the reactor to produce main steam to operate the Rankine cycle. The main steam output by the SMR unit is compressed in a steam compressor to increase its pressure to a level necessary to operate the turbogenerator. The compressor may be operated via a portion of the main steam. An intercooler of the compressor may be used for main steam reheating.

Abstract: A system comprising a sensor device to perform measurements in a wellbore. The system may also include a wireless transmitter to transmit a signal representing the measurements to a wired transmission system. The wired transmission system may transmit the signal to an interrogation system. A radioisotope power source may provide electrical power to the sensor system in the wellbore.

Abstract: A mobile heat pipe cooled fast nuclear reactor may be configured for transportation to remote locations and may be able to provide 0.5 to 2 megawatts of power. The mobile heat pipe cooled fast reactor may contain a plurality of heat pipes that are proximate to a plurality of fuel pins inside the reactor. The plurality of heat pipes may extend out of the reactor. The reactor may be configured to be placed in a standard shipping container, and may further be configured to be contained within a cask and attached to a skid for easier transportation.

Abstract: Systems and methods for rendering cannabis-related waste materials are provided. The method includes obtaining a plurality of cannabis-related waste materials, preparing a blend comprising a predetermined amount of each of the plurality of cannabis-related waste materials, pulverizing the blend such that the blend is unrecognizable and unusable, heating the blend to at least 150 degrees Fahrenheit for an amount of time sufficient to sterilize and denature the blend, removing evaporated liquid from the heated blend, and cooling the heated blend to form a refuse-derived fuel material.

Abstract: Various embodiments of the invention include systems for controlling cold-reheat extraction in a turbomachine system. Some embodiments include a system having: a high-pressure (HP) turbine section including an exhaust; a reheater conduit fluidly connected with the exhaust of the HP turbine and a reheater, the reheater conduit for passing HP exhaust steam from the HP turbine section to the reheater; a cold-reheat extraction conduit fluidly connected with the reheater conduit upstream of the reheater and downstream of the HP turbine section exhaust; and a control system coupled with the HP turbine section and the cold-reheat extraction conduit, the control system configured to: obtain data about a temperature of the HP exhaust steam; and provide instructions to modify a flow rate of the HP exhaust steam to the reheater in response to the temperature of the HP exhaust steam exceeding a threshold.

Abstract: The steam turbine includes the high-and-intermediate pressure turbine of the single flow type, the intermediate-pressure turbine of the single flow type, and the steam passage that communicates a location on a part way of the steam flow inside the high-and-intermediate pressure turbine, to the steam inlet of the intermediate-pressure turbine. The high-and-intermediate pressure turbine includes the high-pressure part on the steam inlet side and the intermediate-pressure part on the steam outlet side. The steam passage feeds a part of the steam having passed through the high-pressure part, from the location between the high-pressure part and the intermediate-pressure part, to the intermediate-pressure turbine.

Abstract: A saturated steam or weakly superheated steam thermodynamic cycle in an electricity generating plant includes at least a nuclear energy source and a turbine having at least a high-pressure module, a medium-pressure module and a low-pressure module. The steam flows successively through the high-pressure, medium-pressure and low-pressure modules. The steam undergoes a first drying and/or superheating cycle between the high-pressure and medium-pressure modules and also a second cycle comprising at least a drying and/or a superheating process between the medium-pressure module and the low-pressure module.

Abstract: Example embodiments include a vapor forming apparatus, system and/or method for producing vapor from radioactive decay material. The vapor forming apparatus including an insulated container configured to enclose a nuclear waste container. The nuclear waste container includes radioactive decay material. The insulated container includes an inlet valve configured to receive vapor forming liquid. The radioactive decay material transfers heat to the vapor forming liquid. The insulated container also includes an outlet valve configured to output the vapor forming liquid heated by the radioactive decay material.

Abstract: An electric generating system employing a nuclear reactor to heat feedwater prior to fossil fueled boiler and superheater sections to economically produce electricity with reduced greenhouse gas and other polluting emissions

Abstract: A cooling device for Stirling circulated dry storage container, which is mainly to make an accommodation space with opening within an external shield, and at the peripherals of the accommodation space, it is installed with a plurality of air flow inlets and air flow outlets that are connected to the external side. In addition, a shield cover is used to cover the opening of the accommodation space, and a nuclear waste storage container is installed within the accommodation space of the external shield, and the peripheral of the accommodation space and the nuclear waste storage container forms an air flow channel.

