CN114582529A - Miniature full natural circulation pressurized water reactor system based on large coil pipe steam generator - Google Patents
Miniature full natural circulation pressurized water reactor system based on large coil pipe steam generator Download PDFInfo
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
- G21C13/024—Supporting constructions for pressure vessels or containment vessels
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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
-
- 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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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
- G21D1/006—Details of nuclear power plant primary side of steam generators
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D5/00—Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
- G21D5/04—Reactor and engine not structurally combined
- G21D5/08—Reactor and engine not structurally combined with engine working medium heated in a heat exchanger by the reactor coolant
- G21D5/12—Liquid working medium vaporised by reactor coolant
- G21D5/14—Liquid working medium vaporised by reactor coolant and also superheated by reactor coolant
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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 a miniature full natural circulation pressurized water reactor system based on a large coil steam generator, which comprises a reactor and a containment vessel, wherein the reactor is arranged in the containment vessel; the containment vessel is placed in the air; the system also comprises a nitrogen pressure stabilizing system, a main water supply system, a main steam system, a purification and waste heat discharge system, a passive reactor core cooling system, a passive waste heat discharge system and a passive containment cooling system. The invention adopts a full natural circulation integrated pressurized water reactor technical route, the coolant leads out the heat of the reactor core in the reactor in a natural circulation mode, the heat is transferred to the two loops of working media by the coil pipe direct current steam generator to generate superheated steam, and the superheated steam can push the high-efficiency small-sized steam turbine generator unit to generate electric energy or directly output heat to prepare fresh water. The reactor has the advantages of small volume, light weight, super long service life, high integration efficiency, simple and convenient operation and maintenance, safety and reliability, and can be applied to remote and severe environment areas such as frontier regions, polar regions, plateaus, islands in open sea and the like.
Description
Technical Field
The invention relates to the field of nuclear reactors, in particular to a miniature full natural circulation pressurized water reactor system based on a large coil steam generator.
Background
In recent years, small reactors have attracted more and more attention in the nuclear power industry. The small reactor has wide application fields, can be used for regional heat supply, industrial steam supply, seawater desalination and the like besides power generation, can provide a new solution for regional power and energy supply distribution and optimization and other special application scenes with difficult conventional energy supply, is considered as an important direction of future nuclear energy application in many countries, and gives optimistic prediction on future development of the small reactor by international related research institutions.
The International Atomic Energy Agency (IAEA) encouraged the development of modular mini-stacks, recognizing that modular mini-stacks are a powerful option for improving energy supply guarantees. IAEA announced re-start of small and medium reactor development programs in 2004 and encouraged interested member countries to consider developing and deploying innovative nuclear power systems together at the main meeting of the IAEA council in 2009. More and more countries are conducting modular mini-heap technical research.
At present, countries in the united states, russia, korea, japan, etc. are dedicated to research and develop a multipurpose small reactor with good safety and economic competitiveness, and over 50 kinds of new small and medium-sized reactors are developed, which are mainly used for power generation and can also take into account the combined supply of heat, electricity and water and other special purposes.
Therefore, there is a great need for a miniature full natural circulation pressurized water reactor system based on large coil steam generators that provides support for the multipurpose use of nuclear energy.
Disclosure of Invention
The invention aims to provide a miniature full-natural circulation pressurized water reactor system based on a large coil steam generator, and provides a miniature full-natural circulation pressurized water reactor system with long service life, high safety and multiple purposes aiming at the future small power scale requirement, multiple energy requirements and multiple application scenes; the invention has the characteristics of high safety, small volume, light weight and the like, and can provide support for multipurpose use of nuclear energy.
The invention adopts a technical route of a full natural circulation integrated pressurized water reactor, wherein a fuel assembly adopts a small-sized rod bundle type fuel assembly, an evaporator adopts a large coil pipe direct current steam generator, a control rod driving mechanism adopts an external driving mechanism, a pressure stabilizing mode adopts external nitrogen for stabilizing pressure, and a safety system adopts a passive safety system. The coolant leads out the heat of the reactor core in a natural circulation mode in the reactor, and the coil pipe direct-current steam generator transfers the heat to the two-loop working medium to generate superheated steam, and the superheated steam can push the high-efficiency small-sized steam turbine generator unit to generate electric energy or directly output the heat to prepare fresh water. The reactor technology has the advantages of small reactor power, small residual heat, small source item, good safety and multiple inherent safety characteristics, can flexibly realize multiple purposes of nuclear energy, and is safe, reliable and distributed clean energy. The power generation device can be used for regional heat supply, industrial steam supply, seawater desalination and the like besides power generation, can be used as a fixed power supply for island and reef power supply, seawater desalination, offshore energy exploitation, small city power supply and heat supply and the like, and can also be used as a mobile power supply for underwater space stations, land emergency disaster relief and the like.
