CN113756891A - Integrated villiaumite cooling high-temperature reactor power system for ships - Google Patents
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- CN113756891A CN113756891A CN202111005721.8A CN202111005721A CN113756891A CN 113756891 A CN113756891 A CN 113756891A CN 202111005721 A CN202111005721 A CN 202111005721A CN 113756891 A CN113756891 A CN 113756891A
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
- F01K13/00—General layout or general methods of operation of complete plants
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
- F01K21/00—Steam engine plants not otherwise provided for
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
- F01K25/00—Plants or engines characterised by use of special working fluids, not otherwise provided for; Plants operating in closed cycles and not otherwise provided for
- F01K25/08—Plants or engines characterised by use of special working fluids, not otherwise provided for; Plants operating in closed cycles and not otherwise provided for using special vapours
- F01K25/10—Plants or engines characterised by use of special working fluids, not otherwise provided for; Plants operating in closed cycles and not otherwise provided for using special vapours the vapours being cold, e.g. ammonia, carbon dioxide, ether
- F01K25/103—Carbon dioxide
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
- F01K7/00—Steam engine plants characterised by the use of specific types of engine; Plants or engines characterised by their use of special steam systems, cycles or processes; Control means specially adapted for such systems, cycles or processes; Use of withdrawn or exhaust steam for feed-water heating
- F01K7/32—Steam engine plants characterised by the use of specific types of engine; Plants or engines characterised by their use of special steam systems, cycles or processes; Control means specially adapted for such systems, cycles or processes; Use of withdrawn or exhaust steam for feed-water heating the engines using steam of critical or overcritical pressure
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
- G21C15/12—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment vessel
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/28—Selection of specific coolants ; Additions to the reactor coolants, e.g. against moderator corrosion
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/02—Details
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- Y—GENERAL 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The invention discloses an integrated villaumite cooling high-temperature reactor power system, which comprises a reactor body system, a Brayton power circulation system and a power system circulation loop formed by other connecting equipment such as pipelines among the systems; the reactor body system is used as a heat source of a power system, and a Brayton power cycle system performs thermal power conversion; all the equipment of the invention can be processed, manufactured, transported and installed in a modularized way; the Brayton power cycle system has the advantages of high thermal efficiency, sufficient power and quick power response, and the thermal efficiency exceeds 48 percent; the invention can not only be well adapted to narrow space on the ship, but also output enough power and flexibly track load change, thereby having reference significance for the development of a new generation of ship nuclear power system.
Description
Technical Field
The invention belongs to the technical field of advanced nuclear power system development and efficient energy conversion, and particularly relates to an integrated villaumite cooling high-temperature reactor power system for ships.
Background
The modularized small-sized villaumite cooling high-temperature reactor has the advantages of high temperature and low pressure, no water cooling and inherent safety, and in addition, because the volume heat capacity of villaumite is equivalent to that of water and is 2.75, 4.49 and 233.5 times of that of liquid lead-bismuth alloy, liquid sodium and helium, more heat can be taken away under the condition of the same volume of coolant, so the modularized small-sized villaumite cooling high-temperature reactor has the outstanding advantages of reducing the volume of a reactor core and ensuring the compact structure; the supercritical carbon dioxide power cycle system has the advantages of outstanding high thermal efficiency, compact structure, flexible control, quick response and the like.
However, the design scheme of the small-sized villiaumite-cooled high-temperature reactor proposed at present is more than the design of a reactor core module, and the design, analysis, optimization and selection of reactor structures, materials and various related devices and the combination research of the reactor structures, the materials and the related devices and the supercritical carbon dioxide power cycle system are not sufficient.
Disclosure of Invention
In order to overcome the problems in the prior art, the invention discloses an integrated villaumite cooling high-temperature reactor power system for ships, which combines a modular small villaumite cooling high-temperature reactor with a supercritical carbon dioxide power circulation system, can well adapt to narrow space on the ships, can output enough power and flexibly track load change, and provides a basis for system optimization and detailed design.
