CN112201379A - Intrinsically safe integrated small nuclear power supply for marine environment - Google Patents

Intrinsically safe integrated small nuclear power supply for marine environment Download PDF

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Publication number
CN112201379A
CN112201379A CN202010929243.9A CN202010929243A CN112201379A CN 112201379 A CN112201379 A CN 112201379A CN 202010929243 A CN202010929243 A CN 202010929243A CN 112201379 A CN112201379 A CN 112201379A
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China
Prior art keywords
nuclear power
power supply
coolant
pressure vessel
marine environment
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CN202010929243.9A
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Chinese (zh)
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CN112201379B (en
Inventor
张志俭
董晓朦
张宇航
李磊
张震泽
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Shenzhen University
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Shenzhen University
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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D5/00Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
    • G21D5/02Reactor and engine structurally combined, e.g. portable
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin

Abstract

The application provides a small-size nuclear power supply of intrinsic safety integration for marine environment, including containment, pressure vessel, reactor core, steam generator, turbo generator set, condenser and oxygen-eliminating device. The nuclear power generation system realizes conversion of nuclear energy, heat energy, mechanical energy and electric energy by means of the reactor core, the steam generator, the steam collecting and conveying pipe and the steam turbine generator unit; the condensed water for deoxidizing is formed by the aid of the condenser and the deaerator and is recycled by the steam generator through the water supply distribution pipe, equipment and the structure are simple, arrangement difficulty and cost of the equipment and the structure are reduced, the pressure resistance and the safety of the nuclear power supply are improved by the aid of the double-ball-type containment inner shell, the nuclear power supply has the capability of submerging in the sea through the design of the water pressing cabin and the ballast cabin, and the marine environment adaptability of the nuclear power supply can be improved.

Description

Intrinsically safe integrated small nuclear power supply for marine environment
Technical Field
The application belongs to the technical field of nuclear power, and particularly relates to an inherent safety integrated small nuclear power supply for a marine environment.
Background
Nuclear power is a way of generating electrical energy using a self-sustaining chain fission reaction of a fissile nuclear species. At present, nuclear power is commonly used in onshore nuclear reactor installations to provide an electrical power supply for onshore electrical grids. The long-term high-efficiency safe power supply of islands to be developed, offshore drilling platforms, submarine exploration and deep sea exploration workstations and the like in wide sea areas has strong demand on small nuclear power supplies in marine environments. The existing marine nuclear power system is designed for being used along or by referring to the original marine nuclear power technology, the system composition is relatively complex, the construction and maintenance are difficult, the cost and the period are both greatly uncertain, most of small nuclear power systems are designed by adopting an active and passive safety system, the system is complex, and the problem that the marine nuclear power system is difficult to arrange equipment and structures is caused.
Disclosure of Invention
An object of the embodiment of the application is to provide a small-size nuclear power supply of intrinsic safety integration for marine environment to solve the technical problem that equipment and the structural arrangement degree of difficulty are great for the nuclear power station of marine environment among the prior art.
In order to achieve the purpose, the technical scheme adopted by the application is as follows: the utility model provides a small-size nuclear power of intrinsic safety integration for marine environment, includes containment, pressure vessel, reactor core, steam generator, turbo generator set, condenser and oxygen-eliminating device, pressure vessel turbo generator set the condenser with the oxygen-eliminating device all sets up in the containment, the reactor core with steam generator all sets up in the pressure vessel, turbo generator set the condenser with the oxygen-eliminating device connects gradually, steam generator with be connected with between the turbo generator set run through in pressure vessel's collection vapour steam delivery pipe, the oxygen-eliminating device with be connected with between the steam generator set run through in pressure vessel's feedwater distribution pipe.
Optionally, the pressure vessel is provided with a coolant outlet and a coolant inlet, a coolant flow pipeline outside the pressure vessel is connected between the coolant outlet and the coolant inlet of the pressure vessel, and a heat exchanger and a salt remover are sequentially arranged on the coolant flow pipeline along a direction from the coolant outlet to the coolant inlet.