The invention is realized by the following technical scheme:
the miniature full natural circulation pressurized water reactor system based on the large coil steam generator comprises a reactor and a containment vessel, wherein the reactor is arranged in the containment vessel; the containment vessel is placed in air;
the system comprises a reactor core, a reactor shell, a reactor core cooling system, a reactor shell cooling system and a reactor shell cooling system, wherein the reactor shell is provided with a reactor shell, and the reactor shell is provided with a reactor shell; the main water supply system is used as a first cooling inlet, the main steam system is used as a first cooling outlet, and cooling water in the main water supply system is heated into superheated steam which is transmitted by the main steam system;
the passive reactor core cooling system is arranged in the containment vessel and outside the reactor, and is connected with the reactor through a first cooling inlet and a second cooling outlet; the passive residual heat removal system is arranged outside the containment, is connected with the main water supply system through a residual heat removal inlet, and is connected with the main steam system through a residual heat removal outlet; the passive containment cooling system is disposed around an outer wall of the containment.
The invention adopts a full natural circulation integrated pressurized water reactor technical route, wherein a fuel assembly adopts a small rod bundle type fuel assembly, an evaporator adopts a large coil pipe direct current steam generator, a control rod driving mechanism adopts an external driving mechanism, and a pressure stabilizing mode adopts external nitrogen for stabilizing pressure. The coolant leads out the heat of the reactor core in a natural circulation mode in the reactor, and the coil pipe direct-current steam generator transfers the heat to the two-loop working medium to generate superheated steam, and the superheated steam can push the high-efficiency small-sized steam turbine generator unit to generate electric energy or directly output the heat to prepare fresh water.
Meanwhile, the passive safety system design is adopted, and after emergency shutdown caused by the accident of power failure (including reliable power loss) of the whole plant occurs, the passive waste heat discharge system continuously discharges the waste heat of the reactor core of the reactor, so that the safety of the reactor is ensured; after a loss of coolant accident, a passive reactor core cooling system executes a reactor core cooling function, an emergency water supplement tank carries out emergency water supplement on a reactor, heat in a containment vessel is condensed and flows back to the bottom of the containment vessel through the wall surface of the containment vessel, the outer side of the lower part of the pressure vessel is submerged, and a direct injection pipeline is arranged at the lower part of the pressure vessel, so that water source can be circularly injected into the pressure vessel. The outer wall surface of the containment is subjected to heat convection through air, heat is discharged to the atmosphere, and the final heat trap function is realized.
Further, the reactor comprises a reactor pressure vessel, a reactor core, a hanging basket assembly, a hold-down barrel assembly, a steam generator, a hold-down assembly, a control rod driving mechanism and a reactor pressure vessel support;
the reactor is characterized in that a reactor core is arranged at the bottom in the reactor pressure vessel, fuel assemblies are arranged in the reactor core, a hanging basket assembly is arranged outside the reactor core, the reactor core is supported by the hanging basket assembly at the bottom, and the upper part of the reactor core is pressed by a pressing barrel assembly; a steam generator is arranged on the upper part of the reactor pressure vessel along the inner wall of the vessel; the reactor compresses and supports a steam generator, a compression assembly and a hanging basket assembly containing a reactor core on an annular boss at the middle part (the top or the bottom of the inner wall of the reactor pressure vessel) through the compression assembly;
the control rod driving mechanism is arranged on a top cover at the top of the reactor pressure vessel; a plurality of reactor pressure vessel supports are uniformly arranged (welded) in the circumferential direction at the middle position of the outer wall of the reactor pressure vessel, one end of each reactor pressure vessel support is fixedly connected with the reactor pressure vessel, and the other end of each reactor pressure vessel support is fixedly connected with (welded or anchored) the inner wall of the containment.
Furthermore, the reactor adopts a full natural circulation technology, a main pump is not needed, the system is simplified, the structure is compact, and the reactor coolant flows through the outer side of the steam generator from top to bottom and exchanges heat with secondary side fluid in the steam generator; secondary side feed water enters the containment through a penetration piece at the top or the side part of the containment, then flows into a feed water header at the top of the steam generator through a penetration piece at the top or the side part of the reactor pressure vessel, flows through a tube bundle of the steam generator from bottom to top after being distributed by the feed water header, exchanges heat with reactor coolant at the outer side of the tube bundle, and is gradually heated by supercooled water to become superheated steam; the superheated steam flows into the steam header and is led out through the steam outlet pipe, and the superheated steam is sent to the turbine system through the top or side penetrating piece of the reactor pressure vessel and the top or side penetrating piece of the containment vessel in sequence.
Furthermore, the steam generator adopts a steam generator with a built-in large-disc straight-flow pipe, the low flow resistance is favorable for establishing natural circulation, the temperature of the coolant in the primary loop is led out to the secondary loop to generate superheated steam, and the effect of reducing the height of the natural circulation reactor is remarkable.