In order to achieve the purpose, the invention adopts the following technical scheme:
the integrated villaumite-cooled high-temperature reactor power system comprises a reactor body system 1 and a Brayton power cycle system 2;
the reactor body system 1 is used as a heat source of an integrated villaumite cooling high-temperature reactor power system for ships and warships and comprises a reactor core active area 1-1, a reactor vessel 1-2, a reactor core axial reflecting layer 1-3, a reactor core radial reflecting layer 1-4, a first axial flow pump 1-5-1, a second axial flow pump 1-5-2, a first main heat exchanger 1-6-1, a second main heat exchanger 1-6-2, a control rod and a driving mechanism 1-7 thereof; wherein an outlet of a reactor core active area 1-1 is connected with inlets of a first main heat exchanger 1-6-1 and a second main heat exchanger 1-6-2, outlets of the first main heat exchanger 1-6-1 and the second main heat exchanger 1-6-2 are respectively connected with inlets of a first axial flow pump 1-5-1 and a second axial flow pump 1-5-2, and outlets of the first axial flow pump 1-5-1 and the second axial flow pump 1-5-2 are connected with an inlet of the reactor core active area 1-1; the reactor core axial reflecting layer 1-3 and the reactor core radial reflecting layer 1-4 are respectively coated in the axial direction and the radial direction of the reactor core active area 1-1, a control rod and a drive mechanism 1-7 thereof are inserted into the reactor core active area 1-1, and all the structures and components are positioned in the reactor vessel 1-2;
the working flow of the reactor body system 1 is as follows: when the reactor body system 1 normally operates, coolant is driven by the first axial flow pump 1-5-1 and the second axial flow pump 1-5-2, enters the reactor core from the bottom of the axial reflecting layer 1-3 of the reactor core, flows upwards through the active area 1-1 of the reactor core to absorb heat, is deflected downwards, releases heat to the Brayton power cycle system 2 through the first main heat exchanger 1-6-1 and the second main heat exchanger 1-6-2, and finally enters the first axial flow pump 1-5-1 and the second axial flow pump 1-5-2 to be pressurized so as to complete the circulation of the coolant in the reactor core;
the Brayton power cycle system 2 is used as an energy conversion module of an integrated villaumite cooling high-temperature reactor power system for ships and warships, and comprises a first main heat regenerator 2-1-1, a second main heat regenerator 2-1-2, a first main flow merging valve 2-2-1, a second main flow merging valve 2-2-2, a first auxiliary heat regenerator 2-3-1, a second auxiliary heat regenerator 2-3-2, a first main flow dividing valve 2-4-1, a second main flow dividing valve 2-4-2, a cooler 2-5, a turbine 2-6, an auxiliary compressor 2-7, a main compressor 2-8, a motor 2-9 and a generator 2-10; wherein, a first inlet and a second inlet of a turbine 2-6 are respectively connected with cold side outlets of a first main heat exchanger 1-6-1 and a second main heat exchanger 1-6-2, a first outlet and a second outlet are respectively connected with hot side inlets of a first main regenerator 2-1-1 and a second main regenerator 2-1-2, hot side outlets of the first main regenerator 2-1-1 and the second main regenerator 2-1-2 are respectively connected with hot side inlets of a first auxiliary regenerator 2-3-1 and a second auxiliary regenerator 2-3-2, hot side outlets of the first auxiliary regenerator 2-3-1 and the second auxiliary regenerator 2-3-2 are respectively connected with inlets of a first main flow dividing valve 2-4-1 and a second main flow dividing valve 2-4-2, first outlets of the first and second main branch valves 2-4-1 and 2-4-2 are connected to first and second inlets of the auxiliary compressor 2-7, respectively, first and second outlets of the auxiliary compressor 2-7 are connected to second inlets of the first and second main merge valves 2-2-1 and 2-2, respectively, second outlets of the first and second main branch valves 2-4-1 and 2-4-2 are connected to hot side first and second inlets of the cooler 2-5, first and second outlets of the cooler 2-5 are connected to first and second inlets of the main compressor 2-8, respectively, first and second outlets of the main compressor 2-8 are connected to cold side inlets of the first and second auxiliary heat regenerators 2-3-1 and 2-3-2, respectively The cold side outlets of the first auxiliary heat regenerator 2-3-1 and the second auxiliary heat regenerator 2-3-2 are respectively connected with the first inlets of the first main confluence valve 2-2-1 and the second main confluence valve 2-2-2, the outlets of the first main confluence valve 2-2-1 and the second main confluence valve 2-2-2 are respectively connected with the cold side inlets of the first main heat regenerator 2-1-1 and the second main heat regenerator 2-1-2, and the cold side outlets of the first main heat regenerator 2-1-1 and the second main heat regenerator 2-1-2 are respectively connected with the cold side inlets of the first main heat exchanger 1-6-1 and the second main heat exchanger 1-6-2;
the working process of the Brayton power cycle system 2 is as follows: the circulating working medium absorbs heat from the cold sides of the first main heat exchanger 1-6-1 and the second main heat exchanger 1-6-2 which are connected in parallel, then enters the turbine 2-6 through two parallel inlets to do work, simultaneously drives the generator 2-10 to generate electricity, then leaves the turbine 2-6 through two parallel outlets, enters the hot sides of the first main heat regenerator 2-1-1 and the second main heat regenerator 2-1-2 which are connected in parallel, releases heat from the hot sides of the first auxiliary heat regenerator 2-3-1 and the second auxiliary heat regenerator 2-3-2 which are connected in parallel, and is shunted through the first main shunt valve 2-4-1 and the second main shunt valve 2-4-2 which are connected in parallel: one part of the mixed gas flows out from a first outlet of the first main flow dividing valve 2-4-1 and a first outlet of the second main flow dividing valve 2-4-2, is connected in parallel to enter an auxiliary compressor 2-7 driven by a motor 2-9 for compression, then leaves the auxiliary compressor 2-7 through two parallel outlets, and enters a second inlet of the first main flow merging valve 2-2-1 and the second main flow merging valve 2-2-2 which are connected in parallel; the other part of the heat flows out from the second outlets of the first main flow dividing valve 2-4-1 and the second main flow dividing valve 2-4-2, enters the high-temperature side of the cooler 2-5 through the parallel inlets to release heat, then enters the main compressor 2-8 driven by the motor 2-9 through the parallel outlets to be compressed, then leaves the main compressor 2-8 through the two parallel outlets, enters the cold sides of the first auxiliary heat regenerator 2-3-1 and the second auxiliary heat regenerator 2-3-2 which are connected in parallel to absorb heat, and finally enters the first inlets of the first main flow combining valve 2-2-1 and the second main flow combining valve 2-2-2 which are connected in parallel; after the two parts are converged, the two parts flow out from outlets of a first main flow merging valve 2-2-1 and a second main flow merging valve 2-2-2 which are connected in parallel, enter cold sides of a first main heat regenerator 2-1-1 and a second main heat regenerator 2-1-2 which are connected in parallel to absorb heat, and finally enter cold sides of a first main heat exchanger 1-6-1 and a second main heat exchanger 1-6-2 which are connected in parallel to absorb heat, so that power circulation is completed.
