WO2002080190A1 - Nuclear power plant and method of operating the same - Google Patents

Nuclear power plant and method of operating the same Download PDF

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Publication number
WO2002080190A1
WO2002080190A1 PCT/IB2002/000979 IB0200979W WO02080190A1 WO 2002080190 A1 WO2002080190 A1 WO 2002080190A1 IB 0200979 W IB0200979 W IB 0200979W WO 02080190 A1 WO02080190 A1 WO 02080190A1
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WO
WIPO (PCT)
Prior art keywords
temperature
low pressure
gas
turbine
recuperator
Prior art date
Application number
PCT/IB2002/000979
Other languages
French (fr)
Other versions
WO2002080190A8 (en
WO2002080190B1 (en
Inventor
Willem Adriaan Odendaal Kriel
Original Assignee
Pebble Bed Modular Reactor (Proprietary) Limited
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Pebble Bed Modular Reactor (Proprietary) Limited filed Critical Pebble Bed Modular Reactor (Proprietary) Limited
Priority to AU2002253417A priority Critical patent/AU2002253417A1/en
Publication of WO2002080190A1 publication Critical patent/WO2002080190A1/en
Publication of WO2002080190A8 publication Critical patent/WO2002080190A8/en
Publication of WO2002080190B1 publication Critical patent/WO2002080190B1/en

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Classifications

    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F02COMBUSTION ENGINES; HOT-GAS OR COMBUSTION-PRODUCT ENGINE PLANTS
    • F02CGAS-TURBINE PLANTS; AIR INTAKES FOR JET-PROPULSION PLANTS; CONTROLLING FUEL SUPPLY IN AIR-BREATHING JET-PROPULSION PLANTS
    • F02C1/00Gas-turbine plants characterised by the use of hot gases or unheated pressurised gases, as the working fluid
    • F02C1/04Gas-turbine plants characterised by the use of hot gases or unheated pressurised gases, as the working fluid the working fluid being heated indirectly
    • F02C1/10Closed cycles
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F02COMBUSTION ENGINES; HOT-GAS OR COMBUSTION-PRODUCT ENGINE PLANTS
    • F02CGAS-TURBINE PLANTS; AIR INTAKES FOR JET-PROPULSION PLANTS; CONTROLLING FUEL SUPPLY IN AIR-BREATHING JET-PROPULSION PLANTS
    • F02C1/00Gas-turbine plants characterised by the use of hot gases or unheated pressurised gases, as the working fluid
    • F02C1/04Gas-turbine plants characterised by the use of hot gases or unheated pressurised gases, as the working fluid the working fluid being heated indirectly
    • F02C1/05Gas-turbine plants characterised by the use of hot gases or unheated pressurised gases, as the working fluid the working fluid being heated indirectly characterised by the type or source of heat, e.g. using nuclear or solar energy
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F02COMBUSTION ENGINES; HOT-GAS OR COMBUSTION-PRODUCT ENGINE PLANTS
    • F02CGAS-TURBINE PLANTS; AIR INTAKES FOR JET-PROPULSION PLANTS; CONTROLLING FUEL SUPPLY IN AIR-BREATHING JET-PROPULSION PLANTS
    • F02C9/00Controlling gas-turbine plants; Controlling fuel supply in air- breathing jet-propulsion plants
    • F02C9/16Control of working fluid flow
    • F02C9/18Control of working fluid flow by bleeding, bypassing or acting on variable working fluid interconnections between turbines or compressors or their stages
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F02COMBUSTION ENGINES; HOT-GAS OR COMBUSTION-PRODUCT ENGINE PLANTS
    • F02CGAS-TURBINE PLANTS; AIR INTAKES FOR JET-PROPULSION PLANTS; CONTROLLING FUEL SUPPLY IN AIR-BREATHING JET-PROPULSION PLANTS
    • F02C9/00Controlling gas-turbine plants; Controlling fuel supply in air- breathing jet-propulsion plants
    • F02C9/16Control of working fluid flow
    • F02C9/24Control of the pressure level in closed cycles
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C1/00Reactor types
    • G21C1/04Thermal reactors ; Epithermal reactors
    • G21C1/06Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/07Pebble-bed reactors; Reactors with granular fuel
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/24Promoting flow of the coolant
    • G21C15/253Promoting flow of the coolant for gases, e.g. blowers
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D1/00Details of nuclear power plant
    • G21D1/02Arrangements of auxiliary equipment
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D3/00Control of nuclear power plant
    • G21D3/08Regulation of any parameters in the plant
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D5/00Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
    • G21D5/04Reactor and engine not structurally combined
    • G21D5/06Reactor and engine not structurally combined with engine working medium circulating through reactor core
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F05INDEXING SCHEMES RELATING TO ENGINES OR PUMPS IN VARIOUS SUBCLASSES OF CLASSES F01-F04
    • F05DINDEXING SCHEME FOR ASPECTS RELATING TO NON-POSITIVE-DISPLACEMENT MACHINES OR ENGINES, GAS-TURBINES OR JET-PROPULSION PLANTS
    • F05D2210/00Working fluids
    • F05D2210/10Kind or type
    • F05D2210/12Kind or type gaseous, i.e. compressible
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F05INDEXING SCHEMES RELATING TO ENGINES OR PUMPS IN VARIOUS SUBCLASSES OF CLASSES F01-F04
    • F05DINDEXING SCHEME FOR ASPECTS RELATING TO NON-POSITIVE-DISPLACEMENT MACHINES OR ENGINES, GAS-TURBINES OR JET-PROPULSION PLANTS
    • F05D2270/00Control
    • F05D2270/01Purpose of the control system
    • F05D2270/06Purpose of the control system to match engine to driven device
    • F05D2270/061Purpose of the control system to match engine to driven device in particular the electrical frequency of driven generator
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F05INDEXING SCHEMES RELATING TO ENGINES OR PUMPS IN VARIOUS SUBCLASSES OF CLASSES F01-F04
    • F05DINDEXING SCHEME FOR ASPECTS RELATING TO NON-POSITIVE-DISPLACEMENT MACHINES OR ENGINES, GAS-TURBINES OR JET-PROPULSION PLANTS
    • F05D2270/00Control
    • F05D2270/01Purpose of the control system
    • F05D2270/11Purpose of the control system to prolong engine life
    • F05D2270/112Purpose of the control system to prolong engine life by limiting temperatures
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F05INDEXING SCHEMES RELATING TO ENGINES OR PUMPS IN VARIOUS SUBCLASSES OF CLASSES F01-F04
    • F05DINDEXING SCHEME FOR ASPECTS RELATING TO NON-POSITIVE-DISPLACEMENT MACHINES OR ENGINES, GAS-TURBINES OR JET-PROPULSION PLANTS
    • F05D2270/00Control
    • F05D2270/30Control parameters, e.g. input parameters
    • F05D2270/303Temperature
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Definitions

  • THIS INVENTION relates to a nuclear power plant. More particularly it relates to a method of operating the nuclear power plant.