Further, steam generator includes multiunit steam conduit and multiunit feed pipe, can keep apart partial heat exchange tube under abnormal conditions, improves the reactor availability. A steam pipeline in the containment is provided with a steam generator group operation isolation valve, and the steam pipeline is connected with a turbine system through a containment penetration piece; and a steam generator group operation isolation valve is arranged on a water supply pipeline in the containment, and the water supply pipeline enters the connection turbine system through the containment penetration piece.
Furthermore, the fuel assemblies adopt a miniaturized truncated rod type fuel assembly, and in order to increase the uranium loading, reduce neutron leakage and flatten the core power distribution, the fuel elements are arranged in a single fuel assembly in a possible mode of 9 × 9 or 11 × 11. The miniaturized truncated rod type fuel assembly is assisted by low-power density design, thereby being beneficial to realizing an ultra-long fuel change period and having good economical efficiency.
Furthermore, the containment vessel is made of miniaturized steel and is close to the reactor, so that the volume is small, the weight is light, the movable deployment and the off-site refueling are facilitated, and the containment vessel is suitable for scenes with strict height requirement restrictions.
Further, purify and waste heat discharge system including purify under let out cooler/waste heat discharge cooler, purification cooling pump and desalination bed, purify under let out cooler/waste heat discharge cooler one end and connect the reactor lower part, the other end and connect the purification cooling pump, purify the cooling pump and connect the desalination bed, the steam generator of reactor is connected to the desalination bed, realizes waste heat discharge system and clean system sharing part equipment and pipeline.
Furthermore, the passive safety system is designed to continuously discharge the reactor core waste heat of the reactor by the passive waste heat discharge system after emergency shutdown caused by the accident of station blackout (including reliable power loss), so that the safety of the reactor is ensured.
The passive core cooling system is used for performing a core cooling function after a loss of coolant accident happens to the pressurized water reactor system; the passive reactor core cooling system comprises an emergency water replenishing tank, an emergency discharge valve and a recirculation valve, wherein the emergency water replenishing tank is connected with the reactor, an inlet of the emergency water replenishing tank is connected with the reactor through the recirculation valve, and an outlet of the emergency water replenishing tank is connected with the reactor through the emergency discharge valve;
the emergency water replenishing tank carries out emergency water replenishing on the reactor, the discharge valve is opened, heat in the containment is condensed and flows back to the bottom of the containment through the wall surface of the containment, the outer side of the lower part of the reactor pressure vessel is submerged, the lower part of the reactor pressure vessel is provided with a direct injection pipeline, and cooling water can be injected into the reactor pressure vessel in a circulating mode by opening the recirculation valve.
Further, the passive containment cooling system utilizes the outer wall surface of the containment to conduct heat convection through air, and heat is discharged to the atmosphere outside the containment, so that the final heat trap function is achieved.
Compared with the prior art, the invention has the following advantages and beneficial effects:
1. the invention discloses a miniature full-natural circulation pressurized water reactor system, which belongs to the miniature full-natural circulation pressurized water reactor nuclear power supply technology with extremely small size, ultra-long service life, high integration efficiency, simple and convenient operation and maintenance, safety and reliability, the integral height can be less than 6m, the integral weight of a reactor and a containment module can be less than 50t, the refueling period can be no less than 10 years, and the miniature full-natural circulation pressurized water reactor system has better economical efficiency in the ranges of thermal power of 10 MW-15 MW and electric power of 2 MW-3.5 MW.
2. The invention has the characteristics of high power density, long endurance, capability of isolated island operation and the like, adopts modular factory prefabrication, is convenient to transport, is quickly assembled on site, is plug and play, has the outstanding advantages of safety, reliability, high integration efficiency, simplicity and convenience in operation and maintenance and the like, eliminates the difficulty of large-scale construction of a nuclear power station, reduces the capital cost, and has strong movable deployment characteristics.
3. The invention can be widely applied to remote and severe environment areas such as frontier regions, polar regions, plateaus, remote islands and the like, can provide continuous, safe and reliable special power and heat energy supply for isolated small towns, large industrial and mining enterprises and the like, can also provide rapid, stable and powerful energy supply for emergency rescue and disaster relief under extreme conditions such as earthquakes, snow disasters and the like, and has wide market application prospect.
Drawings
The accompanying drawings, which are included to provide a further understanding of the embodiments of the invention and are incorporated in and constitute a part of this application, illustrate embodiment(s) of the invention and together with the description serve to explain the principles of the invention. In the drawings:
fig. 1 is a schematic structural view of a miniature full natural circulation pressurized water reactor system based on a large coil steam generator according to the present invention.
Fig. 2 is a schematic diagram of the reactor structure of a miniature full natural circulation pressurized water reactor system based on a large coil steam generator according to the present invention.