The coolant of the reactor body system 1 adopts LiF-BeF2Molten salt, the inlet temperature of the reactor core is 650 ℃, the outlet temperature is 700 ℃, the total thermal power is 125MW, the inlet temperature and the outlet temperature are allowed to have deviation of plus or minus 50 ℃ in actual operation, and the total thermal power is allowed to have deviation of plus or minus 25 MW.
The reactor core active area 1-1 of the reactor body system 1 adopts a spiral cross-shaped fuel element, the pellet material is uranium-zirconium alloy, and the enrichment degree is 19.75%; the cladding material is hastelloy; the single-component fuel rods are arranged in a triangular shape, and the components are arranged in a triangular shape.
The reactor vessel 1-2 of the reactor body system 1 has a diameter of less than 3.5 meters and a height of less than 3 meters. The first main heat exchanger 1-6-1 and the second main heat exchanger 1-6-2 of the reactor body system 1 are printed circuit board type heat exchangers.
In the control rods and the driving mechanisms 1-7 of the reactor body system 1, 7 control rods are arranged in a single component, and the material of the control rods is boron carbide.
The working medium of the Brayton power cycle system 2 is carbon dioxide, and the lowest temperature and pressure of the cycle is higher than the critical temperature and pressure thereof; the highest circulating pressure in normal operation is not more than 20MPa, and the highest circulating pressure in special working conditions is not more than 25 MPa; the cycle thermal efficiency is over 48 percent.
The Brayton power cycle system 2 exchanges heat with the reactor body system 1 through a first main heat exchanger 1-6-1 and a second main heat exchanger 1-6-2 which are connected in parallel; the loops of all the heat exchangers of the Brayton power cycle system are connected in parallel, and the Brayton power cycle system has redundancy characteristics.
The first main heat regenerator 2-1-1, the second main heat regenerator 2-1-2, the first auxiliary heat regenerator 2-3-1, the second auxiliary heat regenerator 2-3-2 and the cooler 2-5 of the Brayton power cycle system 2 are all printed circuit board heat exchangers, wherein a working medium at the cold side of the cooler 2-5 is filtered seawater.
The turbines 2-6, the auxiliary compressors 2-7 and the main compressors 2-8 of the Brayton power cycle system 2 adopt an off-axis arrangement mode of coaxial line positions, so that the power can be flexibly adjusted; the total electric power is greater than 50 MW.
Compared with the prior art, the invention has the following advantages:
1. the combination of the modularized small-sized villaumite cooling high-temperature reactor and the supercritical carbon dioxide power cycle system can well adapt to narrow space on a ship, can output enough power and can flexibly track load change.
2. The reactor adopts LiF-BeF2The molten salt is used as a coolant and has the advantages of high temperature, low pressure, no water cooling and compact volume. LiF-BeF2The boiling point of the molten salt is over 1000 ℃, the freezing point is lower than 500 ℃, and the molten salt is far away from the saturation point under normal pressure, so that the heat transfer deterioration risk of high-strength phase change can be effectively reduced; the volume heat capacity of the reactor is equivalent to that of water, is higher than that of liquid lead-bismuth alloy, liquid sodium and helium, can carry away more heat under the same coolant volume, and is beneficial to reducing the volume of the reactor.
3. The safety and potential economy are high, and the arrangement is simplified. The reactor fuel element adopts a spiral cross type, and the structure of the reactor fuel element can enhance the coolant turbulences among the channels so as to strengthen the heat exchange, and can effectively reduce the hot spot on the surface of the cladding; the fuel pellet is made of uranium zirconium alloy material, has higher thermal conductivity compared with ceramic fuel, can effectively reduce the peak temperature of the pellet, is beneficial to thermal engineering safety, and can also allow the power density to be improved, thereby improving the economy; in addition, the self-positioning function among the spiral cross-shaped fuel elements also saves the use of a positioning grid, and simplifies the core arrangement.