  • a method of operating the nuclear power plant which includes the steps of monitoring the temperature of the gas entering at least one of the components of the power plant; and if the temperature of the gas entering the at least one component of the power plant exceeds a predetermined maximum temperature, mixing cooler gas with the gas whose temperature has exceeded the predetermined maximum temperature, to reduce the temperature of the gas before it enters the at least one component.
  • the nuclear power plant includes a high temperature gas, typically helium, cooled reactor and a power conversion unit which is connected together with the reactor in a closed loop and which includes a high pressure turbine, a low pressure turbine, a power turbine, a counterflow recuperator having a high pressure side and a low pressure side, each side having an inlet and an outlet, a low pressure compressor to which the low pressure turbine is drivingly connected, and a high pressure compressor to which the high pressure turbine is drivingly connected
  • the method may include the steps of monitoring the temperature of the gas entering at least one of the high pressure turbine, the low pressure turbine, the power turbine and the low pressure side of the recuperator; and if the temperature of the gas entering the at least one of the high pressure turbine, low pressure turbine, power turbine, and low pressure side of the recuperator, exceeds a predetermined maximum temperature, mixing cooler gas with the gas the temperature of which has exceeded the predetermined maximum temperature, to reduce the temperature of the gas before it enters the at least one of the high pressure turbine, low pressure turbine, power turbine and low pressure side
  • the source of the cooler gas may be the low temperature section of the power generation circuit, the method then including feeding the cooler gas from the low temperature section of the power generation circuit to a position in the high temperature section of the circuit upstream of the at least one of the high pressure turbine, low pressure turbine, power turbine and low pressure side of the recuperator.
  • the method may include regulating the flow of gas from the low temperature section of the circuit to the high temperature section of the circuit by means of at least one coolant valve.
  • a nuclear power plant which includes a high temperature gas cooled reactor and a power conversion unit connected together with the reactor in a closed loop power generation circuit; temperature sensing means for sensing the temperature of a gas entering at least one component of the power generation circuit; at least one coolant feed line leading from a source of coolant gas to a position upstream of the at least one component; and a coolant valve mounted in the coolant feed line and arranged to regulate the flow of coolant gas through the coolant feed line in response to signals received from the temperature sensing means thereby to permit the temperature of the gas entering the at least one component to be regulated.
  • the power conversion unit may include a high pressure turbine, a low pressure turbine, a power turbine, a counterflow recuperator having a high pressure and a low pressure side, each side having an inlet and an outlet, a low pressure compressor to which the low pressure turbine is drivingly connected, a high pressure compressor to which the high pressure turbine is drivingly connected, a pre-cooler positioned in series upstream of the low pressure compressor and an intercooler positioned between the low pressure compressor and the high pressure compressor, the power generation circuit having a high temperature section defined on the reactor side of the recuperator and a low temperature section defined on the other side of the recuperator, the plant including temperature sensing means for sensing the temperature of gas entering at least one of the high pressure turbine, low pressure turbine, power turbine and low pressure side of the recuperator; at least one coolant feedline extending from the low temperature section of the circuit to a position upstream of the at least one of the high pressure turbine, low pressure turbine, power turbine and low pressure side of the recuperator; and a coolant valve mounted in the coolant feedline
  • the reactor typically has an outlet which is connected to an inlet of the high pressure turbine, an outlet of the high pressure turbine being connected to an inlet of the low pressure turbine, an outlet of the low pressure turbine being connected to an inlet of the power turbine, an outlet of the power turbine beingconnected to an inlet of the low pressure side of the recuperator, an outlet of the low pressure side of the recuperator being connected via the pre-coolerto the inlet of the low pressure compressor, an outlet of the low pressure compressor being connected via the intercooler to an inlet of the high pressure compressor, an outlet of the high pressure compressor being connected to an inlet of the high pressure side of the recuperator and an outlet of the high pressure side of the recuperator being connected to an inlet of the reactor.
  • a temperature sensing means, a coolant feedline and a coolant valve may be provided in respect of each of the high pressure turbine, the low pressure turbine, the power turbine and the inlet on the low pressure side of the recuperator to regulate the temperature of gas being fed thereto.