Reference numbers and corresponding part names:
1-a reactor; 101-a reactor pressure vessel; 102-a core; 103-basket assembly; 104-a pressure barrel assembly; 105-a steam generator; 106-a hold down assembly; 107-control rod drive mechanism; 108-reactor pressure vessel support; 2-a containment vessel; 3-nitrogen pressure stabilizing system; 4-a main water supply system; 5-main steam system; 6-purification and waste heat discharge system; 7-passive core cooling system; 8-passive residual heat removal system; 9-passive containment cooling system; 10-a cooling water system; 11-an emergency water replenishing tank; 12-emergency drain valve; 13-a recirculation valve; 14-purge letdown cooler/residual heat removal cooler; 15-a clean cooling pump; 16-desalting bed; 17-passive waste heat exchanger; and 18-a cooling water tank.
Detailed Description
Hereinafter, the term "comprising" or "may include" used in various embodiments of the present invention indicates the presence of the invented function, operation or element, and does not limit the addition of one or more functions, operations or elements. Furthermore, as used in various embodiments of the present invention, the terms "comprises," "comprising," "includes," "including," "has," "having" and their derivatives are intended to mean that the specified features, numbers, steps, operations, elements, components, or combinations of the foregoing, are only meant to indicate that a particular feature, number, step, operation, element, component, or combination of the foregoing, and should not be construed as first excluding the existence of, or adding to the possibility of, one or more other features, numbers, steps, operations, elements, components, or combinations of the foregoing.
In various embodiments of the invention, the expression "or" at least one of a or/and B "includes any or all combinations of the words listed simultaneously. For example, the expression "a or B" or "at least one of a or/and B" may include a, may include B, or may include both a and B.
Expressions (such as "first", "second", and the like) used in various embodiments of the present invention may modify various constituent elements in various embodiments, but may not limit the respective constituent elements. For example, the above description does not limit the order and/or importance of the elements described. The foregoing description is for the purpose of distinguishing one element from another. For example, the first user device and the second user device indicate different user devices, although both are user devices. For example, a first element could be termed a second element, and, similarly, a second element could be termed a first element, without departing from the scope of various embodiments of the present invention.
It should be noted that: if it is described that one constituent element is "connected" to another constituent element, the first constituent element may be directly connected to the second constituent element, and a third constituent element may be "connected" between the first constituent element and the second constituent element. In contrast, when one constituent element is "directly connected" to another constituent element, it is understood that there is no third constituent element between the first constituent element and the second constituent element.
The terminology used in the various embodiments of the invention is for the purpose of describing particular embodiments only and is not intended to be limiting of the various embodiments of the invention. As used herein, the singular forms are intended to include the plural forms as well, unless the context clearly indicates otherwise. Unless otherwise defined, all terms (including technical and scientific terms) used herein have the same meaning as commonly understood by one of ordinary skill in the art to which various embodiments of the present invention belong. The terms (such as those defined in commonly used dictionaries) should be interpreted as having a meaning that is consistent with their contextual meaning in the relevant art and will not be interpreted in an idealized or overly formal sense unless expressly so defined herein in various embodiments of the present invention.
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is further described in detail below with reference to examples and accompanying drawings, and the exemplary embodiments and descriptions thereof are only used for explaining the present invention and are not meant to limit the present invention.
Example 1
The invention adopts a full natural circulation integrated pressurized water reactor technical route, wherein a fuel assembly adopts a small-sized rod bundle type fuel assembly, an evaporator adopts a large coil pipe direct current steam generator, a control rod driving mechanism adopts an external driving mechanism, and a pressure stabilizing mode adopts external nitrogen for stabilizing pressure. The coolant leads out the heat of the reactor core in a natural circulation mode in the reactor, and the coil pipe direct-current steam generator transfers the heat to the two loops of working media to generate superheated steam, and the superheated steam can push the high-efficiency small-sized steam turbine generator unit to generate electric energy or directly output the heat to prepare fresh water.
Meanwhile, the passive safety system design is adopted, and after emergency shutdown caused by the accident of power failure (including reliable power loss) of the whole plant occurs, the passive waste heat discharge system continuously discharges the waste heat of the reactor core of the reactor, so that the safety of the reactor is ensured; after a loss of coolant accident, a passive reactor core cooling system executes a reactor core cooling function, an emergency water supplement tank carries out emergency water supplement on a reactor, heat in a containment vessel is condensed and flows back to the bottom of the containment vessel through the wall surface of the containment vessel, the outer side of the lower part of the pressure vessel is submerged, and a direct injection pipeline is arranged at the lower part of the pressure vessel, so that water source can be circularly injected into the pressure vessel. The outer wall surface of the containment is subjected to heat convection through air, heat is discharged to the atmosphere, and the final heat trap function is realized.
As shown in FIG. 1, the invention relates to a miniature full natural circulation pressurized water reactor system based on a large coil steam generator, which comprises a reactor 1 and a containment vessel 2, wherein the reactor 1 is arranged in the containment vessel 2; the containment vessel 2 is placed in the air, so that the outer wall surface of the containment vessel is fully contacted with the air, the heat exchange of the outer wall surface of the containment vessel through air convection is conveniently realized under the accident condition, and the heat in the containment vessel is discharged to the air outside the containment vessel.