4. Miniaturization and modularization technology. Each device of the invention can be processed, manufactured, transported and installed in a modular way. The adopted heat exchangers are all printed circuit board type heat exchangers, and have the advantages of compact structure, large heat transfer area, high structural strength, easiness in modular design and manufacture and the like;
5. high thermal efficiency, sufficient power and rapid power response. Compared with the traditional Rankine cycle, the supercritical carbon dioxide Brayton power cycle system has the advantages of outstanding high thermal efficiency, compact structure, flexible control, quick response and the like, and is suitable for power conversion of hundred MWe magnitude. The thermal efficiency of the Brayton power cycle system of the invention is over 48% by design calculation.
Drawings
FIG. 1 is a schematic diagram of an integrated villaumite cooling high-temperature reactor power system for ships. In the drawings:
1: a reactor body system;
1-1: a core active area; 1-2: a reactor vessel; 1-3: a reactor core axial reflecting layer; 1-4: a reactor core radial reflecting layer; 1-5-1: a first axial flow pump; 1-5-2: a second axial flow pump; 1-6-1: a first primary heat exchanger; 1-6-2: a second primary heat exchanger; 1-7: control rod and drive mechanism thereof
2: a Brayton power cycle system;
2-1-1: a first primary regenerator; 2-1-2: a second primary regenerator; 2-2-1: a first main confluence valve (1 is a first inlet, and 2 is a second inlet); 2-2-2: a second main confluence valve (1 is a first inlet, and 2 is a second inlet); 2-3-1: a first auxiliary heat regenerator; 2-3-2: a second auxiliary heat regenerator; 2-4-1: a first main diverter valve (1 being a first outlet, 2 being a second outlet); 2-4-2: a second main diverter valve (1 is a first outlet, 2 is a second outlet); 2-5: a cooler (the upper side 1 is a first outlet at a hot side, the upper side 2 is a second outlet at the hot side, the lower side 1 is a first inlet at the hot side, and the lower side 2 is a second inlet at the hot side); 2-6: a turbine (left side 1 is a first inlet, left side 2 is a second inlet; right side 1 is a first outlet, and right side 2 is a second outlet); 2-7: an auxiliary compressor (the left side 1 is a first outlet, the left side 2 is a second outlet, the right side 1 is a first inlet, and the right side 2 is a second inlet); 2-8: a main compressor (the left side 1 is a first outlet, the left side 2 is a second outlet, the right side 1 is a first inlet, and the right side 2 is a second inlet); 2-9: an electric motor; 2-10: an electric generator.
Detailed Description
The invention provides an integrated villaumite cooling high-temperature reactor power system for ships, which is further described in detail with reference to the attached drawing 1.
The integrated villaumite-cooled high-temperature reactor power system comprises a reactor body system 1 and a Brayton power cycle system 2;
the reactor body system 1 is used as a heat source of an integrated villaumite cooling high-temperature reactor power system for ships, and mainly comprises a reactor core active area 1-1, a reactor vessel 1-2, a reactor core axial reflecting layer 1-3, a reactor core radial reflecting layer 1-4, a first axial flow pump 1-5-1, a second axial flow pump 1-5-2, a first main heat exchanger 1-6-1, a second main heat exchanger 1-6-2, a control rod and a driving mechanism 1-7 thereof.
The Brayton power cycle system 2 is used as an energy conversion module of an integrated villaumite cooling high-temperature reactor power system for ships, and the main equipment of the Brayton power cycle system comprises a first main heat regenerator 2-1-1, a second main heat regenerator 2-1-2, a first main flow merging valve 2-2-1, a second main flow merging valve 2-2-2, a first auxiliary heat regenerator 2-3-1, a second auxiliary heat regenerator 2-3-2, a first main flow dividing valve 2-4-1, a second main flow dividing valve 2-4-2, a cooler 2-5, a turbine 2-6, an auxiliary compressor 2-7, a main compressor 2-8, a motor 2-9 and a generator 2-10; wherein, a first inlet and a second inlet of a turbine 2-6 are respectively connected with cold side outlets of a first main heat exchanger 1-6-1 and a second main heat exchanger 1-6-2, a first outlet and a second outlet are respectively connected with hot side inlets of a first main regenerator 2-1-1 and a second main regenerator 2-1-2, hot side outlets of the first main regenerator 2-1-1 and the second main regenerator 2-1-2 are respectively connected with hot side inlets of a first auxiliary regenerator 2-3-1 and a second auxiliary regenerator 2-3-2, hot side outlets of the first auxiliary regenerator 2-3-1 and the second auxiliary regenerator 2-3-2 are respectively connected with inlets of a first main flow dividing valve 2-4-1 and a second main flow dividing valve 2-4-2, first outlets of the first and second main branch valves 2-4-1 and 2-4-2 are connected to first and second inlets of the auxiliary compressor 2-7, respectively, first and second outlets of the auxiliary compressor 2-7 are connected to second inlets of the first and second main merge valves 2-2-1 and 2-2, respectively, second outlets of the first and second main branch valves 2-4-1 and 2-4-2 are connected to hot side first and second inlets of the cooler 2-5, first and second outlets of the cooler 2-5 are connected to first and second inlets of the main compressor 2-8, respectively, first and second outlets of the main compressor 2-8 are connected to cold side inlets of the first and second auxiliary heat regenerators 2-3-1 and 2-3-2, respectively The cold side outlets of the first auxiliary heat regenerator 2-3-1 and the second auxiliary heat regenerator 2-3-2 are respectively connected with the first inlets of the first main confluence valve 2-2-1 and the second main confluence valve 2-2-2, the outlets of the first main confluence valve 2-2-1 and the second main confluence valve 2-2-2 are respectively connected with the cold side inlets of the first main heat regenerator 2-1-1 and the second main heat regenerator 2-1-2, and the cold side outlets of the first main heat regenerator 2-1-1 and the second main heat regenerator 2-1-2 are respectively connected with the cold side inlets of the first main heat exchanger 1-6-1 and the second main heat exchanger 1-6-2.