Optionally, the coolant flow conduit comprises a first flow tube, a second flow tube, and a third flow tube, and the heat exchanger comprises a regenerative heat exchanger and a non-regenerative heat exchanger; one end of the first flow pipe is connected to the coolant outlet of the pressure vessel, the other end of the first flow pipe is connected to the desalter, and the first flow pipe penetrates through the regenerative heat exchanger and the non-regenerative heat exchanger in sequence along the direction from the coolant outlet to the desalter; one end of the second flow pipe is connected to the desalter, and the other end of the second flow pipe is connected to the regenerative heat exchanger; one end of the third flow pipe is connected to the regenerative heat exchanger, and the other end of the third flow pipe is connected to a coolant inlet of the pressure vessel.
Optionally, the containment further comprises a coolant supply tank arranged in the containment, a coolant supply pipe is connected between the coolant supply tank and the third flow pipe, and a supply drive pump and a supply control valve are arranged on the coolant supply pipe.
Optionally, the control device also comprises a control rod movably arranged in the pressure vessel and a control rod driving mechanism arranged outside the pressure vessel, wherein the control rod driving mechanism is connected with the control rod and is used for driving the control rod to move.
Optionally, a sealing water pipe is connected between the control rod drive mechanism and the third flow pipe, and a sealing water drive pump and a sealing water control valve are arranged on the sealing water pipe.
Optionally, the containment further comprises a boric acid tank arranged in the containment, a boric acid pipe is connected between the boric acid tank and the third flow pipe, and a boric acid drive pump and a boric acid control valve are arranged on the boric acid pipe.
Optionally, a radioactive waste resin collection system is connected to the desalter, a shielding cover is arranged outside the radioactive waste resin collection system, and a coolant stop valve is arranged on the second flow pipe.
Optionally, the coolant supply tank and the boric acid tank are both of an annular structure and are arranged around the outside of the pressure vessel, and the regenerative heat exchanger, the non-regenerative heat exchanger and the desalter are distributed around the outside of the pressure vessel.
Optionally, a propeller driving mechanism is arranged on the outer side of the containment vessel.
Optionally, the containment vessel includes an outer shell and an inner shell disposed in the outer shell, the pressure vessel is disposed in the inner shell, a first support frame is connected between the pressure vessel and the inner shell, a second support frame is connected between the outer shell and the inner shell, and the inner shell is in a double-ball shape.
Optionally, a supporting table is arranged on the top of the outer shell, electric power transmission and distribution equipment, a solar power generation device and a wind power generation device are arranged on the supporting table, and a third supporting structure is connected between the inner shell and the supporting table.
Optionally, a water tank is arranged on the support table, the water tank is connected with a nozzle located between the outer shell and the inner shell, a steam release pipeline is connected to the outer side of the outer shell, and a steam release valve is arranged on the steam release pipeline.
Optionally, a burst valve is disposed between the outer shell and the inner shell.
Optionally, the steam turbine generator unit, the condenser, the deaerator, the steam generator, and the reactor core are arranged in order from top to bottom.
Optionally, the turbo generator unit is arranged vertically, and the condenser and the deaerator are both of an annular structure and respectively encircle the turbo generator unit in the axial direction.
Optionally, a water pressure tank and a ballast tank are arranged between the inner shell and the outer shell of the containment vessel.
The embodiment of the application has at least the following beneficial effects: the reactor core generates a large amount of heat, so that liquid water in the steam generator is heated to form saturated steam, the saturated steam generated by the steam generator is collected and conveyed to the steam turbine generator unit through the steam collecting and conveying pipe, the steam turbine generator unit works under the pushing of the saturated steam to convert the heat energy of the saturated steam into the mechanical energy of the steam turbine generator unit, then the steam turbine generator unit converts the mechanical energy into electric energy, the conversion of nuclear energy, heat energy, mechanical energy and electric energy can be realized by relying on the reactor core, the steam generator, the steam collecting and conveying pipe and the steam turbine generator unit, deoxygenated condensate water is formed by relying on the condenser and the deoxygenator and is supplied to the steam generator unit for recycling through the water supply and distribution pipe, the equipment and the structure of the whole nuclear power supply are simple, the difficulty and the cost of arrangement are reduced, and the pressure resistance and the safety of the nuclear power, the design of the ballast tank and the ballast tank enables the nuclear power supply to have the capability of submerging and surfacing in the ocean, and can also improve the ocean environment adaptability of the nuclear power supply.