  • the coolant feedlines may each have an inlet which is connected to the low temperature section of the power generation circuit between the outlet of the low pressure compressor and the inlet of the high pressure side of the recuperator and an outlet which is connected to the high temperature section of the power generation circuit at a position upstream of the associated high pressure turbine, low pressure turbine, power turbine and inlet of the low pressure side of the recuperator, as the case may be.
  • the power generation circuit may make use of a direct closed Brayton cycle as the thermodynamic conversion cycle.
  • the reactor is typically of the pebble bed type having a core which includes a plurality of spherical fuel elements or pebbles.
  • the Brayton cycle typically has a high temperature section and a lopw temperature section corresponding to the high temperature section and low temperature section respectively, of the power generation circuit.
  • the transitions between the high temperature section and low temperature section occur within the recuperator.
  • a recirculation valve configuration and associated control system are designed to address the requirements of being able to operate under various load conditions and to accommodate abrupt loss of load with the minimum impact.
  • the Inventor believes that the invention will find application particularly when mass flow through the reactor core is reduced resulting in a decrease in fluidic power. This can occur when the recirculation valve configuration is opened in order to compensate for a reduction in power demand. As a result, the power delivered by the power turbine will decrease due to the bigger fraction of available power being consumed by the compressors as well as the decreased efficiency of the power turbine owing to the lower mass flow therethrough. As a result, the gas temperature entering the high pressure turbine, low pressure turbine, power turbine and low pressure side of the recuperator tend to increase. This is due to the fact that the reactor outlet temperature remains the same, but less heat is removed by the high pressure turbine, low pressure turbine and power turbine. This increase in temperature can be compensated for making use of the coolant valves as described above.
  • reference numeral 10 refers generally to part of a nuclear power plant in accordance with the invention.
  • the nuclear power plant 10 includes a closed loop power generation circuit, generally indicated by reference numeral 1 2.
  • the power generation circuit 12 includes a nuclear reactor 14 and a power conversion unit, generally indicated by reference numeral 1 6.
  • the power conversion unit 1 6 includes a high pressure turbine 1 8, a low pressure turbine 20, a power turbine 22, a counterflow recuperator 24, a pre-cooler 26, a low pressure compressor 28, an intercooler 30 and a high pressure compressor 32.
  • the reactor 14 is a high temperature helium cooled pebble bed reactor making use of spherical fuel elements.
  • the reactor 14 has an inlet 14.1 and an outlet 14.2.
  • the high pressure turbine 1 8 is drivingly connected to the high pressure compressor 32 and has an upstream side or inlet 18.1 and a downstream side or outlet 1 8.2, the inlet 1 8.1 being connected to the outlet 14.2 of the reactor 14.
  • the low pressure turbine 20 is drivingly connected to the low pressure compressor 28 and has an upstream side or inlet 20.1 and a downstream side or outlet 20.2.
  • the inlet 20.1 is connected to the outlet 18.2 of the high pressure turbine 18.
  • the nuclear power plant 10 includes a generator, generally indicated by reference numeral 34 to which the power turbine 22 is drivingly connected.
  • the power turbine 22 includes an upstream side or inlet 22.1 and a downstream side or outlet 22.2.
  • the inlet 22.1 of the power turbine 22 is connected to the outlet 20.2 of the low pressure turbine 20.
  • the recuperator 24 has a low pressure side 36 and a high pressure side 38.
  • the low pressure side of the recuperator 36 has an inlet 36.1 and an outlet 36.2.
  • the inlet 36.1 of the low pressure side is connected to the outlet 22.2 of the power turbine 22.
  • the pre-cooler 26 is a helium to water heat exchanger and includes a helium inlet 26.1 and a helium outlet 26.2.
  • the inlet 26.1 of the pre-cooler 26 is connected to the outlet 36.2 of the low pressure side 36 of the recuperator 24.
  • the low pressure compressor 28 has an upstream side or inlet 28.1 and a downstream side or outlet 28.2.
  • the inlet 28.1 of the low pressure compressor 28 is connected to the helium outlet 26.2 of the pre-cooler 26.
  • the intercooler 30 is a helium to water heat exchanger and includes a helium inlet 30.1 and a helium outlet 30.2.
  • the helium inlet 30.1 is connected to the outlet 28.2 of the low pressure compressor 28.
  • the high pressure compressor 32 includes an upstream side or inlet 32.1 and a downstream side or outlet 32.2.
  • the inlet 32.1 of the high pressure compressor 32 is connected to the helium outlet 30.2 of the intercooler 30.
  • the outlet 32.2 of the high pressure compressor 32 is connected to an inlet 38.1 of high pressure side of the recuperator 24.
  • An outlet 38.2 of the high pressure side of the recuperator 24 is connected to the inlet 14.1 of the reactor 14.
  • the nuclear power plant 10 includes a start-up blower system, generally indicated by reference numeral 40, connected between the outlet 36.2 of the low pressure side 36 of the recuperator 24 and the inlet 26.1 of the pre-cooler 26.
  • the start-up blower system 40 includes a normally open start-up system in line valve 42 which is connected in line between the outlet 36.2 of the low pressure side of the recuperator and the inlet 26.1 of the pre-cooler 26.
  • a low pressure compressor recirculation line 48 extends from a position between the outlet or downstream side 28.2 of the low pressure compressor 28 and the inlet 30.1 of the intercooler 30 to a position between the start-up blower system 40 and the inlet 26.1 of the pre- cooler 26.
  • a normally closed low pressure recirculation valve arrangement 50 is mounted in the low pressure compressor recirculation line 48.
  • a high pressure compressor recirculation line 52 extends from a position between the outlet or downstream side of 32.2 of the high pressure compressor and the inlet 38.1 of the high pressure side 38 of the recuperator 24 to a position between the outlet or downstream side 28.2 of the low pressure compressor 28 and the inlet 30.1 of the intercooler 30.