The system comprises a reactor shell, and is characterized by further comprising a nitrogen pressure stabilizing system 3, a main water supply system 4, a main steam system 5, a purification and waste heat discharge system 6, a passive core cooling system 7, a passive waste heat discharge system 8 and a passive containment cooling system 9, wherein the nitrogen pressure stabilizing system 3, the main water supply system 4, the main steam system 5 and the purification and waste heat discharge system 6 are arranged outside the containment 2 and penetrate through the containment 2 to be connected with the reactor 1; the main water supply system 4 is used as a first cooling inlet, the main steam system 5 is used as a first cooling outlet, and cooling water in the main water supply system 4 is heated into superheated steam which is transmitted by the main steam system 5;
the passive core cooling system 7 is arranged in the containment 2 and outside the reactor 1 and is connected with the reactor 1 through a first cooling inlet and a second cooling outlet; the passive residual heat removal system 8 is arranged outside the containment vessel 2, is connected with the main water supply system 4 through a residual heat removal inlet, and is connected with the main steam system 5 through a residual heat removal outlet; the passive containment cooling system 9 is disposed around the outer wall of the containment vessel 2.
In the present embodiment, as shown in fig. 2, the reactor 1 includes a reactor pressure vessel 101, a core 102, a gondola assembly 103, a hold-down cylinder assembly 104, a steam generator 105, a hold-down assembly 106, a control rod drive mechanism 107, a reactor pressure vessel support 108;
a reactor core 102 is arranged at the bottom in the reactor pressure vessel 101, fuel assemblies are arranged in the reactor core 102, a basket assembly 103 is arranged outside the reactor core 102, the reactor core 102 is supported by the basket assembly 103 at the bottom, and the upper part of the reactor core 102 is compressed by a compression barrel assembly 104; a steam generator 105 is arranged on the upper part of the reactor pressure vessel 101 along the inner wall of the vessel; the reactor is used for tightly supporting a steam generator 105, a pressing assembly 104 and a hanging basket assembly 103 containing a core 102 on an annular boss at the middle (top or bottom) position of the inner wall of a reactor pressure vessel 101 through a pressing assembly 106;
the control rod drive mechanism 107 is mounted on the top head of the top of the reactor pressure vessel 101; a plurality of reactor pressure vessel supports 108 are uniformly arranged (welded) in the circumferential direction at the middle position of the outer wall of the reactor pressure vessel 101, one end of each reactor pressure vessel support 108 is fixedly connected with the reactor pressure vessel 101, and the other end of each reactor pressure vessel support is fixedly connected (welded or anchored) with the inner wall of the containment vessel 2.
In this embodiment, the reactor 1 employs a full natural circulation technique, has no main pump, simplifies the system, and has a compact structure, and the reactor coolant flows through the outside of the steam generator 105 from top to bottom to exchange heat with the secondary side fluid in the steam generator 105; secondary side feed water enters the containment through a top penetrating piece or a side penetrating piece of the containment 2, then flows into a feed water header at the top of the steam generator 105 through the top penetrating piece or the side penetrating piece of the reactor pressure vessel 101, flows through a tube bundle of the steam generator 105 from bottom to top after being distributed by the feed water header, exchanges heat with a reactor coolant outside the tube bundle, and is gradually heated into superheated steam from supercooled water; the superheated steam flows into the steam header and is led out through a steam outlet pipe, and the superheated steam is sent to the turbine system through the top or side penetrating piece of the reactor pressure vessel 101 and the top or side penetrating piece of the containment vessel 2 in sequence.
In this embodiment, the steam generator 105 employs a steam generator with a built-in large-disc through-flow pipe, which is low in flow resistance and favorable for establishing natural circulation, and guides the temperature of the coolant in the primary loop to the secondary loop to generate superheated steam, thereby significantly reducing the height of the natural circulation reactor.
In this embodiment, the steam generator 105 includes multiple sets of steam pipes and multiple sets of water supply pipes in the containment 2, the steam pipes are provided with steam generator group operation isolation valves, and the steam pipes are connected to the turbine system through a containment penetration piece; and a steam generator group operation isolation valve is arranged on the water supply pipeline, and the water supply pipeline enters the connection turbine system through the containment penetration piece.
For example, a plurality of groups of steam pipelines are converged into two main steam pipelines in the containment vessel 2, two main steam pipelines in the containment vessel 2 are provided with steam generator group operation isolation valves, and the two main steam pipelines are connected with a turbine system through a containment vessel penetration piece; the multiple groups of water supply pipes are converged into two main water supply pipelines in the containment vessel 2, steam generator group operation isolation valves are arranged on the two main water supply pipelines in the containment vessel 2, and the two main water supply pipelines enter the connection turbine system through a containment vessel penetrating piece.