Abstract: A low energy nuclear thermoelectric system for a vehicle which provides a cost-effective and sustainable means of transportation for long operation range with zero emission using an onboard low energy nuclear reaction thermal generator. The present invention generally includes a thermal generator within a thermal enclosure case, an energy conversion system linked with the thermal generator, an energy storage system linked with the energy conversion system, a cooling system and a central control system. The thermal generator reacts nickel powder with hydrogen within a reactor chamber to produce heat. The heat is then transferred to the energy conversion system to be converted into electricity for storage in the energy storage system. The cooling system provides cooling for the various components of the present invention and the control system regulates its overall operation. The present invention may be utilized to power a vehicle in an efficient, sustainable and cost-effective manner.

Abstract: An electric generator comprises a central cylindrical shielded autoclave fuel capsule made out of metal in which are contained radioisotope fuel rods. A spiral cylindrical heat exchanger encases the fuel capsule. A thermal insulating material insulates the fuel capsule from the cylindrical heat exchanger which encases it to avoid thermal losses. The radioisotope fuel capsule and heat exchanger are contained within a cylindrical housing having a bore formed therein eccentrically located in a cylindrical rotor to form an “eccentric” compression chamber. A number of movable vanes slide radially inwards and outwards in slots formed in the cylindrical rotor. The ends of the vanes are biased against the walls of the eccentric cylinder by means of gas/vapor pressure in the rear part of the radial slots or by spring bias.

Abstract: Example embodiments include a vapor forming apparatus, system and/or method for producing vapor from radioactive decay material. The vapor forming apparatus including an insulated container configured to enclose a nuclear waste container. The nuclear waste container includes radioactive decay material. The insulated container includes an inlet valve configured to receive vapor forming liquid. The radioactive decay material transfers heat to the vapor forming liquid. The insulated container also includes an outlet valve configured to output the vapor forming liquid heated by the radioactive decay material.

Abstract: An apparatus for controlling an output of a pressure setting signal to automatically control a steam bypass control system includes a pressure setting signal output unit for outputting a pressure setting signal according to a cold leg temperature of a reactor coolant; a first logic value output unit for outputting a first logic value that is changed according to reactor power; a second logic value output unit for outputting a second logic value that is changed according to a temperature difference between an average temperature of the reactor coolant and a reference temperature; a NAND gate circuit unit for outputting an inverse logic value according to the first and second logic values; and a first output control unit for controlling whether to output the pressure setting signal according to the inverse logic value of the NAND gate circuit unit.

Abstract: In a nuclear power plant, thermal power in a second operation cycle of a nuclear reactor is uprated from thermal power in a first operation cycle preceding the second operation cycle by at least one operation cycle. A proportion of steam extracted from a steam system and introduced to a feedwater heater, which is in particular extracted from an intermediate point and an outlet of a high pressure turbine, with respect to a flow rate of main steam, is reduced in the second operation cycle from that in the first operation cycle such that the temperature of feedwater discharged from the feedwater heater is lowered by 1° C. to 40° C. in the second operation cycle.

Abstract: An electric power plant supplies steam generated to a high-pressure turbine and a low-pressure turbine. The steam discharged from the low-pressure turbine is condensed with a condenser. Water generated with the condenser is heated with a low-pressure feed water heater and a high-pressure feed water heater. The steam extracted from the high-pressure turbine is supplied to the high-pressure feed water heater. The steam extracted from the low-pressure turbine is compressed with a steam compressor, and the steam whose temperature has been increased is then supplied to the high-pressure feed water heater. The feed water is heated in the high-pressure feed water heater by the steam extracted from the high-pressure turbine and the steam compressed with the steam compressor. Because the feed water is heated by the extracted steam and the compressed steam in the high-pressure feed water heater, the amount of power consumed by the steam compressor can be reduced.

Abstract: A process (10) for co-producing synthesis gas and power includes in a synthesis gas generation stage, producing a hot synthesis gas and, in a nuclear power generation stage (12), heating a working fluid with heat generated by a nuclear reaction to produce a heated working fluid and generating power by expanding the heated working fluid using one or more turbines (16), with additional heating (14) of the heated working fluid by indirect transfer of heat from the hot synthesis gas to the heated working fluid.