  • a normally closed high pressure recirculation valve arrangement 53 is mounted in the high pressure compressor recirculation line 52.
  • the power generation circuit 12 hence has a high temperature section, generally indicated by reference numeral 60 which is on the reactor side of the recuperator 36 and a low temperature section, generally indicated by reference numeral 62 which is on the other side of the recuperator 36.
  • the transitions between the high temperature section 60 and the low temperature section 62 typically occur at the recuperator 36.
  • the plant 10 includes four coolant feed lines 64, 66, 68, 70 in each of which a coolant valve 72, 74, 76, 78, respectively, is mounted.
  • the coolant feed lines 64, 66, 68, 70 extend from a position between the outlet 32.2 of the high pressure compressor 32 and the inlet 38.1 of the low pressure side 38 of the recuperator 24 to positions upstream of the high pressure turbine 18, low pressure turbine 20, power turbine 22 and low pressure side 36 of the recuperator 24, respectively.
  • the coolant feed lines could in fact lead from any position between the outlet 28.2 of the low pressure compressor and the inlet 38.1 .
  • the plant 10 further includes temperature sensing means in the form of sensors 73, 75, 77, 79 for sensing the temperature of helium entering the high pressure turbine 18, low pressure turbine 20, power turbine 22 and low pressure side 36 of the recuperator 24, respectively.
  • the temperature sensor 73 associated with the high pressure turbine is operatively connected to the coolant valve 72 to control the operation thereof.
  • the temperature sensors 75, 77, 79 associated with the low pressure turbine 20, power turbine 22 and low pressure side 36 of the recuperator 26 are operatively connected to the coolant valves 74, 76, 78, respectively.
  • the plant 10 which makes use of a Brayton cycle as the thermodynamic conversion cycle is designed for operation under various load conditions. The load conditions might vary from ordinary and frequent load variations, to a complete loss of load.
  • the focus during these changes in load will be on keeping the plant synchronized with and connected to an electrical distribution grid, whilst keeping the Brayton cycle self-sustaining. This is desirable to ensure that the plant 10 can react promptly to demand variations.
  • regular changes in required delivery are foreseen, and the plant is therefore designed to be able to accommodate the load changes with minimum impact on plant operation.
  • the plant 10 is furthermore designed to be capable of accommodating an abrupt loss of load whilst again still remaining synchronized and connected to the grid, with the Brayton cycle continuing to be self-sustaining. This will typically result in the case of the power levels approaching zero with minimal or no delivery to the grid.
  • the recirculation valve arrangements 50, 53 can be used to regulate the power output of the plant 10.
  • the recirculation valve arrangement 50, 53 is opened. This results in reduced mass flow through the reactor core and therefore a decrease in fluidic power.
  • the power delivered by the power turbine 22 will decrease due to the bigger fraction of available power being consumed by the turbo machines 28, 32 as well as the decreased efficiency of the power turbine 22 owing to the lower mass flow therethrough.
  • the electrical power generated can be controlled and adjusted relatively quickly.
  • the gas temperature entering the high pressure turbine 18, low pressure turbine 20, power turbine 22 and low pressure side 36 of the recuperator 24 tend to increase. This is due to the fact that the reactor outlet temperature remains the same, but less heat is removed by the high pressure turbine 18, low pressure turbine 20 and power turbine 22.
  • the maximum temperature of gas entering these components not exceed a predetermined maximum temperature (eg of the order of 600°C in the case of the recuperator 24). Accordingly, the temperature sensors73, 75, 77, 79 associated with each of these components sense the temperature of gas entering the associated components. Should the temperature of the gas exceed a predetermined maximum temperature, then the associated coolant valve 72, 74, 76, 78 is opened thereby to feed cooler helium from the low temperature section 62 to the high temperature section 60 which is mixed with the high temperature helium prior to its introduction into the turbine 18, 20, 22 or the recuperator 24, as the case may be.
  • a predetermined maximum temperature eg of the order of 600°C in the case of the recuperator 24.
  • the temperature of the gas entering the components can be maintained at a temperature below the predetermined maximum temperature thereby avoiding overheating and possible damage of the components on the high temperature section of the power generation circuit 12.
  • a secondary advantage associated with the opening of the coolant valves 72, 74, 76, 78 is that they will augment the compressor recirculation valve power control process, as the coolant valves will in fact be acting as additional recirculation valves.
  • the coolant valves 72, 74, 76, 78 can also be used during the process of decay heat removal.
  • the start-up blower system 40 is operational and is used to remove heat from the core.
  • the start-up blower system 40 delivers relatively lower flow rates than the compressors 28, 33 and therefor the same situation as described above, ie the possibility of the temperature of the gas entering the turbines 18, 20, 22 or recuperator 24 exceeding the predetermined maximum temperature exists.
  • the coolant valves 72, 74, 76, 78 can be used in the manner described above to regulate the temperature of gas entering the various components by mixing helium from the low temperature section of the power generation circuit with the high temperature gas stream.
  • coolant valves 72, 74, 76, 78 have been described as single valves, they may in fact each comprise a valve set.
  • the valve sets could include combinations of differently sized control valves or any other arrangement. Further, the control of the valves may be such that the valves can be used separately or in any required combination.
  • the Inventor believes that the invention will permit the plant to accommodate variations in load demand quickly and safely. It will also enable the removal of decay heat from the reactor, without causing damage to equipment in the high temperature section by exposure to temperatures above the maximum desired temperatures.