Drawings
In order to more clearly illustrate the technical solutions in the embodiments of the present application, the drawings needed to be used in the embodiments or the prior art descriptions will be briefly described below, and it is obvious that the drawings in the following description are only some embodiments of the present application, and it is obvious for those skilled in the art to obtain other drawings based on these drawings without inventive exercise.
FIG. 1 is a schematic overall structure diagram of an embodiment of the present application;
FIG. 2 is a schematic diagram showing the pressure vessel, coolant makeup tank, boric acid tank, and coolant flow lines in an embodiment of the present application;
FIG. 3 is a schematic top view of a pressure vessel, coolant makeup tank, boric acid tank, and coolant flow lines in an embodiment of the present application.
Wherein, each mark in the figure is:
1. a containment vessel; 2. a pressure vessel; 3. a reactor core; 4. a steam generator; 5. a turbo generator unit; 6. a condenser; 7. a deaerator; 8. a steam collecting and conveying pipe; 9. a feed water distribution pipe; 10. a coolant outlet; 11. a coolant inlet; 12. a first flow tube; 13. a second flow tube; 14. a third flow tube; 15. a regenerative heat exchanger; 16. a non-regenerative heat exchanger; 17. a desalter; 18. an outlet control valve; 19. a coolant-driven pump; 20. an inlet control valve; 21. a coolant supply tank; 22. a coolant supply pipe; 23. a supply drive pump; 24. a replenishment control valve; 25. a control rod; 26. a control rod drive mechanism; 27. sealing the water pipe; 28. sealing the water-driven pump; 29. sealing the water control valve; 30. a boric acid tank; 31. a boric acid tube; 32. a boric acid driven pump; 33. a boric acid control valve; 34. a radioactive spent resin collection system; 35. a shield case; 36. a coolant shut-off valve; 37. a propeller drive mechanism; 38. a housing; 39. an inner shell; 40. a first support frame; 41. a second support frame; 42. a third support frame; 43. a support table; 44. electric power transmission and distribution equipment; 45. a solar power generation device; 46. a wind power generation device; 47. a water tank; 48. a nozzle; 49. a steam release conduit; 50. a steam release valve; 51. a blast valve; 52. a voltage regulator; 53. an annular water shield chamber; 54. a water-pressing cabin; 55. a ballast tank; 56. and (4) a main pump.
Detailed Description
In order to make the technical problems, technical solutions and advantageous effects to be solved by the present application clearer, the present application is further described in detail below with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative of the present application and are not intended to limit the present application.
It will be understood that when an element is referred to as being "secured to" or "disposed on" another element, it can be directly on the other element or be indirectly on the other element. When an element is referred to as being "connected to" another element, it can be directly or indirectly connected to the other element. The terms "upper", "lower", "left", "right", and the like, indicate orientations or positional relationships based on those shown in the drawings, are merely for convenience of description, and do not indicate or imply that the referred devices or elements must have a specific orientation, be constructed in a specific orientation, and operate, and thus are not to be construed as limiting the patent, and the specific meanings of the above terms will be understood by those skilled in the art according to specific situations. The terms "first", "second" and "first" are used merely for descriptive purposes and are not to be construed as indicating or implying relative importance or implicitly indicating the number of technical features. The meaning of "plurality" is two or more unless specifically limited otherwise.
The embodiment of the application provides an intrinsically safe integrated small nuclear power supply for a marine environment, which comprises a containment vessel 1, a pressure vessel 2, a reactor core 3, a steam generator 4, a turbo generator unit 5, a condenser 6 and a deaerator 7, wherein the pressure vessel 2, the turbo generator unit 5, the condenser 6 and the deaerator 7 are all arranged in the containment vessel 1, and the reactor core 3 and the steam generator 4 are all arranged in the pressure vessel 2; turbo generator set 5, condenser 6 and oxygen-eliminating device 7 connect gradually, are connected with collection vapour steam transmission pipe 8 between steam generator 4 and the turbo generator set 5, and collection vapour steam transmission pipe 8 runs through to set up in pressure vessel 2, is connected with feedwater distribution pipe 9 between oxygen-eliminating device 7 and the steam generator 4, and feedwater distribution pipe 9 runs through to set up in pressure vessel 2. A pressure stabilizer 52 is connected to the pressure vessel 2 to maintain a stable pressure in the pressure vessel 2.