In this embodiment, the fuel assemblies adopt miniaturized truncated rod type fuel assemblies, and in order to increase the uranium loading, reduce neutron leakage, and flatten the core power distribution, the fuel elements are arranged in a single fuel assembly in a manner of 9 × 9 or 11 × 11. The miniaturized truncated rod type fuel assembly is assisted by low-power density design, thereby being beneficial to realizing an ultra-long fuel change period and having good economical efficiency.
In the embodiment, the containment vessel 2 is a miniaturized steel containment vessel which is close to a reactor, has small volume and light weight, is beneficial to mobile deployment and off-site refueling, and is suitable for scenes with strict height requirement limitation.
In this embodiment, the purification and waste heat removal system 6 includes a purification and blowdown cooler/waste heat removal cooler 14, a purification cooling pump 15 and a desalination bed 16, the purification and blowdown cooler/waste heat removal cooler 14 is connected to reactor 1 lower part, the other end of purification and blowdown cooling pump 15, the purification cooling pump 15 is connected with desalination bed 16, and desalination bed 16 is connected with steam generator 105 of reactor 1, realizes that waste heat removal system and clean system share some equipment and pipelines.
In the embodiment, the passive safety system is designed to continuously discharge the reactor core waste heat of the reactor by the passive waste heat discharge system after emergency shutdown caused by the power failure (including reliable power loss) of the whole plant, so as to ensure the safety of the reactor;
the passive core cooling system 7 is used for performing a core cooling function after a loss of coolant accident occurs to the pressurized water reactor system; the passive reactor core cooling system 7 comprises an emergency water replenishing tank 11, an emergency discharge valve 12 and a recirculation valve 13, wherein the emergency water replenishing tank 11 is connected with the reactor 1, an inlet of the emergency water replenishing tank is connected with the reactor 1 through the recirculation valve 13, and an outlet of the emergency water replenishing tank is connected with the reactor 1 through the emergency discharge valve 12;
the emergency water replenishing tank 11 performs emergency water replenishing on the reactor 1, the discharge valve 12 is opened, heat in the containment vessel 2 is condensed and flows back to the bottom of the containment vessel 2 through the wall surface of the containment vessel 2, the outer side of the lower part of the reactor pressure vessel 101 is submerged, the direct injection pipeline is arranged at the lower part of the reactor pressure vessel 101, and cooling water can be circularly injected into the reactor pressure vessel 101 by opening the recirculation valve 13.
In this embodiment, the passive residual heat removal system 9 includes a passive residual heat removal heat exchanger 17 and a cooling water tank 18.
In this embodiment, the passive containment cooling system 9 and the passive core cooling system 7 together derive core decay heat, and the passive containment cooling system 9 uses the outer wall surface of the containment 2 to perform heat convection through air, so as to discharge heat to the atmosphere outside the containment, thereby realizing a final heat sink function.
In the specific implementation:
in the embodiment, a steam generator 105 with a built-in large-disc straight-flow pipe is adopted, the flow resistance is low, natural circulation is favorably established, the temperature of a coolant in a primary loop is led out to a secondary loop, cooling water in a main water supply system 4 is heated into superheated steam and is transmitted by a main steam system 5, and the effect of reducing the height of a natural circulation reactor is remarkable; an external nitrogen pressure stabilizing system 3 is adopted, so that the reactor is favorable for quick start, the system is simplified, the control is simple and convenient, and the self-consumption energy is small; the small truncated rod type fuel assembly is adopted, and the low-power density design is adopted, so that the ultra-long refueling period is favorably realized, and the economy is good; the full natural circulation pressurized water reactor technology is adopted, a main pump is not used, the system is simplified, and the structure is compact; the small steel containment vessel 2 is close to a reactor, has small volume and light weight, is beneficial to mobile deployment and off-site refueling, and is suitable for scenes with strict height requirement restriction.
The reactor coolant system consists of a reactor 1, a coiled tube steam generator 105 disposed within the reactor pressure vessel 101, a nitrogen pressure stabilization system 3, and instrumentation, the system having full power natural circulation capability. The reactor coolant heated by the core 102 flows upward, out of the hold-down barrel assembly 104, through the inner wall water flow holes integrated with the coil once-through steam generator 105, into the inlet chamber of the coil once-through steam generator 105, and then flows downward through the spiral heat transfer tubes of the coil once-through steam generator 105, transferring heat to the secondary side feedwater and causing it to generate superheated steam for use by the main steam system 5. The reactor coolant cooled by the feedwater of the main feedwater system 4 exits the coil once-through steam generator 105 and enters the core 101 from the bottom of the basket assembly 103 to form a closed natural circulation.
the steam generator 105 is provided with a steam generator group operation isolation valve on a steam pipe in the containment 2, and the steam pipe is connected with a turbine system through a containment penetration. The steam generator 105 is provided with a steam generator group operation isolation valve on a water supply pipe in the containment 2, and the water supply pipe enters the connection turbine system through a containment 2 penetrating piece.