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  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • Combustion & Propulsion (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Plasma & Fusion (AREA)
  • Mechanical Engineering (AREA)
  • Fluid Mechanics (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Sustainable Development (AREA)
  • Sustainable Energy (AREA)
  • Control Of Turbines (AREA)
  • Control Of Temperature (AREA)

Abstract

A nuclear power plant makes use of a high temperature gas cooled reactor. Under certain circumstances, the possibility exists that the temperature of gas entering various components of the plant exceeds desired operating parameters. To prevent this, the temperature of the gas entering at least one of the components of the power plant is monitored and, should the temperature of the gas exceed a predetermined temperature, cooler gas is mixed with the gas whose temperature had exceeded the predetermined temperature, to reduce the temperature of the gas. Accordingly, the plant includes at least one coolant feedline leading from a source of coolant gas, typically at a point in the power generation circuit where the temperature of the gas is relatively low, to a position upstream of the component. A coolant valve is mounted in the coolant feedline to regulate the flow of coolant gas therethrough.

Description

NUCLEAR POWER PLANT AND METHOD OF OPERATING THE SAME
THIS INVENTION relates to a nuclear power plant. More particularly it relates to a method of operating the nuclear power plant.
According to one aspect of the invention, in a nuclear power plant which uses gas as the working fluid, there is provided a method of operating the nuclear power plant, which includes the steps of monitoring the temperature of the gas entering at least one of the components of the power plant; and if the temperature of the gas entering the at least one component of the power plant exceeds a predetermined maximum temperature, mixing cooler gas with the gas whose temperature has exceeded the predetermined maximum temperature, to reduce the temperature of the gas before it enters the at least one component.
When the nuclear power plant includes a high temperature gas, typically helium, cooled reactor and a power conversion unit which is connected together with the reactor in a closed loop and which includes a high pressure turbine, a low pressure turbine, a power turbine, a counterflow recuperator having a high pressure side and a low pressure side, each side having an inlet and an outlet, a low pressure compressor to which the low pressure turbine is drivingly connected, and a high pressure compressor to which the high pressure turbine is drivingly connected, the method may include the steps of monitoring the temperature of the gas entering at least one of the high pressure turbine, the low pressure turbine, the power turbine and the low pressure side of the recuperator; and if the temperature of the gas entering the at least one of the high pressure turbine, low pressure turbine, power turbine, and low pressure side of the recuperator, exceeds a predetermined maximum temperature, mixing cooler gas with the gas the temperature of which has exceeded the predetermined maximum temperature, to reduce the temperature of the gas before it enters the at least one of the high pressure turbine, low pressure turbine, power turbine and low pressure side of the recuperator.
When the reactor and the power conversion unit are connected together in a closed loop power generation circuit having a high temperature section and a low temperature section, the source of the cooler gas may be the low temperature section of the power generation circuit, the method then including feeding the cooler gas from the low temperature section of the power generation circuit to a position in the high temperature section of the circuit upstream of the at least one of the high pressure turbine, low pressure turbine, power turbine and low pressure side of the recuperator.
The method may include regulating the flow of gas from the low temperature section of the circuit to the high temperature section of the circuit by means of at least one coolant valve.
According to another aspect of the invention there is provided a nuclear power plant which includes a high temperature gas cooled reactor and a power conversion unit connected together with the reactor in a closed loop power generation circuit; temperature sensing means for sensing the temperature of a gas entering at least one component of the power generation circuit; at least one coolant feed line leading from a source of coolant gas to a position upstream of the at least one component; and a coolant valve mounted in the coolant feed line and arranged to regulate the flow of coolant gas through the coolant feed line in response to signals received from the temperature sensing means thereby to permit the temperature of the gas entering the at least one component to be regulated.
The power conversion unit may include a high pressure turbine, a low pressure turbine, a power turbine, a counterflow recuperator having a high pressure and a low pressure side, each side having an inlet and an outlet, a low pressure compressor to which the low pressure turbine is drivingly connected, a high pressure compressor to which the high pressure turbine is drivingly connected, a pre-cooler positioned in series upstream of the low pressure compressor and an intercooler positioned between the low pressure compressor and the high pressure compressor, the power generation circuit having a high temperature section defined on the reactor side of the recuperator and a low temperature section defined on the other side of the recuperator, the plant including temperature sensing means for sensing the temperature of gas entering at least one of the high pressure turbine, low pressure turbine, power turbine and low pressure side of the recuperator; at least one coolant feedline extending from the low temperature section of the circuit to a position upstream of the at least one of the high pressure turbine, low pressure turbine, power turbine and low pressure side of the recuperator; and a coolant valve mounted in the coolant feedline and arranged to regulate the flow of gas through the coolant feed line from the low temperature section of the circuit to the high temperature section of the circuit in response to a signal received from the temperature sensing means.
More particularly, the reactor typically has an outlet which is connected to an inlet of the high pressure turbine, an outlet of the high pressure turbine being connected to an inlet of the low pressure turbine, an outlet of the low pressure turbine being connected to an inlet of the power turbine, an outlet of the power turbine beingconnected to an inlet of the low pressure side of the recuperator, an outlet of the low pressure side of the recuperator being connected via the pre-coolerto the inlet of the low pressure compressor, an outlet of the low pressure compressor being connected via the intercooler to an inlet of the high pressure compressor, an outlet of the high pressure compressor being connected to an inlet of the high pressure side of the recuperator and an outlet of the high pressure side of the recuperator being connected to an inlet of the reactor.