Abstract: In a nuclear power plant, thermal power in a second operation cycle of a nuclear reactor is uprated from thermal power in a first operation cycle preceding the second operation cycle by at least one operation cycle. A proportion of steam extracted from a steam system and introduced to a feedwater heater, which is in particular extracted from an intermediate point and an outlet of a high pressure turbine, with respect to a flow rate of main steam, is reduced in the second operation cycle from that in the first operation cycle such that the temperature of feedwater discharged from the feedwater heater is lowered by 1° C. to 40° C. in the second operation cycle.

Abstract: A saturated steam or weakly superheated steam thermodynamic cycle in an electricity generating plant includes at least a nuclear energy source and a turbine having at least a high-pressure module, a medium-pressure module and a low-pressure module. The steam flows successively through the high-pressure, medium-pressure and low-pressure modules. The steam undergoes a first drying and/or superheating cycle between the high-pressure and medium-pressure modules and also a second cycle comprising at least a drying and/or a superheating process between the medium-pressure module and the low-pressure module.

Abstract: A nuclear island includes at least one nuclear reactor. A turbine island includes at least a turbine building housing at least one turbine driven by steam generated by the nuclear reactor. A protected area has a perimeter protected by at least one fence. An isolation zone surrounds the protected area and includes intrusion detection devices configured to detect unauthorized approach toward the protected area. The nuclear island is disposed inside the protected area, and the turbine island is disposed outside of and spaced apart from the protected area.

Abstract: Methods and systems are disclosed for the production of hydrogen and the use of high-temperature heat sources in energy conversion. In one embodiment, a primary loop may include a nuclear reactor utilizing a molten salt or helium as a coolant. The nuclear reactor may provide heat energy to a power generation loop for production of electrical energy. For example, a supercritical carbon dioxide fluid may be heated by the nuclear reactor via the molten salt and then expanded in a turbine to drive a generator. An intermediate heat exchange loop may also be thermally coupled with the primary loop and provide heat energy to one or more hydrogen production facilities. A portion of the hydrogen produced by the hydrogen production facility may be diverted to a combustor to elevate the temperature of water being split into hydrogen and oxygen by the hydrogen production facility.

Abstract: A hybrid power plant is described in which a pressurized water nuclear reactor or a biomass-fueled power plant, which have a relatively low operating temperature, such as, is combined with a coal or other fossil fuel power plant having a higher operating temperature. Steam from the first plant is superheated in the second power plant to provide a hybrid plant with improved efficiencies and lower emissions.

Abstract: An apparatus that harnesses the thermal energy of spent fuel rods in nuclear power plants to power the cooling system of the nuclear power plant particularly the cooling for the spent fuel rod storage ponds and the main reactors. The apparatus is comprised of a heat exchanger unit that accumulates the thermal energy of the spent fuel rods, a heat conveyance system that conveys the thermal energy of the spent fuel rods, and a heat engine that receives its thermal energy input from the spent fuel rods and produces mechanical power that runs an electrical generator which powers the cooling system of the nuclear power plant, particularly the controls and pumps that cool the spent fuel rod storage ponds and the main reactors. The apparatus provides a redundant power source and makes the cooling system of nuclear power plants independent of externally supplied electrical power and thereby resolves a key redundancy and safety concern with nuclear power generation.

Abstract: A superheated steam generator includes an introduction section for introducing saturated steam into hollow pipe members arranged as steam flow passages and acting as inductively heated elements, and a discharge section for discharging superheated steam from the flow passages, wherein a turbulence generator is disposed in each of the steam flow passages to accelerate heat transfer to the steam in the pipe members, wherein the turbulence generator is a zigzag bent member disposed in the steam flow passage, and a zigzag bending pitch of the bent member changes from rough to minute from the introduction section to the discharge section.

Abstract: In a nuclear power plant, thermal power in a second operation cycle of a nuclear reactor is uprated from thermal power in a first operation cycle preceding the second operation cycle by at least one operation cycle. A proportion of steam extracted from a steam system and introduced to a feedwater heater, which is in particular extracted from an intermediate point and an outlet of a high pressure turbine, with respect to a flow rate of main steam, is reduced in the second operation cycle from that in the first operation cycle such that the temperature of feedwater discharged from the feedwater heater is lowered by 1° C. to 40° C. in the second operation cycle.