When the reactor core 3 works, a large amount of heat is generated by the reactor core 3, so that liquid water in the steam generator 4 is heated to form saturated steam, the saturated steam generated by the steam generator 4 is collected and conveyed to the steam turbine generator unit 5 through the steam collecting and conveying pipe 8, the steam turbine generator unit 5 works under the pushing of the saturated steam, the heat energy of the saturated steam is converted into the mechanical energy of the steam turbine generator unit 5, and then the steam turbine generator unit 5 converts the mechanical energy into electric energy, so that the conversion of nuclear energy, heat energy, mechanical energy and electric energy is realized; steam enters the condenser 6 after passing through the turbo generator unit 5, and the condensation forms liquid water, then liquid water reenters the oxygen-eliminating device 7 and carries out the deoxidization, and the liquid water after the deoxidization enters into steam generator 4 through feedwater distribution pipe 9, forms saturated steam under the effect of reactor core 3 production heat once more, so constantly circulates.
The small-size nuclear power source of intrinsic safety integration for marine environment that this application embodiment provided, rely on reactor core 3, steam generator 4, collection vapour steam transmission pipe 8 and turbo generator unit 5, can realize nuclear energy, heat energy, mechanical energy, the conversion of electric energy, and rely on the condensate water of condenser 6 and oxygen-eliminating device 7 formation deoxidization, through the 4 recycles of water supply and distribution pipe steam generator, the equipment and the simple structure of whole nuclear power source, thereby the degree of difficulty and the cost of arranging of equipment and structure have been reduced, be particularly suitable for the nuclear power station that is arranged in the marine environment.
In one embodiment, the pressure vessel 2 is provided with a coolant outlet 10 and a coolant inlet 11, a coolant flow pipeline is connected between the coolant outlet 10 and the coolant inlet 11 of the pressure vessel 2, and the coolant flow pipeline is positioned outside the pressure vessel 2; the coolant flow line is provided with a heat exchanger and a demineralizer 17 in this order in the direction from the coolant outlet 10 to the coolant inlet 11.
The reactor core 3 is arranged at the bottom of the pressure vessel 2 in the pressure vessel 2, and a large amount of heat generated by the reactor core 3 is transferred to the steam generator 4 through the coolant; after absorbing the heat of the reactor core 3, the coolant in the pressure vessel 2 flows out of the pressure vessel 2 through the coolant outlet 10 of the pressure vessel 2 and sequentially flows through the heat exchanger and the demineralizer 17 along the coolant flow pipe, the coolant with a large amount of residual heat is cooled and cooled when passing through the heat exchanger, then is purified through the demineralizer 17, and the cooled and purified coolant enters the pressure vessel 2 through the coolant inlet 11 of the pressure vessel 2 and continues to be used as a heat transfer medium in the pressure vessel 2. By providing the pressure vessel 2 with the coolant outlet 10 and the coolant inlet 11 and providing the coolant flow tube with the heat exchanger and the demineralizer 17 between the coolant outlet 10 and the coolant inlet 11, excess heat in the pressure vessel 2 can be transferred out in a timely manner and the coolant can be continuously purified.
In one of the embodiments, the coolant flow lines comprise a first flow tube 12, a second flow tube 13, and a third flow tube 14, and the heat exchangers comprise a regenerative heat exchanger 15 and a non-regenerative heat exchanger 16; one end of a first flow pipe 12 is connected to the coolant outlet 10 of the pressure vessel 2, the other end of the first flow pipe 12 is connected to a desalter 17, and the first flow pipe 12 is sequentially disposed through the regenerative heat exchanger 15 and the non-regenerative heat exchanger 16 in the direction from the coolant outlet 10 to the desalter 17; one end of the second flow tube 13 is connected to the desalter 17, and the other end of the second flow tube 13 is connected to the regenerative heat exchanger 15; one end of the third flow tube 14 is connected to the regenerative heat exchanger 15, and the other end of the third flow tube 14 is connected to the coolant inlet 11 of the pressure vessel 2. In addition, two desalinizers 17 are connected by piping, an outlet control valve 18 and a coolant-driven pump 19 are provided on the first flow pipe 12, and an inlet control valve 20 is provided on the third flow pipe 14.