A temperature sensing means, a coolant feedline and a coolant valve may be provided in respect of each of the high pressure turbine, the low pressure turbine, the power turbine and the inlet on the low pressure side of the recuperator to regulate the temperature of gas being fed thereto. The coolant feedlines may each have an inlet which is connected to the low temperature section of the power generation circuit between the outlet of the low pressure compressor and the inlet of the high pressure side of the recuperator and an outlet which is connected to the high temperature section of the power generation circuit at a position upstream of the associated high pressure turbine, low pressure turbine, power turbine and inlet of the low pressure side of the recuperator, as the case may be.
The power generation circuit may make use of a direct closed Brayton cycle as the thermodynamic conversion cycle.
The reactor is typically of the pebble bed type having a core which includes a plurality of spherical fuel elements or pebbles.
The Brayton cycle typically has a high temperature section and a lopw temperature section corresponding to the high temperature section and low temperature section respectively, of the power generation circuit. Typically, the transitions between the high temperature section and low temperature section occur within the recuperator.
To facilitate control of the plant, a recirculation valve configuration and associated control system are designed to address the requirements of being able to operate under various load conditions and to accommodate abrupt loss of load with the minimum impact.
The Inventor believes that the invention will find application particularly when mass flow through the reactor core is reduced resulting in a decrease in fluidic power. This can occur when the recirculation valve configuration is opened in order to compensate for a reduction in power demand. As a result, the power delivered by the power turbine will decrease due to the bigger fraction of available power being consumed by the compressors as well as the decreased efficiency of the power turbine owing to the lower mass flow therethrough. As a result, the gas temperature entering the high pressure turbine, low pressure turbine, power turbine and low pressure side of the recuperator tend to increase. This is due to the fact that the reactor outlet temperature remains the same, but less heat is removed by the high pressure turbine, low pressure turbine and power turbine. This increase in temperature can be compensated for making use of the coolant valves as described above.
In addition, during decay heat removal, flow of helium is achieved by a start-up blower system. However, the start-up blower system delivers relatively lower flow rate than the compressors and as a result, the possibility of the temperature of the gas entering the turbines or recuperator increasing exists. Once again, the coolant valves can be used in the manner described above to regulate the temperature of gas entering the various components.
The invention will now be described, by way of example, with reference to the accompanying diagrammatic drawing which shows a schematic representation of part of a nuclear power plant in accordance with the invention.
In the drawing, reference numeral 10 refers generally to part of a nuclear power plant in accordance with the invention. The nuclear power plant 10 includes a closed loop power generation circuit, generally indicated by reference numeral 1 2. The power generation circuit 12 includes a nuclear reactor 14 and a power conversion unit, generally indicated by reference numeral 1 6.
The power conversion unit 1 6 includes a high pressure turbine 1 8, a low pressure turbine 20, a power turbine 22, a counterflow recuperator 24, a pre-cooler 26, a low pressure compressor 28, an intercooler 30 and a high pressure compressor 32.
The reactor 14 is a high temperature helium cooled pebble bed reactor making use of spherical fuel elements. The reactor 14 has an inlet 14.1 and an outlet 14.2.
The high pressure turbine 1 8 is drivingly connected to the high pressure compressor 32 and has an upstream side or inlet 18.1 and a downstream side or outlet 1 8.2, the inlet 1 8.1 being connected to the outlet 14.2 of the reactor 14.
The low pressure turbine 20 is drivingly connected to the low pressure compressor 28 and has an upstream side or inlet 20.1 and a downstream side or outlet 20.2. The inlet 20.1 is connected to the outlet 18.2 of the high pressure turbine 18.
The nuclear power plant 10 includes a generator, generally indicated by reference numeral 34 to which the power turbine 22 is drivingly connected. The power turbine 22 includes an upstream side or inlet 22.1 and a downstream side or outlet 22.2. The inlet 22.1 of the power turbine 22 is connected to the outlet 20.2 of the low pressure turbine 20.
The recuperator 24 has a low pressure side 36 and a high pressure side 38. The low pressure side of the recuperator 36 has an inlet 36.1 and an outlet 36.2. The inlet 36.1 of the low pressure side is connected to the outlet 22.2 of the power turbine 22.
The pre-cooler 26 is a helium to water heat exchanger and includes a helium inlet 26.1 and a helium outlet 26.2. The inlet 26.1 of the pre-cooler 26 is connected to the outlet 36.2 of the low pressure side 36 of the recuperator 24.
The low pressure compressor 28 has an upstream side or inlet 28.1 and a downstream side or outlet 28.2. The inlet 28.1 of the low pressure compressor 28 is connected to the helium outlet 26.2 of the pre-cooler 26.
The intercooler 30 is a helium to water heat exchanger and includes a helium inlet 30.1 and a helium outlet 30.2. The helium inlet 30.1 is connected to the outlet 28.2 of the low pressure compressor 28.
The high pressure compressor 32 includes an upstream side or inlet 32.1 and a downstream side or outlet 32.2. The inlet 32.1 of the high pressure compressor 32 is connected to the helium outlet 30.2 of the intercooler 30. The outlet 32.2 of the high pressure compressor 32 is connected to an inlet 38.1 of high pressure side of the recuperator 24. An outlet 38.2 of the high pressure side of the recuperator 24 is connected to the inlet 14.1 of the reactor 14. The nuclear power plant 10 includes a start-up blower system, generally indicated by reference numeral 40, connected between the outlet 36.2 of the low pressure side 36 of the recuperator 24 and the inlet 26.1 of the pre-cooler 26.
The start-up blower system 40 includes a normally open start-up system in line valve 42 which is connected in line between the outlet 36.2 of the low pressure side of the recuperator and the inlet 26.1 of the pre-cooler 26.