As a preferred embodiment of the present invention, LiF-BeF is used as the coolant for the reactor body system 12Molten salt, the inlet temperature of the reactor core is 650 ℃, the outlet temperature is 700 ℃, the total thermal power is 125MW, the inlet temperature and the outlet temperature are allowed to have deviation of plus or minus 50 ℃ in actual operation, and the total thermal power is allowed to have deviation of plus or minus 25 MW.
As a preferred embodiment of the invention, a core active area 1-1 of a reactor body system 1 adopts spiral cross-shaped fuel elements, pellet materials are uranium-zirconium alloy, and the enrichment degree is 19.75%; the cladding material is hastelloy; the single-component fuel rods are arranged in a triangular shape, and the components are arranged in a triangular shape.
As a preferred embodiment of the invention, the reactor vessel 1-2 of the reactor body system 1 is less than 3.5 meters in diameter and less than 3 meters in height.
As a preferred embodiment of the invention, the first and second primary heat exchangers 1-6-1, 1-6-2 of the reactor body system 1 are printed circuit board heat exchangers.
In the preferred embodiment of the invention, the control rods of the reactor body system 1 and the driving mechanisms 1 to 7 thereof are arranged in a single assembly, and the material of the control rods is boron carbide.
As the preferred embodiment of the invention, the working medium of the Brayton power cycle system 2 is carbon dioxide, and the lowest temperature and pressure of the cycle is higher than the critical temperature and pressure; the highest circulating pressure in normal operation is not more than 20MPa, and the highest circulating pressure in special working conditions is not more than 25 MPa; the cycle thermal efficiency is over 48 percent.
As a preferred embodiment of the invention, the Brayton power cycle system 2 exchanges heat with the reactor body system 1 through a first main heat exchanger 1-6-1 and a second main heat exchanger 1-6-2 which are connected in parallel; the loops of all the heat exchangers of the Brayton power cycle system are connected in parallel, and the Brayton power cycle system has redundancy characteristics.
As a preferred embodiment of the invention, the first main heat regenerator 2-1-1, the second main heat regenerator 2-1-2, the first auxiliary heat regenerator 2-3-1, the second auxiliary heat regenerator 2-3-2 and the cooler 2-5 of the Brayton power cycle system 2 are all printed circuit plate heat exchangers, wherein the working medium at the cold side of the cooler 2-5 is filtered seawater.
As the preferred embodiment of the invention, the turbines 2-6, the auxiliary compressors 2-7 and the main compressors 2-8 of the Brayton power cycle system 2 adopt the coaxial arrangement mode of coaxial positions, thereby being convenient for flexibly adjusting the power; the total electric power is greater than 50 MW.
The reactor body system 1 has the following working procedures: when the reactor body system 1 normally operates, coolant is driven by the first axial flow pump 1-5-1 and the second axial flow pump 1-5-2, enters the reactor core from the bottom of the axial reflecting layer 1-3 of the reactor core, flows upwards through the active area 1-1 of the reactor core to absorb heat, is deflected downwards, releases heat to the Brayton power cycle system 2 through the first main heat exchanger 1-6-1 and the second main heat exchanger 1-6-2, and finally enters the first axial flow pump 1-5-1 and the second axial flow pump 1-5-2 to be pressurized so as to complete the circulation of the coolant in the reactor core.