The pipes running through the containment vessel 2 are mainly: an inlet pipeline and an outlet pipeline of a purification and waste heat discharge system 6, a 3 surge pipe of a nitrogen pressure stabilizing system, a main water supply pipe of a main water supply system 4, a main steam pipe of a main steam system 5 and the like. Wherein an inlet pipeline of the purification and waste heat discharge system 6 is led out from the vicinity of the upper part of a tube bundle of a coil direct current steam generator 105 in the reactor pressure vessel 101, passes through an isolation valve and then is led out through the containment vessel 2; the outlet pipeline of the purification and waste heat discharge system 6 and the surge pipe of the nitrogen pressure stabilizing system 3 are led out from the vicinity of the lower part of the pipe bundle of the coil once-through steam generator 105 in the reactor pressure vessel 101, pass through the containment vessel 2 after passing through the isolation valve.
The system pressure control adopts a nitrogen pressure stabilizing system 3, and the reactor pressure vessel 101 is connected with the nitrogen pressure stabilizer 3 through a pipeline, and has the main functions of compensating the volume fluctuation of the reactor coolant and maintaining the pressure of the reactor coolant system within a normal range.
The safety system adopts a passive design, and after emergency shutdown caused by a power failure (including reliable power loss) accident of a whole plant, the passive residual heat removal system 8 continuously removes the reactor core residual heat of the reactor, so that the safety of the reactor is ensured; after a loss of coolant accident, a passive reactor core cooling system 7 executes a reactor core cooling function, an emergency water replenishing tank 11 performs emergency water replenishing on a reactor, a discharge valve 12 is opened, heat in a containment vessel 2 is condensed and reflows to the bottom of the containment vessel 2 through the wall surface of the containment vessel 2, the outer side of the lower part of a reactor pressure vessel 101 is submerged, a direct injection pipeline is arranged at the lower part, and cooling water can be circularly injected into the pressure vessel by opening a recirculation valve 13; the passive containment cooling system 9 and the passive core cooling system 7 lead out the core decay heat together, the outer wall surface of the containment exchanges heat through air convection, the heat is discharged to the atmosphere, and the final heat trap function is realized.
The invention relates to a miniature full-natural circulation pressurized water reactor system based on a large coil pipe steam generator, which adopts a full-natural circulation integrated pressurized water reactor technical route, wherein a fuel assembly adopts a small rod bundle type fuel assembly, an evaporator adopts a large coil pipe direct current steam generator, a control rod driving mechanism adopts an external driving mechanism, a pressure stabilizing mode adopts external nitrogen for stabilizing pressure, and a safety system adopts a passive safety system. The coolant leads out the heat of the reactor core in a natural circulation mode in the reactor, and the coil pipe direct-current steam generator transfers the heat to the two loops of working media to generate superheated steam, and the superheated steam can push the high-efficiency small-sized steam turbine generator unit to generate electric energy or directly output the heat to prepare fresh water. The reactor technology has the characteristics of small reactor power, small waste heat, small source item, good safety and multiple inherent safety, can flexibly realize nuclear energy multiple purposes, and is safe, reliable and distributed clean energy. The power generation device can be used for regional heat supply, industrial steam supply, seawater desalination and the like besides power generation, can be used as a fixed power supply to supply power to islands and reefs, desalinate seawater, supply power and supply heat to marine energy, small cities and the like, and can also be used as a mobile power supply for underwater space stations, land emergency relief and the like.
The above-mentioned embodiments are intended to illustrate the objects, technical solutions and advantages of the present invention in further detail, and it should be understood that the above-mentioned embodiments are merely exemplary embodiments of the present invention, and are not intended to limit the scope of the present invention, and any modifications, equivalent substitutions, improvements and the like made within the spirit and principle of the present invention should be included in the scope of the present invention.
Claims (10)
1. The miniature full natural circulation pressurized water reactor system based on the large coil steam generator comprises a reactor and a containment vessel, wherein the reactor is arranged in the containment vessel; the safety shell is characterized in that the safety shell is placed in the air;
the system comprises a reactor core, a reactor shell, a reactor core cooling system, a reactor shell cooling system and a reactor shell cooling system, wherein the reactor shell is provided with a reactor shell, and the reactor shell is provided with a reactor shell; the main water supply system is used as a first cooling inlet, and the main steam system is used as a first cooling outlet;
the passive core cooling system is arranged in the containment and outside the reactor and is connected with the reactor through a first cooling inlet and a second cooling outlet.