A low pressure compressor recirculation line 48 extends from a position between the outlet or downstream side 28.2 of the low pressure compressor 28 and the inlet 30.1 of the intercooler 30 to a position between the start-up blower system 40 and the inlet 26.1 of the pre- cooler 26. A normally closed low pressure recirculation valve arrangement 50 is mounted in the low pressure compressor recirculation line 48.
A high pressure compressor recirculation line 52 extends from a position between the outlet or downstream side of 32.2 of the high pressure compressor and the inlet 38.1 of the high pressure side 38 of the recuperator 24 to a position between the outlet or downstream side 28.2 of the low pressure compressor 28 and the inlet 30.1 of the intercooler 30. A normally closed high pressure recirculation valve arrangement 53 is mounted in the high pressure compressor recirculation line 52.
The power generation circuit 12 hence has a high temperature section, generally indicated by reference numeral 60 which is on the reactor side of the recuperator 36 and a low temperature section, generally indicated by reference numeral 62 which is on the other side of the recuperator 36. The transitions between the high temperature section 60 and the low temperature section 62 typically occur at the recuperator 36.
The plant 10 includes four coolant feed lines 64, 66, 68, 70 in each of which a coolant valve 72, 74, 76, 78, respectively, is mounted.
In the embodiment shown, the coolant feed lines 64, 66, 68, 70 extend from a position between the outlet 32.2 of the high pressure compressor 32 and the inlet 38.1 of the low pressure side 38 of the recuperator 24 to positions upstream of the high pressure turbine 18, low pressure turbine 20, power turbine 22 and low pressure side 36 of the recuperator 24, respectively. The coolant feed lines could in fact lead from any position between the outlet 28.2 of the low pressure compressor and the inlet 38.1 .
The plant 10 further includes temperature sensing means in the form of sensors 73, 75, 77, 79 for sensing the temperature of helium entering the high pressure turbine 18, low pressure turbine 20, power turbine 22 and low pressure side 36 of the recuperator 24, respectively. The temperature sensor 73 associated with the high pressure turbine is operatively connected to the coolant valve 72 to control the operation thereof. Similarly, the temperature sensors 75, 77, 79 associated with the low pressure turbine 20, power turbine 22 and low pressure side 36 of the recuperator 26 are operatively connected to the coolant valves 74, 76, 78, respectively. The plant 10 which makes use of a Brayton cycle as the thermodynamic conversion cycle is designed for operation under various load conditions. The load conditions might vary from ordinary and frequent load variations, to a complete loss of load. The focus during these changes in load will be on keeping the plant synchronized with and connected to an electrical distribution grid, whilst keeping the Brayton cycle self-sustaining. This is desirable to ensure that the plant 10 can react promptly to demand variations. During normal operation, regular changes in required delivery are foreseen, and the plant is therefore designed to be able to accommodate the load changes with minimum impact on plant operation. The plant 10 is furthermore designed to be capable of accommodating an abrupt loss of load whilst again still remaining synchronized and connected to the grid, with the Brayton cycle continuing to be self-sustaining. This will typically result in the case of the power levels approaching zero with minimal or no delivery to the grid.
To this end the recirculation valve arrangements 50, 53 can be used to regulate the power output of the plant 10.
Accordingly, if there is a reduction in power demand, then one or both of the recirculation valve arrangement 50, 53 is opened. This results in reduced mass flow through the reactor core and therefore a decrease in fluidic power. The power delivered by the power turbine 22 will decrease due to the bigger fraction of available power being consumed by the turbo machines 28, 32 as well as the decreased efficiency of the power turbine 22 owing to the lower mass flow therethrough. In this case, the electrical power generated can be controlled and adjusted relatively quickly. However, when the power generated is reduced making use of the recirculation valves, the gas temperature entering the high pressure turbine 18, low pressure turbine 20, power turbine 22 and low pressure side 36 of the recuperator 24 tend to increase. This is due to the fact that the reactor outlet temperature remains the same, but less heat is removed by the high pressure turbine 18, low pressure turbine 20 and power turbine 22.
However, in order to avoid possible damage to the turbines 18, 20, 22 or the recuperator 24, it is desirable that the maximum temperature of gas entering these components not exceed a predetermined maximum temperature (eg of the order of 600°C in the case of the recuperator 24). Accordingly, the temperature sensors73, 75, 77, 79 associated with each of these components sense the temperature of gas entering the associated components. Should the temperature of the gas exceed a predetermined maximum temperature, then the associated coolant valve 72, 74, 76, 78 is opened thereby to feed cooler helium from the low temperature section 62 to the high temperature section 60 which is mixed with the high temperature helium prior to its introduction into the turbine 18, 20, 22 or the recuperator 24, as the case may be.
In this way, the temperature of the gas entering the components can be maintained at a temperature below the predetermined maximum temperature thereby avoiding overheating and possible damage of the components on the high temperature section of the power generation circuit 12.
A secondary advantage associated with the opening of the coolant valves 72, 74, 76, 78 is that they will augment the compressor recirculation valve power control process, as the coolant valves will in fact be acting as additional recirculation valves.
In addition to being used during normal operation of the plant, in the manner described above, the coolant valves 72, 74, 76, 78 can also be used during the process of decay heat removal. During decay heat removal the start-up blower system 40 is operational and is used to remove heat from the core. The start-up blower system 40 delivers relatively lower flow rates than the compressors 28, 33 and therefor the same situation as described above, ie the possibility of the temperature of the gas entering the turbines 18, 20, 22 or recuperator 24 exceeding the predetermined maximum temperature exists. Once again, the coolant valves 72, 74, 76, 78 can be used in the manner described above to regulate the temperature of gas entering the various components by mixing helium from the low temperature section of the power generation circuit with the high temperature gas stream.