The working process of the Brayton power cycle system 2 is as follows: the circulating working medium absorbs heat from the cold sides of the first main heat exchanger 1-6-1 and the second main heat exchanger 1-6-2 which are connected in parallel, enters the turbine 2-6 through two parallel inlets to do work, simultaneously drives the generator 2-10 to generate electricity, then leaves the turbine through two parallel outlets, enters the hot sides of the first main heat regenerator 2-1-1 and the second main heat regenerator 2-1-2 which are connected in parallel, releases heat from the hot sides of the first auxiliary heat regenerator 2-3-1 and the second auxiliary heat regenerator 2-3-2 which are connected in parallel, and is shunted through the first main shunt valve 2-4-1 and the second main shunt valve 2-4-2 which are connected in parallel: one part of the mixed gas flows out from a first outlet of the first main flow dividing valve 2-4-1 and a first outlet of the second main flow dividing valve 2-4-2, is connected in parallel to enter an auxiliary compressor 2-7 driven by a motor 2-9 for compression, then leaves the auxiliary compressor through two parallel outlets and enters a second inlet of the first main flow merging valve 2-2-1 and the second main flow merging valve 2-2-2 which are connected in parallel; the other part of the heat flows out from the second outlets of the first main flow dividing valve 2-4-1 and the second main flow dividing valve 2-4-2, enters the high-temperature side of the cooler 2-5 through the parallel inlets to release heat, then enters the main compressor 2-8 driven by the motor 2-9 through the parallel outlets to be compressed, then leaves the main compressor through the two parallel outlets, enters the cold sides of the first auxiliary heat regenerator 2-3-1 and the second auxiliary heat regenerator 2-3-2 which are connected in parallel to absorb heat, and finally enters the first inlets of the first main flow combining valve 2-2-1 and the second main flow combining valve 2-2-2 which are connected in parallel; after the two parts are converged, the two parts flow out from outlets of a first main flow merging valve 2-2-1 and a second main flow merging valve 2-2-2 which are connected in parallel, enter cold sides of a first main heat regenerator 2-1-1 and a second main heat regenerator 2-1-2 which are connected in parallel to absorb heat, and finally enter cold sides of a first main heat exchanger 1-6-1 and a second main heat exchanger 1-6-2 which are connected in parallel to absorb heat, so that power circulation is completed.
While the invention has been described in further detail with reference to specific preferred embodiments thereof, it will be understood by those skilled in the art that various changes in form and details may be made therein without departing from the spirit and scope of the invention as defined by the appended claims.
Claims (10)
1. Naval vessel is with integration villaumite cooling high temperature heap driving system, its characterized in that: comprises a reactor body system (1) and a Brayton power cycle system (2);
the reactor body system (1) is used as a heat source of an integrated villaumite cooling high-temperature reactor power system for ships and warships and comprises a reactor core active area (1-1), a reactor vessel (1-2), a reactor core axial reflecting layer (1-3), a reactor core radial reflecting layer (1-4), a first axial flow pump (1-5-1), a second axial flow pump (1-5-2), a first main heat exchanger (1-6-1), a second main heat exchanger (1-6-2), a control rod and a driving mechanism (1-7) thereof; wherein an outlet of the reactor core active area (1-1) is connected with inlets of a first main heat exchanger (1-6-1) and a second main heat exchanger (1-6-2), outlets of the first main heat exchanger (1-6-1) and the second main heat exchanger (1-6-2) are respectively connected with inlets of a first axial flow pump (1-5-1) and a second axial flow pump (1-5-2), and outlets of the first axial flow pump (1-5-1) and the second axial flow pump (1-5-2) are connected with an inlet of the reactor core active area (1-1); the reactor core axial reflecting layer (1-3) and the reactor core radial reflecting layer (1-4) are respectively coated in the axial direction and the radial direction of the reactor core active area (1-1), a control rod and a driving mechanism (1-7) thereof are inserted into the reactor core active area (1-1), and all the structures and components are positioned in the reactor vessel (1-2);
the working flow of the reactor body system (1) is as follows: when the reactor body system (1) normally operates, coolant is driven by the first axial flow pump (1-5-1) and the second axial flow pump (1-5-2), enters the reactor core from the bottom of the axial reflecting layer (1-3) of the reactor core, flows upwards through the active area (1-1) of the reactor core to absorb heat, is deflected downwards, releases heat to the Brayton power cycle system (2) through the first main heat exchanger (1-6-1) and the second main heat exchanger (1-6-2), and finally enters the first axial flow pump (1-5-1) and the second axial flow pump (1-5-2) to be pressurized so as to complete the circulation of the coolant in the reactor core; the Brayton power cycle system (2) is used as an energy conversion module of an integrated villaumite cooling high-temperature reactor power system for ships and warships, and comprises a first main heat regenerator (2-1-1), a second main heat regenerator (2-1-2), a first main flow merging valve (2-2-1), a second main flow merging valve (2-2-2), a first auxiliary heat regenerator (2-3-1), a second auxiliary heat regenerator (2-3-2), a first main flow dividing valve (2-4-1), a second main flow dividing valve (2-4-2), a cooler (2-5), a turbine (2-6), an auxiliary compressor (2-7), a main compressor (2-8), a motor (2-9) and a generator (2-10); wherein, a first inlet and a second inlet of the turbine (2-6) are respectively connected with a cold side outlet of the first main heat exchanger (1-6-1) and the second main heat exchanger (1-6-2), a first outlet and a second outlet are respectively connected with a hot side inlet of the first main regenerator (2-1-1) and the second main regenerator (2-1-2), the hot side outlets of the first main regenerator (2-1-1) and the second main regenerator (2-1-2) are respectively connected with the hot side inlets of the first auxiliary regenerator (2-3-1) and the second auxiliary regenerator (2-3-2), and the hot side outlets of the first auxiliary regenerator (2-3-1) and the second auxiliary regenerator (2-3-2) are respectively connected with an inlet of the first main flow valve (2-4-1) and the second main flow valve (2-4-2) The first outlets of the first main diversion valve (2-4-1) and the second main diversion valve (2-4-2) are respectively connected with the first inlet and the second inlet of the auxiliary compressor (2-7), the first outlet and the second outlet of the auxiliary compressor (2-7) are respectively connected with the second inlets of the first main confluence valve (2-2-1) and the second main confluence valve (2-2-2), the second outlets of the first main diversion valve (2-4-1) and the second main diversion valve (2-4-2) are respectively connected with the first inlet and the second inlet of the hot side of the cooler (2-5), the first outlet and the second outlet of the hot side of the cooler (2-5) are respectively connected with the first inlet and the second inlet of the main compressor (2-8), and the first outlet and the second outlet of the main compressor (2-8) are respectively connected with the first auxiliary regenerator (2-2) 3-1) and a cold side inlet of a second auxiliary heat regenerator (2-3-2), cold side outlets of the first auxiliary heat regenerator (2-3-1) and the second auxiliary heat regenerator (2-3-2) are respectively connected with first inlets of a first main flow merging valve (2-2-1) and a second main flow merging valve (2-2-2), outlets of the first main flow merging valve (2-2-1) and the second main flow merging valve (2-2-2) are respectively connected with cold side inlets of the first main heat regenerator (2-1-1) and the second main heat regenerator (2-1-2), and cold side outlets of the first main heat regenerator (2-1-1) and the second main heat regenerator (2-1-2) are respectively connected with cold side inlets of the first main heat exchanger (1-6-1) and the second main heat exchanger (1-6-2);
the working process of the Brayton power cycle system (2) is as follows: the method comprises the following steps that a circulating working medium absorbs heat from cold sides of a first main heat exchanger (1-6-1) and a second main heat exchanger (1-6-2) which are connected in parallel, then enters a turbine (2-6) through two parallel inlets to do work, simultaneously drives a generator (2-10) to generate power, then leaves the turbine (2-6) through two parallel outlets, sequentially enters hot sides of a first main heat regenerator (2-1-1) and a second main heat regenerator (2-1-2) which are connected in parallel, releases heat of the hot sides of a first auxiliary heat regenerator (2-3-1) and a second auxiliary heat regenerator (2-3-2) which are connected in parallel, and is shunted through a first main shunt valve (2-4-1) and a second main shunt valve (2-4-2) which are connected in parallel: one part of the mixed gas flows out from a first outlet of the first main flow dividing valve (2-4-1) and a first outlet of the second main flow dividing valve (2-4-2), is connected in parallel to enter an auxiliary compressor (2-7) driven by a motor (2-9) for compression, then leaves the auxiliary compressor (2-7) through two parallel outlets, and then enters a second inlet of the first main flow combining valve (2-2-1) and the second main flow combining valve (2-2-2) which are connected in parallel; the other part of the heat-absorbing material flows out from a second outlet of the first main flow dividing valve (2-4-1) and the second main flow dividing valve (2-4-2), enters a high-temperature side of the cooler (2-5) from a parallel inlet to release heat, then enters a main compressor (2-8) driven by a motor (2-9) from a parallel outlet to be compressed, then leaves the main compressor (2-8) through two parallel outlets, enters a cold side of a first auxiliary regenerator (2-3-1) and a second auxiliary regenerator (2-3-2) connected in parallel to absorb heat, and finally enters a first inlet of the first main flow combining valve (2-2-1) and the second main flow combining valve (2-2-2) connected in parallel; after the two parts are converged, the two parts flow out from outlets of a first main flow merging valve (2-2-1) and a second main flow merging valve (2-2-2) which are connected in parallel, enter cold sides of a first main heat regenerator (2-1-1) and a second main heat regenerator (2-1-2) which are connected in parallel to absorb heat, and finally enter cold sides of a first main heat exchanger (1-6-1) and a second main heat exchanger (1-6-2) which are connected in parallel to absorb heat, so that power circulation is completed.
2. The integrated villaumite-cooled high-temperature reactor power system for ships and warships of claim 1, which is characterized in that: the coolant of the reactor body system (1) adopts LiF-BeF2Molten salt, the inlet temperature of the reactor core is 650 ℃, the outlet temperature is 700 ℃, the total thermal power is 125MW, the inlet temperature and the outlet temperature are allowed to have deviation of plus or minus 50 ℃ in actual operation, and the total thermal power is allowed to have deviation of plus or minus 25 MW.
3. The integrated villaumite-cooled high-temperature reactor power system for ships and warships of claim 1, which is characterized in that: the reactor core active area (1-1) of the reactor body system (1) adopts a spiral cross-shaped fuel element, the pellet material is uranium-zirconium alloy, and the enrichment degree is 19.75%; the cladding material is hastelloy; the single-component fuel rods are arranged in a triangular shape, and the components are arranged in a triangular shape.
4. The integrated villaumite-cooled high-temperature reactor power system for ships and warships of claim 1, which is characterized in that: the reactor vessel (1-2) of the reactor body system (1) has a diameter of less than 3.5 meters and a height of less than 3 meters.