2. The large coil steam generator based micro all natural circulation pressurized water reactor system of claim 1, wherein the reactor comprises a reactor pressure vessel, a core, a basket assembly, a hold-down barrel assembly, a steam generator, a hold-down assembly, a control rod drive mechanism, a reactor pressure vessel support;
the reactor is characterized in that a reactor core is arranged at the bottom in the reactor pressure vessel, fuel assemblies are arranged in the reactor core, a hanging basket assembly is arranged outside the reactor core, the reactor core is supported by the hanging basket assembly at the bottom, and the upper part of the reactor core is pressed by a pressing barrel assembly; a steam generator is arranged on the upper part of the reactor pressure vessel along the inner wall of the vessel; the reactor compresses and supports the steam generator, the compressing assembly and the hanging basket assembly containing the reactor core on an annular boss in the middle or upper part or bottom part of the inner wall of the reactor pressure vessel through the compressing assembly;
the control rod driving mechanism is arranged on a top cover at the top of the reactor pressure vessel; a plurality of reactor pressure vessel supports are uniformly arranged in the middle of the outer wall of the reactor pressure vessel in the circumferential direction, one end of each reactor pressure vessel support is fixedly connected with the reactor pressure vessel, and the other end of each reactor pressure vessel support is fixedly connected with the inner wall of the containment.
3. The large coil steam generator based micro full natural circulation pressurized water reactor system of claim 2, wherein full natural circulation technology is used in the reactor, and reactor coolant flows through the outside of the steam generator from top to bottom to exchange heat with secondary side fluid in the steam generator; secondary side feed water enters the containment through a penetration piece at the top or the side part of the containment, then flows into a feed water header at the top of the steam generator through a penetration piece at the top or the side part of the reactor pressure vessel, flows through a tube bundle of the steam generator from bottom to top after being distributed by the feed water header, exchanges heat with a reactor coolant at the outer side of the tube bundle, and is gradually heated by supercooled water to be changed into superheated steam; the superheated steam flows into the steam header and is led out through the steam outlet pipe, and the superheated steam is sent to the turbine system through the top or side penetrating piece of the reactor pressure vessel and the top or side penetrating piece of the containment vessel in sequence.
4. The large coil steam generator based micro all natural circulation pressurized water reactor system of claim 2, wherein the steam generator employs a large coil once-through steam generator.
5. The large coil steam generator based micro full natural circulation pressurized water reactor system according to claim 4, wherein the steam generator includes multiple sets of steam pipes and multiple sets of feed pipes, wherein a steam generator group operation isolation valve is arranged on the steam pipe in the containment, and the steam pipe is connected with the turbine system through the containment penetration; and a steam generator group operation isolation valve is arranged on a water supply pipeline in the containment, and the water supply pipeline enters the connection turbine system through the containment penetration piece.
6. The large coil steam generator based micro full natural circulation pressurized water reactor system according to claim 2, wherein said fuel assemblies are miniaturized truncated rod type fuel assemblies with possible arrangements of fuel elements in a single fuel assembly of 9 x 9 or 11 x 11, etc.
7. The large coil steam generator based micro full natural circulation pressurized water reactor system of claim 1, wherein the containment is a miniaturized steel containment.
8. The large coil steam generator based mini full natural circulation pressurized water reactor system of claim 2, wherein the purge and residual heat removal system comprises a purge downcomer cooler, a purge cooling pump and a desalination bed, wherein the purge downcomer cooler is connected to the lower part of the reactor at one end and the purge cooling pump at the other end, the purge cooling pump is connected to the desalination bed, and the desalination bed is connected to the steam generator of the reactor, so that the shared parts of equipment and pipelines of the residual heat removal system and the purge system are realized.
9. The large coil steam generator based micro full natural circulation pressurized water reactor system according to claim 2, wherein the passive residual heat removal system is used for continuously removing the reactor core residual heat after emergency shutdown caused by the station blackout accident, so as to ensure the safety of the reactor; the plant outage comprises a reliable power loss;
the passive core cooling system is used for performing a core cooling function after a loss of coolant accident happens to the pressurized water reactor system; the passive reactor core cooling system comprises an emergency water supplementing tank, an emergency discharge valve and a recirculation valve, wherein the emergency water supplementing tank is connected with the reactor, an inlet of the emergency water supplementing tank is connected with the reactor through the recirculation valve, and an outlet of the emergency water supplementing tank is connected with the reactor through the emergency discharge valve;
the emergency water replenishing tank carries out emergency water replenishing on the reactor, the discharge valve is opened, heat in the containment is condensed and flows back to the bottom of the containment through the wall surface of the containment, the outer side of the lower part of the reactor pressure vessel is submerged, the lower part of the reactor pressure vessel is provided with a direct injection pipeline, and cooling water is circularly injected into the reactor pressure vessel by opening the recirculation valve.
10. The large coil steam generator based micro full natural circulation pressurized water reactor system according to claim 1 or 9, wherein the passive containment cooling system utilizes the outer containment wall surface to discharge heat to the outside-containment atmosphere by air convection heat transfer to achieve the final heat sink function.
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