It will be appreciated that, although the coolant valves 72, 74, 76, 78 have been described as single valves, they may in fact each comprise a valve set. The valve sets could include combinations of differently sized control valves or any other arrangement. Further, the control of the valves may be such that the valves can be used separately or in any required combination.
The Inventor believes that the invention will permit the plant to accommodate variations in load demand quickly and safely. It will also enable the removal of decay heat from the reactor, without causing damage to equipment in the high temperature section by exposure to temperatures above the maximum desired temperatures.

Claims

CLAIMS:
1 . In a nuclear power plant which uses gas as the working fluid, there is provided a method of operating the nuclear power plant, which includes the steps of monitoring the temperature of the gas entering at least one of the components of the power plant; and if the temperature of the gas entering the at least one component of the power plant exceeds a predetermined maximum temperature, mixing cooler gas with the gas whose temperature has exceeded the predetermined maximum temperature, to reduce the temperature of the gas before it enters the at least one component.
2. A method as claimed in claim 1 , which, when the nuclear power plant includes a high temperature gas cooled reactor and a power conversion unit which is connected together with the reactor in a closed loop and includes a high pressure turbine, a low pressure turbine, a power turbine, a counterflow recuperator having a high pressure side and a low pressure side, each side having an inlet and an outlet, a low pressure compressor to which the low pressure turbine is drivingly connected, and a high pressure compressor to which the high pressure turbine is drivingly connected, includes the steps of monitoring the temperature of the gas entering at least one of the high pressure turbine, the low pressure turbine, the power turbine and the low pressure side of the recuperator; and if the temperature of the gas entering the at least one of the high pressure turbine, low pressure turbine, power turbine, and low pressure side of the recuperator, exceeds a predetermined maximum temperature, mixing cooler gas with the gas the temperature of which has exceeded the predetermined maximum temperature, to reduce the temperature of the gas before it enters the at least one of the high pressure turbine, low pressure turbine, power turbine and low pressure side of the recuperator.
3. A method as claimed in claim 2, which, when the reactor and the power conversion unit are connected together in a closed loop power generation circuit having a high temperature section and a low temperature section, includes feeding the cooler gas from the low temperature section of the power generation circuit to a position in the high temperature section of the circuit upstream of the at least one of the high pressure turbine, low pressure turbine, power turbine and low pressure side of the recuperator.
4. A method as claimed in claim 3, which includes regulating the flow of gas from the low temperature section of the circuit to the high temperature section of the circuit by means of at least one coolant valve.
5. A nuclear power plant which includes a high temperature gas cooled reactor and a power conversion unit connected together with the reactor in a closed loop power generation circuit; temperature sensing means for sensing the temperature of a gas entering at least one component of the power generation circuit; at least one coolant feed line leading from a source of coolant gas to a position upstream of the at least one component; and a coolant valve mounted in the coolant feed line and arranged to regulate the flow of coolant gas through the coolant feed line in response to signals received from the temperature sensing means thereby to permit the temperature of the gas entering the at least one component to be regulated.
6. A nuclear power plant as claimed in claim 5, in which the power conversion unit includes a high pressure turbine, a low pressure turbine, a power turbine, a counterflow recuperator having a high pressure and a low pressure side, each side having an inlet and an outlet, a low pressure compressor to which the low pressure turbine is drivingly connected, a high pressure compressor to which the high pressure turbine is drivingly connected, a pre-cooler positioned in series upstream of the low pressure compressor and an intercooler positioned between the low pressure compressor and high pressure compressor, the power generation circuit having a high temperature section defined on the reactor side of the recuperator and a low temperature section defined on the other side of the recuperator, the plant including temperature sensing means for sensing the temperature of gas entering at least one of the high pressure turbine, low pressure turbine, power turbine and low pressure side of the recuperator; at least one coolant feedline extending from the low temperature section of the circuit to a position upstream of the at least one of the high pressure turbine, low pressure turbine, power turbine and low pressure side of the recuperator; and a coolant valve mounted in the coolant feedline and arranged to regulate the flow of gas through the coolant feed line from the low temperature section of the circuit to the high temperature section of the circuit in response to a signal received from the temperature sensing means.
7. A nuclear power plant as claimed in claim 6, in which a temperature sensing means, a coolant feedline and a coolant valve are provided in respect of each of the high pressure turbine, the low pressure turbine, the power turbine and the inlet on the low pressure side of the recuperator to regulate the temperature of gas being fed thereto.
8. A nuclear power plant as claimed in claim 7, in which the coolant feedlines each have an inlet which is connected to the low temperature section of the power generation circuit between the outlet of the low pressure compressor and the inlet of the high pressure side of the recuperator and an outlet which is connected to the high temperature section of the power generator circuit at a position upstream of the associated high pressure turbine, low pressure turbine, power turbine and inlet of the low pressure side of the recuperator, as the case may be.
9. A method of operating a nuclear power plant as claimed in claim 1 , substantially as described and illustrated herein.
1 0. A nuclear power plant as claimed in claim 5, substantially as described and illustrated herein.
1 1 . A new method or plant substantially as described herein.
PCT/IB2002/000979 2001-03-30 2002-03-28 Nuclear power plant and method of operating the same WO2002080190A1 (en)

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US11846197B2 (en) 2020-08-12 2023-12-19 Malta Inc. Pumped heat energy storage system with charge cycle thermal integration
US11885244B2 (en) 2020-08-12 2024-01-30 Malta Inc. Pumped heat energy storage system with electric heating integration
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US11927130B2 (en) 2016-12-28 2024-03-12 Malta Inc. Pump control of closed cycle power generation system
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