5. The integrated villaumite-cooled high-temperature reactor power system for ships and warships of claim 1, which is characterized in that: the first main heat exchanger (1-6-1) and the second main heat exchanger (1-6-2) of the reactor body system (1) are printed circuit board type heat exchangers.
6. The integrated villaumite-cooled high-temperature reactor power system for ships and warships of claim 1, which is characterized in that: in the control rods of the reactor body system (1) and the driving mechanisms (1-7) thereof, 7 control rods are arranged in a single component, and the material of the control rods is boron carbide.
7. The integrated villaumite-cooled high-temperature reactor power system for ships and warships of claim 1, which is characterized in that: the working medium of the Brayton power cycle system (2) is carbon dioxide, and the lowest temperature and pressure of the cycle is higher than the critical temperature and pressure of the cycle; the highest circulating pressure in normal operation is not more than 20MPa, and the highest circulating pressure in special working conditions is not more than 25 MPa; the cycle thermal efficiency is over 48 percent.
8. The integrated villaumite-cooled high-temperature reactor power system for ships and warships of claim 1, which is characterized in that: the Brayton power cycle system (2) exchanges heat with the reactor body system (1) through a first main heat exchanger (1-6-1) and a second main heat exchanger (1-6-2) which are connected in parallel; the loops of all the heat exchangers of the Brayton power cycle system are connected in parallel, and the Brayton power cycle system has redundancy characteristics.
9. The integrated villaumite-cooled high-temperature reactor power system for ships and warships of claim 1, which is characterized in that: a first main heat regenerator (2-1-1), a second main heat regenerator (2-1-2), a first auxiliary heat regenerator (2-3-1), a second auxiliary heat regenerator (2-3-2) and a cooler (2-5) of the Brayton power cycle system (2) are all printed circuit plate heat exchangers, wherein a working medium at the cold side of the cooler (2-5) is filtered seawater.
10. The integrated villaumite-cooled high-temperature reactor power system for ships and warships of claim 1, which is characterized in that: the turbines (2-6), the auxiliary compressors (2-7) and the main compressors (2-8) of the Brayton power cycle system (2) adopt a coaxial-line position different-shaft arrangement mode, so that the power can be flexibly adjusted; the total electric power is greater than 50 MW.
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114837760A (en) * | 2022-03-31 | 2022-08-02 | 西安交通大学 | Efficient hydrogen production and power generation coupling system based on small-sized villiaumite cooling high-temperature reactor |
Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US20100024421A1 (en) * | 2006-12-08 | 2010-02-04 | United Technologies Corporation | Supercritical co2 turbine for use in solar power plants |
| US20100307389A1 (en) * | 2009-06-05 | 2010-12-09 | Stewart Albert E | Reactor system and solid fuel composite therefor |
| CN109356679A (en) * | 2018-11-30 | 2019-02-19 | 西安交通大学 | A kind of Nuclear steam-Bretton association circulating power generation system |
| KR102029421B1 (en) * | 2018-04-30 | 2019-10-07 | 고등기술연구원연구조합 | Fuel cell hybrid generation system |
| CN111951993A (en) * | 2020-07-23 | 2020-11-17 | 东南大学 | Lead-cooled fast reactor supercritical carbon dioxide circulation switchable type vessel power system |
| CN112922685A (en) * | 2021-03-29 | 2021-06-08 | 西安交通大学 | Closed air Brayton-organic Rankine combined cycle system |
| CN113299408A (en) * | 2021-04-30 | 2021-08-24 | 西安交通大学 | Modular small-sized villaumite cooling high-temperature reactor system |
-
2021
- 2021-08-30 CN CN202111005721.8A patent/CN113756891B/en active Active
Patent Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US20100024421A1 (en) * | 2006-12-08 | 2010-02-04 | United Technologies Corporation | Supercritical co2 turbine for use in solar power plants |
| US20100307389A1 (en) * | 2009-06-05 | 2010-12-09 | Stewart Albert E | Reactor system and solid fuel composite therefor |
| KR102029421B1 (en) * | 2018-04-30 | 2019-10-07 | 고등기술연구원연구조합 | Fuel cell hybrid generation system |
| CN109356679A (en) * | 2018-11-30 | 2019-02-19 | 西安交通大学 | A kind of Nuclear steam-Bretton association circulating power generation system |
| CN111951993A (en) * | 2020-07-23 | 2020-11-17 | 东南大学 | Lead-cooled fast reactor supercritical carbon dioxide circulation switchable type vessel power system |
| CN112922685A (en) * | 2021-03-29 | 2021-06-08 | 西安交通大学 | Closed air Brayton-organic Rankine combined cycle system |
| CN113299408A (en) * | 2021-04-30 | 2021-08-24 | 西安交通大学 | Modular small-sized villaumite cooling high-temperature reactor system |
Non-Patent Citations (1)
| Title |
|---|
| 石明珠等: "核动力船舰超临界二氧化碳循环系统建模与性能分析", 《东南大学学报(自然科学版)》 * |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114837760A (en) * | 2022-03-31 | 2022-08-02 | 西安交通大学 | Efficient hydrogen production and power generation coupling system based on small-sized villiaumite cooling high-temperature reactor |
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