Abstract: In a nuclear power plant, thermal power in a second operation cycle of a nuclear reactor is uprated from thermal power in a first operation cycle preceding the second operation cycle by at least one operation cycle. A proportion of steam extracted from a steam system and introduced to a feedwater heater, which is in particular extracted from an intermediate point and an outlet of a high pressure turbine, with respect to a flow rate of main steam, is reduced in the second operation cycle from that in the first operation cycle such that the temperature of feedwater discharged from the feedwater heater is lowered by 1° C. to 40° C. in the second operation cycle.

Abstract: In a nuclear power plant, thermal power in a second operation cycle of a nuclear reactor is uprated from thermal power in a first operation cycle preceding the second operation cycle by at least one operation cycle. A proportion of steam extracted from a steam system and introduced to a feedwater heater, which is in particular extracted from an intermediate point and an outlet of a high pressure turbine, with respect to a flow rate of main steam, is reduced in the second operation cycle from that in the first operation cycle such that the temperature of feedwater discharged from the feedwater heater is lowered by 1° C. to 40° C. in the second operation cycle.

Abstract: A nuclear power plant and method of operation for augmenting a second reactor thermal power output in a second operation cycle to a level larger than a first reactor thermal power output in the previous operation cycle. The plant is equipped, for example, with a reactor; a steam loop comprising high and low pressure turbines; a condenser for condensing steam discharged therefrom the low pressure turbine; a feedwater heater for heating feedwater supplied from the condenser; and a feedwater loop for leading feedwater discharged from the feedwater heater to the reactor. The operation method includes decreasing a ratio of extraction steam which is led to the feedwater heater from a steam loop in the second operation cycle.

Abstract: Pendular and differential periodic heat engines with theoretical efficiencies of ONE, and industrial efficiencies close to ONE, exclusively subordinate to the physical constraints inherent in any material device under ordinary conditions of use, operating with recirculation of the gases in closed loops between a thermodynamic pendulum (2/2, 2/4) made up of a chamber (1/2, 1/4) fitted with a piston (2/2, 2/4) connected to a free flywheel (3/2), and a regulated supply of heat (10/4, 10/4, etc.) positioned some distance away from the chamber of the thermodynamic pendulum (FIG. 2), with extension to turbine engines (FIG. 5) thanks to phase changes.

Abstract: Methods and systems are disclosed for the production of hydrogen and the use of high-temperature heat sources in energy conversion. In one embodiment, a primary loop may include a nuclear reactor utilizing a molten salt or helium as a coolant. The nuclear reactor may provide heat energy to a power generation loop for production of electrical energy. For example, a supercritical carbon dioxide fluid may be heated by the nuclear reactor via the molten salt and then expanded in a turbine to drive a generator. An intermediate heat exchange loop may also be thermally coupled with the primary loop and provide heat energy to one or more hydrogen production facilities. A portion of the hydrogen produced by the hydrogen production facility may be diverted to a combustor to elevate the temperature of water being split into hydrogen and oxygen by the hydrogen production facility.

Abstract: A process (10) for co-producing synthesis gas and power includes in a synthesis gas generation stage, producing a hot synthesis gas and, in a nuclear power generation stage (12), heating a working fluid with heat generated by a nuclear reaction to produce a heated working fluid and generating power by expanding the heated working fluid using one or more turbines (16), with additional heating (14) of the heated working fluid by indirect transfer of heat from the hot synthesis gas to the heated working fluid.

Abstract: A method and apparatus for extracting useful energy from biomass fuels as part of a hybrid electricity generating thermal power plant, utilising both a primary heat source, such as coal, gas, oil or nuclear power, and a secondary heat source in the form of biomass, whereby the biomass is oxidised in aqueous solution in a supercritical water oxidation (SCWO) process utilising energy from the primary heat source to heat and compress a feed stream of water to a temperature and pressure at or beyond its critical point.

Abstract: A method and apparatus for forming a chemical hydride is described and which includes a pseudo-plasma-electrolysis reactor which is operable to receive a solution capable of forming a chemical hydride and which further includes a cathode and a movable anode, and wherein the anode is moved into and out of fluidic, ohmic electrical contact with the solution capable of forming a chemical hydride and which further, when energized produces an oxygen plasma which facilitates the formation of a chemical hydride in the solution.