Because the working temperature of the resin material in the demineralizer 17 is low, the high-temperature coolant in the pressure vessel 2 needs to be cooled and then can be sent to the demineralizer 17 for purification. The coolant flowing out of the coolant outlet 10 passes through the outlet control valve 18, is driven by the coolant drive pump 19, is sent to the tube side of the regenerative heat exchanger 15, is cooled once, and is sent to the tube side of the non-regenerative heat exchanger 16; sea water is injected into the non-regenerative heat exchanger 16 through a pipeline and a driving pump, the sea water carries out secondary temperature reduction on the coolant flowing through the first flow pipe 12 of the non-regenerative heat exchanger 16 and then flows into the sea through the pipeline, and the coolant is sent into the desalter 17 for purification after the temperature of the coolant meets the working requirement of resin in the desalter 17. The inner space of the non-regenerative heat exchanger 16 in fig. 2 can also be used as the annular water shielding chamber in fig. 1, that is, the first flow pipe penetrates through the annular water shielding chamber of the non-regenerative heat exchanger 16, seawater is injected into the annular water shielding chamber of the non-regenerative heat exchanger 16 through a pipeline and a driving pump, and the seawater cools the coolant flowing in the first flow pipe 12 for the second time and then flows into the ocean through the pipeline. The purified coolant is sent to the shell side of the regenerative heat exchanger 15, is heated by the heat released from the tube side of the regenerative heat exchanger 15, and is then sent back to the pressure vessel 2 through the coolant inlet 11. The first flow pipe 12 sequentially penetrates through the regenerative heat exchanger 15 and the non-regenerative heat exchanger 16 along the direction from the coolant outlet 10 to the desalter 17, so that the coolant can be cooled twice before entering the desalter 17 for purification, and the temperature of the coolant is ensured to meet the working requirement of resin in the desalter 17; one end of the third flow pipe 14 is connected to the regenerative heat exchanger 15, and the other end of the third flow pipe 14 is connected to the coolant inlet 11 of the pressure vessel 2, so that the cooling rate of the coolant when the first flow pipe 12 passes through the regenerative heat exchanger 15 can be increased.
In one embodiment, the intrinsically safe integrated small nuclear power supply for marine environment further comprises a coolant supply tank 21 arranged in the containment vessel 1, a coolant supply pipe 22 is connected between the coolant supply tank 21 and the third flow pipe 14, and a supply driving pump 23 and a supply control valve 24 are arranged on the coolant supply pipe 22. When the coolant in the pressure vessel 2 is low and the flow rate of the coolant in the coolant flow line is low, the purge coolant stored in the coolant makeup tank 21 is driven by the makeup drive pump 23, flows through the makeup control valve 24 and the inlet control valve 20, and is sent into the pressure vessel 2 through the coolant inlet 11 to replenish the coolant in the pressure vessel 2.
In one embodiment, the intrinsically safe integrated small nuclear power supply for marine environments further comprises a control rod 25 and a control rod drive mechanism 26, the control rod 25 being movably disposed within the pressure vessel 2, the control rod drive mechanism 26 being disposed outside the pressure vessel 2, the control rod drive mechanism 26 being connected to the control rod 25 and being adapted to drive movement of the control rod 25. By inserting the control rods 25 into the reactor core 3 by the control rod drive mechanism 26, the reactivity of the reactor core 3 can be adjusted, and the power of the reactor core 3 can be adjusted.
In one embodiment, a seal water pipe 27 is connected between the control rod drive mechanism 26 and the third flow tube 14, and a seal water drive pump 28 and a seal water control valve 29 are provided on the seal water pipe 27. A coolant in accordance with the requirements can be fed into the control rod drive mechanism 26 through the seal water drive pump 28 and the seal water pipe 27 as seal water for the control rod drive mechanism 26.