Abstract: Disclosed herein is an integrated process for production of electricity, hydrogen, and water using a high-temperature gas-cooled reactor as a single source, including: the high-temperature gas-cooled reactor, a power conversion unit connected directly or indirectly with the high-temperature gas-cooled reactor to receive heat produced by a reactor core of the high-temperature gas-cooled reactor and drive a gas turbine by the heat, thereby producing electricity through an electric generator, a hydrogen production unit that produces hydrogen by receiving the heat produced by the high-temperature gas-cooled reactor and/or the electricity produced by the electric generator, an electrical desalination unit that produces water by using the electricity produced by the electric generator, and a thermal desalination unit that produces water by distilling fresh water from salt water with waste heat recovered from a precooler and an intercooler of the power conversion unit.

Abstract: A system and a method are provided that may be used to control the temperature of steam being reheated by a moisture separator reheater (MSR). The temperature of a steam being reheated by a MSR may be sensed, and controller embodiments may use the sensed temperature to control the transfer of heat from various MSR components into the reheated steam. By using such control embodiments, the MSR may provide optimally heated steam to other power plant components, thus increasing the performance, efficiency, and safety of a power plant.

Abstract: This invention publishes a kind of nuclear reactor, including shell body, lighter system, starting system and fuel system, the shell body is installed magnetic force bearing axle, which is installed flywheel axle, which is installed flywheel, which is installed gas-mixed room, and there is air inlet in the middle of gas-mixed room, cylinder installed on the outside of flywheel. There is an air outlet on the outside of the air-mixed room, air inlets on cylinder bottom, the air outlets and inlets are interconnected. There are lighters equipped in cylinder, which's spraying direction and flywheel semi diameter form the included angle ?1. it adopts the new manner of nuclear reaction, which can realize every kind of nuclear reaction, realize the nuclear fusion and realize the reaction of ganta into energy, safe and reliable and without any nuclear.

Abstract: A power generation system includes a mixing unit for receiving and combining heated fluid from a heated fluid source and working fluid to form a vapor. The system also includes a condensation unit positioned at a location having a higher elevation than the heated fluid source. The condensation unit receives the vapor from the mixing unit through a first conduit and condenses the vapor into a liquid. The system further includes a turbine positioned at a location having a lower elevation than the condensation unit. The turbine receives the liquid condensed in the condensation unit through a second conduit. The turbine is driven by the liquid to generate electric power. The system also includes a heat exchanger for transferring heat from the liquid driving the turbine to the working fluid provided to the mixing unit.

Abstract: The objects are to provide easy maintenance/inspection and to rapidly achieve stable start-up of a plant. Provided is a closed-cycle plant including a high-temperature gas-cooled reactor having a nuclear reactor; a gas turbine that is driven by working fluid heated in the high-temperature gas-cooled reactor; a low-pressure compressor and high-pressure compressor that are linked coaxially with the gas turbine; a power generator connected to the gas turbine through an output shaft; and a power supply unit that is connected to the power generator in a disconnectable manner and supplies electric power, wherein, at startup, the power supply unit is connected to the power generator and electric power is supplied so as to make the speed-up ratio of the power generator constant.

Abstract: In a nuclear power plant, thermal power in a second operation cycle of a nuclear reactor is uprated from thermal power in a first operation cycle preceding the second operation cycle by at least one operation cycle. A proportion of steam extracted from a steam system and introduced to a feedwater heater, which is in particular extracted from an intermediate point and an outlet of a high pressure turbine, with respect to a flow rate of main steam, is reduced in the second operation cycle from that in the first operation cycle such that the temperature of feedwater discharged from the feedwater heater is lowered by 1° C. to 40° C. in the second operation cycle.

Abstract: A method of converting energy into electricity using a gaseous working fluid and an evaporative fluid comprises pressuring the working fluid (20) in a compressor (1), heating the high-pressure working fluid (22) in a recuperator (8) using thermal energy in low-pressure working fluid (34) emerging from a turbine (2), adding energy from an energy source (5, 6) to increase the temperature and enthalpy of the working fluid (32), expanding the working fluid (32) through the turbine (2), using the turbine to generate electricity, and cooling the low-pressure working fluid (34) emerging from the turbine in the recuperator. The method further comprises lowering the temperature and increasing the mass of the high-pressure working fluid (22) after leaving the compressor (1), and/or after leaving the recuperator (8), by introducing the evaporative fluid (48, 49) to produce evaporative cooling.

Abstract: Methods and systems are disclosed for generating power though the use of thermodynamic engines and low-temperature liquids. A liquid cryogen maintains a temperature differential with a heat source across a thermodynamic engine. The thermodynamic engine is run to convert heat provided in the form of the temperature differential to a nonheat form of energy. Cryogen vapor produced by vaporization of the liquid cryogen is collected and combusted to generate additional energy.