In one embodiment, the intrinsically safe integrated small nuclear power supply for the marine environment further comprises a boric acid tank 30 arranged in the containment vessel 1, a boric acid pipe 31 is connected between the boric acid tank 30 and the third flow pipe 14, and a boric acid driving pump 32 and a boric acid control valve 33 are arranged on the boric acid pipe 31. Under the condition of emergency, if the control rod 25 fails to adjust the reactivity of the reactor core 3, the boric acid driving pump 32 is used for driving, and the concentrated boric acid in the boric acid tank 30 is injected into the pressure vessel 2 through the boric acid control valve 33 and the inlet control valve 20 and then through the coolant inlet 11, so that the deep shutdown of the reactor is realized.
In one embodiment, a radioactive waste resin collection system 34 is connected to the demineralizer 17, a shield 35 is provided in addition to the radioactive waste resin collection system 34, and a coolant shut-off valve 36 is provided on the second flow pipe 13. When the desalter 17 works for a long time, the capacity of purifying the coolant by the resin is reduced, the coolant stop valve 36 can be closed, and the resin in the desalter 17 can be impacted by injecting high-pressure water into the desalter 17, so that the resin in the desalter 17 can be discharged into the radioactive waste resin collecting system 34; the radioactivity of the waste resin in the radioactive waste resin collecting system 34 is high, and the radioactive diffusion can be prevented by providing the shielding case 35 outside thereof.
In one embodiment, the coolant supply tank 21 and the boric acid tank 30 are both in an annular structure and are arranged around the outside of the pressure vessel 2, and the regenerative heat exchanger 15, the non-regenerative heat exchanger 16 and the desalter 17 are distributed around the outside of the pressure vessel 2. Through the arrangement, the weight distribution of the whole nuclear power supply is more uniform, and the floating stability and the safety of the whole nuclear power supply in the marine environment can be improved.
In one embodiment, a propeller driving mechanism 37 is arranged on the outer side of the containment vessel 1, so that the whole nuclear power supply can be assembled on the land coast and then put into the open sea by means of a ship or the propeller driving mechanism 37 of the ship; and by starting different propeller driving mechanisms 37 and controlling the rotating speeds of different propellers, the whole nuclear power supply can deal with potential dangers such as stormy waves or marine organisms in the marine environment, and the floating stability and the safety of the whole nuclear power supply in the marine environment are further improved.
In one embodiment, the containment vessel 1 includes an outer shell 38 and an inner shell 39 disposed in the outer shell 38, the pressure vessel 2 is disposed in the inner shell 39, a first support frame 40 is connected between the pressure vessel 2 and the inner shell 39, and a second support frame 41 is connected between the outer shell 38 and the inner shell 39. Through the double-layer structure design of the outer shell 38 and the inner shell 39, the inner shell 39 is in a negative pressure state, and when the outer shell 38 or the inner shell 39 is damaged, radioactive substances cannot leak; the first support frame 40 can increase the connection strength between the pressure vessel 2 and the inner shell 39, and the second support frame 41 can increase the connection strength between the outer shell 38 and the inner shell 39, so that the structure of the whole nuclear power supply is more stable. The inner shell 39 is of a double-ball type, and the pressure resistance and the safety of the nuclear power supply are improved.
In one embodiment, the top of the outer casing 38 has a support platform 43, the support platform 43 is provided with an electric power distribution device 44, a solar power generation device 45 and a wind power generation device 46, and a third support structure is connected between the inner casing 39 and the support platform 43. The power transmission and distribution equipment 44 can transmit the electric energy generated by the steam turbine generator unit 5 to a ship for use, and the solar power generation device 45 and the wind power generation device 46 can provide power under the condition that a nuclear power supply fails, are used for safe system operation and related active equipment action in the nuclear power supply, and can also be used for providing power for computers, GPS and the like, so that the whole nuclear power supply can be accurately positioned and is convenient to maintain under the accident condition; the third support frame 42 can increase the connection strength between the inner shell 39 and the support table 43, so that the structure of the whole nuclear power supply is more stable, and the first support frame 40, the second support frame 41 and the third support frame 42 can provide necessary support for the whole nuclear power supply, so that the inner shell 39, the outer shell 38 and the pressure container 2 are connected into a whole, and the occurrence of bumping under marine conditions is avoided.
In one embodiment, a water tank 47 is provided on the support platform 43, a nozzle 48 is connected to the water tank 47 between the outer shell 38 and the inner shell 39, a steam release pipe 49 is connected to the outside of the outer shell 38, and a steam release valve 50 is provided on the steam release pipe 49. When the temperature and the pressure in the inner shell 39 exceed the limit value, water in the water tank 47 is sprayed to the outer surface of the inner shell 39 through the nozzle 48, is changed into steam after phase change heat exchange, and can be discharged to the external environment through the steam release pipeline 49, so that heat in the inner shell 39 can be taken away in time, the temperature and the pressure are reduced, and the structural integrity of the containment vessel 1 and the safety of the whole nuclear power supply are ensured.
In one embodiment, a burst valve 51 is disposed between the outer shell 38 and the inner shell 39. Under extreme accident conditions, the explosion valve 51 is opened, and seawater is filled into the whole containment vessel 1, so that the nuclear power supply can sink deep into the ocean, and leakage of radioactive substances is reduced as much as possible.
In one embodiment, the steam turbine generator unit 5, the condenser 6, the deaerator 7, the steam generator 4, and the reactor core 3 are arranged in order from top to bottom. When an accident occurs, because the position of the reactor core 3 is the lowest, the position of the steam generator 4 is the second, the height difference exists between the cold source and the heat source, steam in the steam generator 4 can form a plurality of natural circulation flows under the driving of the density difference along the circulation loop, and heat in the pressure vessel 2 is transferred to the outside (seawater), so that the inherent safety of the nuclear power supply is improved.
In one embodiment, the steam turbine generator unit 5 is arranged vertically, and the condenser 6 and the deaerator 7 are both of annular structures and are respectively arranged around the axial direction of the steam turbine generator unit 5 in a surrounding manner. Through the arrangement, the weight of equipment and structures in the whole nuclear power supply is favorably and uniformly distributed, the gravity center of the whole nuclear power supply is basically positioned on the axis of the steam turbine generator unit 5, and the floating stability of the whole nuclear power supply in the marine environment is favorably improved; and the vertical steam turbine generator set 5 can provide partial buoyancy lift force for the whole system after rotating, so that the floating stability and safety of the whole nuclear power supply in the marine environment are further improved.
In one embodiment, a water compression cabin 54 is arranged between the outer shell 38 and the inner shell 39 of the containment vessel 1, and the nuclear power supply floats up and submerges in the marine environment through water filling and draining of the water compression cabin 54. The ballast tank 55 is arranged at the bottom center between the outer shell 38 and the inner shell 39, so that the center of gravity of the whole nuclear power supply is kept to be lower, the suspension stability is realized, and the marine environment adaptability of the nuclear power supply can be improved.
The above description is only exemplary of the present application and should not be taken as limiting the present application, as any modification, equivalent replacement, or improvement made within the spirit and principle of the present application should be included in the protection scope of the present application.

Claims (17)

1. The utility model provides a small-size nuclear power of intrinsic safety integration for marine environment, a serial communication port, including containment, pressure vessel, reactor core, steam generator, turbo generator unit, condenser and oxygen-eliminating device, pressure vessel turbo generator unit the condenser with the oxygen-eliminating device all sets up in the containment, the reactor core with steam generator all sets up in the pressure vessel, turbo generator unit the condenser with the oxygen-eliminating device connects gradually, steam generator with be connected with between the turbo generator unit run through in pressure vessel's collection vapour steam transmission pipe, the oxygen-eliminating device with be connected with between the steam generator unit run through in pressure vessel's feedwater distributing pipe.
2. The intrinsically-safe integrated small nuclear power supply for a marine environment as claimed in claim 1, wherein the pressure vessel is opened with a coolant outlet and a coolant inlet, a coolant flow pipeline outside the pressure vessel is connected between the coolant outlet and the coolant inlet of the pressure vessel, and a heat exchanger and a salt remover are sequentially arranged on the coolant flow pipeline along a direction from the coolant outlet to the coolant inlet.