Abstract: In a nuclear power plant, thermal power in a second operation cycle of a nuclear reactor is uprated from thermal power in a first operation cycle preceding the second operation cycle by at least one operation cycle. A proportion of steam extracted from a steam system and introduced to a feedwater heater, which is in particular extracted from an intermediate point and an outlet of a high pressure turbine, with respect to a flow rate of main steam, is reduced in the second operation cycle from that in the first operation cycle such that the temperature of feedwater discharged from the feedwater heater is lowered by 1° C. to 40° C. in the second operation cycle.

Abstract: A gas turbine plant, wherein a plurality of first gas turbines positioned coaxially with compressors and a second gas turbine positioned coaxially with a generator are rotated by a coolant heated by heat energy provided by the fission of a coated particle fuel. A flow in a bypass passage is controlled by controlling the opening of bypass valves of (n?1) in quantity which bypass the first gas turbines on up to (n?1) shafts in starting. Accordingly, the rotational speeds of the first gas turbines on up to (n) shafts are increased to a rated rotational speed in order starting at the initial stage on the upstream side of a high temperature gas-cooled reactor toward the lower stage for each shaft.

Abstract: The group of inventions relates to nuclear techniques and to power industry. The nuclear power plant contains a nuclear reactor (1) cooled by liquid metal, for example lead. Heated-up liquid metal is cooling in heat exchanger <<liquid metal-gas>> (3). This heat exchanger is embodied as not-mixing heat exchanger. The pump (2) moves cooled liquid metal through the filters into the reactor (1). The compressor (4) moves gas through heat exchanger <<liquid metal-gas>> (3) into gas turbines (8, 9, 10, 22, 23, 24). After gas turbines this gas vaporizes and overheats the water in heat exchangers <<gas-water>> (5, 6, 7) and moves back to compressor (3). Produced steam moves the steam turbines (12, 13), condenses into the water by means of condenser (15) and circulation pump (16) and then is moved by the pumps (17, 20) back to heat exchangers <<gas-water>> (5, 6, 7).

Abstract: An efficient turbine system that preferably utilizes nuclear thermal energy in a unique combined Carnot cycle and Rankine cycle in a closed cogenerative and regenerative cycle with a condensible working fluid heated by the nuclear thermal energy and delivered to each stage of a multiple-stage gas turbine for isothermal expansion with a portion of the spent working fluid condensed and injected onto stators before and between the turbine blade stages and onto the turbine blades for a regenerative cogeneration expansion that supplements and combines with the primary working fluid in the staged gas turbine and in a final adiabatic expansion in a staged recovery turbine with work extracted by electric generators.

Abstract: Oxygen is mixed with heater drain water of power plant which contains fine particles of iron oxides such that the concentration of the dissolved oxygen in the heater drain water after the mixing of oxygen is in a range from 1 &mgr;g/liter to 20 &mgr;g/liter. The obtained heater drain water after oxygen mixing is filtered through a filter such as a hollow fiber filter to remove fine particles of iron oxides.

Abstract: Methods and apparatuses are provided for removing thermal energy from a nuclear reactor, which are fault tolerant. The apparatus includes at least one heat pipe configured to absorb thermal energy produced by the nuclear reactor. In addition, the apparatus includes a first compartment thermally coupled to the at least one heat pipe. The first compartment is configured to contain a first gas. Furthermore, the apparatus includes a second compartment thermally coupled to the at least one heat pipe. The second compartment is configured to contain a second gas and configured to isolate the second gas from the first gas.

Abstract: A steam turbine power plant comprises a high-pressure turbine to be driven by steam generated by a steam generator, a first reheater for separating moisture from steam discharged from the high-pressure turbine and heating the steam, an intermediate-pressure turbine to be driven by the steam heated by the first reheater, a second reheater for heating exhaust steam discharged from the intermediate-pressure turbine, and a low-pressure turbine to be driven by the steam heated by the second reheater. The intermediate-pressure turbine discharges dry steam.

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 saturated steam generation system is supplemented with at least one gas turbine set, at least one heat recovery steam generator, at least one topping steam turbine and at least one steam mixing component. The topping steam turbine is coupled to the gas turbine set and is supplied by the steam generated in the heat recovery steam generator. The exhaust steam from the topping steam turbine is fed via the steam mixing component to the steam turbine set.