3. The intrinsically-safe integrated small nuclear power supply for a marine environment of claim 2, wherein the coolant flow line comprises a first flow tube, a second flow tube, and a third flow tube, the heat exchanger comprises a regenerative heat exchanger and a non-regenerative heat exchanger; one end of the first flow pipe is connected to the coolant outlet of the pressure vessel, the other end of the first flow pipe is connected to the desalter, and the first flow pipe penetrates through the regenerative heat exchanger and the non-regenerative heat exchanger in sequence along the direction from the coolant outlet to the desalter; one end of the second flow pipe is connected to the desalter, and the other end of the second flow pipe is connected to the regenerative heat exchanger; one end of the third flow pipe is connected to the regenerative heat exchanger, and the other end of the third flow pipe is connected to a coolant inlet of the pressure vessel.
4. The intrinsically-safe integrated small nuclear power supply for a marine environment of claim 3, further comprising a coolant supply tank disposed within the containment vessel, a coolant supply pipe connected between the coolant supply tank and the third flow pipe, and a supply drive pump and a supply control valve disposed on the coolant supply pipe.
5. An intrinsically-safe small nuclear power supply for a marine environment as claimed in claim 3, further comprising control rods movably disposed within the pressure vessel and a control rod drive mechanism disposed outside the pressure vessel, the control rod drive mechanism being connected to the control rods and being adapted to drive movement of the control rods.
6. An intrinsically safe small nuclear power supply for a marine environment as claimed in claim 5, wherein a sealed water pipe is connected between the control rod drive mechanism and the third flow tube, and a sealed water drive pump and a sealed water control valve are provided on the sealed water pipe.
7. The intrinsically-safe integrated small nuclear power supply for a marine environment of claim 3, further comprising a boric acid tank disposed within the containment vessel, a boric acid pipe connected between the boric acid tank and the third flow pipe, and a boric acid drive pump and a boric acid control valve disposed on the boric acid pipe.
8. An intrinsically safe small nuclear power supply for a marine environment as claimed in claim 3 wherein the demineralizer is connected to a radioactive waste resin collection system with a shield in addition to the radioactive waste resin collection system and a coolant shut-off valve on the second flow tube.
9. The intrinsically-safe integrated small nuclear power supply of claim 3, wherein the coolant makeup tank and boric acid tank are both of annular configuration and are circumferentially disposed outside the pressure vessel, and the regenerative heat exchanger, the non-regenerative heat exchanger and the demineralizer are circumferentially distributed outside the pressure vessel.
10. An intrinsically safe integrated small nuclear power supply as claimed in any one of claims 1 to 9 in which the outside of the containment vessel is provided with a propeller drive mechanism.
11. An intrinsically safe integrated small nuclear power supply as claimed in any one of claims 1 to 9, wherein the containment vessel comprises an outer shell and an inner shell arranged in the outer shell, the pressure vessel is arranged in the inner shell, a first support frame is connected between the pressure vessel and the inner shell, a second support frame is connected between the outer shell and the inner shell, and the inner shell is of a double-ball type.
12. An intrinsically safe integrated small nuclear power supply for a marine environment as claimed in claim 11, wherein the top of the outer hull has a support platform on which are located power distribution equipment, solar power generation and wind power generation, and a third support structure is connected between the inner hull and the support platform.
13. An intrinsically safe compact nuclear power supply for a marine environment as claimed in claim 12, wherein a water tank is provided on the support platform, the water tank is connected to a nozzle between the outer and inner shells, a steam release conduit is connected to the outside of the outer shell, and a steam release valve is provided on the steam release conduit.
14. An intrinsically safe integrated small nuclear power supply for a marine environment as claimed in claim 11, wherein a burst valve is provided between the outer and inner housings.
15. An intrinsically safe integrated small nuclear power supply for a marine environment as claimed in any one of claims 1 to 9, wherein the turbo-generator unit, the condenser, the deaerator, the steam generator and the reactor core are arranged in sequence from top to bottom.
16. An intrinsically safe small nuclear power supply as claimed in any one of claims 15 in which the turbo unit is arranged vertically and the condenser and the oxygen scavenger are both of annular configuration and are arranged around the turbo unit axis respectively.
17. An intrinsically-safe integrated small nuclear power supply for a marine environment as claimed in claim 11, wherein a ballast tank and a ballast tank are provided between the inner and outer shells of the containment vessel.
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