CN116364318A - Sodium cooled reactor system - Google Patents

Sodium cooled reactor system Download PDF

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Publication number
CN116364318A
CN116364318A CN202310348065.4A CN202310348065A CN116364318A CN 116364318 A CN116364318 A CN 116364318A CN 202310348065 A CN202310348065 A CN 202310348065A CN 116364318 A CN116364318 A CN 116364318A
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China
Prior art keywords
sodium
carbon dioxide
reactor
heat
heat recovery
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CN202310348065.4A
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Chinese (zh)
Inventor
张宇婷
石文涛
潘霖霖
杜海鸥
张庚
樊亦江
常一狄
朱庆福
龙斌
王荣东
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China Institute of Atomic of Energy
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China Institute of Atomic of Energy
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Priority to CN202310348065.4A priority Critical patent/CN116364318A/en
Publication of CN116364318A publication Critical patent/CN116364318A/en
Pending legal-status Critical Current

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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
    • G21C15/24—Promoting flow of the coolant
    • G21C15/243—Promoting flow of the coolant for liquids
    • G21C15/247—Promoting flow of the coolant for liquids for liquid metals
    • 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
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D1/00—Details of nuclear power plant
    • G21D1/02—Arrangements of auxiliary equipment
    • 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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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

Embodiments of the present invention disclose a sodium cooled reactor system. The sodium cooled reactor system includes: a plurality of reactors including a reactor vessel, a core, and a sodium coolant contained in the reactor vessel, the core being disposed in the reactor vessel, the sodium coolant for absorbing heat of the core; a sodium pipe connected between the reactor vessels of the plurality of reactors for connecting the reactor vessels of the plurality of reactors in series to form a sodium circulation loop, and sodium coolant circulating in the reactor vessels of the plurality of reactors and the sodium pipe; the heat exchange device is connected in the sodium pipeline and used for cooling sodium coolant after absorbing heat of the reactor core; and the sodium driving device is connected in the sodium pipeline and is used for driving sodium coolant to circulate in the sodium circulation loop. The sodium cooling reactor system breaks through the traditional single reactor core design, a plurality of reactor cores are operated in series, and the reactor cores share a sodium loop system, so that the thermal efficiency of the reactor system is improved.

Description

Sodium cooled reactor system
Technical Field
The embodiment of the invention relates to the technical field of nuclear reactors, in particular to a sodium cooling reactor system.
Background
The large-sized sodium-cooled fast reactor is designed in a pool type, and a large amount of sodium coolant is contained in a reactor container of the large-sized pool-type sodium-cooled fast reactor, so that the large-sized pool-type sodium-cooled fast reactor has the characteristics of very large sodium loading and power ratio and the like. However, the large pool type sodium-cooled fast reactor has long construction period, high construction cost and poor system maintenance and change flexibility. For example, when some equipment in the reactor pool is damaged and needs to be overhauled, the whole unit is required to be stopped; even if some key equipment is damaged which cannot be maintained, the whole unit is scrapped, and the economy of the power plant is seriously affected. For this reason, studies on small sodium-cooled fast reactors have been conducted. The small sodium-cooled fast reactor system has the advantages of smaller equipment volume, more contribution to underground arrangement, higher safety, feasible design and construction technology, economy, rationality and the like.
However, the current small sodium-cooled fast reactor has a temperature of only about 300-320 ℃, and the power generation thermal efficiency is only about 20-30%, which is economically bad.
Disclosure of Invention
According to one embodiment of the present invention, a sodium cooled reactor system is provided. The sodium cooled reactor system includes: a plurality of reactors including a reactor vessel, a core, and a sodium coolant contained in the reactor vessel, the core being disposed in the reactor vessel, the sodium coolant for absorbing heat of the core; a sodium pipe connected between the reactor vessels of the plurality of reactors for connecting the reactor vessels of the plurality of reactors in series to form a sodium circulation loop, and sodium coolant circulating in the reactor vessels of the plurality of reactors and the sodium pipe; the heat exchange device is connected in the sodium pipeline and used for cooling sodium coolant after absorbing heat of the reactor core; and the sodium driving device is connected in the sodium pipeline and is used for driving sodium coolant to circulate in the sodium circulation loop.
The sodium cooling reactor system breaks through the traditional single reactor core design, a plurality of reactor cores are operated in series, and the reactor cores share a sodium loop system, so that the cooling control of the reactor cores is facilitated, the temperature rise of the single reactor core is reduced, the temperature of sodium coolant in a sodium loop heat exchange device is greatly improved, and the thermal efficiency of the reactor system is improved.
Drawings
Other objects and advantages of the present invention will become apparent from the following description of embodiments of the present invention, which is to be read in connection with the accompanying drawings, and may assist in a comprehensive understanding of the present invention.
Fig. 1 is a schematic diagram of a sodium cooled reactor system according to one embodiment of the invention.
Fig. 2 is a schematic structural view of a sodium cooled reactor system according to another embodiment of the present invention.
Fig. 3 is a schematic structural view of a reactor according to an embodiment of the present invention.
Fig. 4 is a schematic diagram of a sodium inter-process architecture according to one embodiment of the present invention.
It should be noted that the drawings are not necessarily to scale, but are merely shown in a schematic manner that does not affect the reader's understanding.
Detailed Description
For the purposes, technical solutions and advantages of the present application, the technical solutions of the present application will be clearly and completely described below with reference to the drawings of the embodiments of the present application. It will be apparent that the described embodiments are one embodiment of the present application, but not all embodiments. All other embodiments, which can be made by one of ordinary skill in the art without the benefit of the present disclosure, are intended to be within the scope of the present application based on the described embodiments.
It is to be noted that unless otherwise defined, technical or scientific terms used herein should be taken in a general sense as understood by one of ordinary skill in the art to which this application belongs. If, throughout, reference is made to "first," "second," etc., the description of "first," "second," etc., is used merely for distinguishing between similar objects and not for understanding as indicating or implying a relative importance, order, or implicitly indicating the number of technical features indicated, it being understood that the data of "first," "second," etc., may be interchanged where appropriate. If "and/or" is present throughout, it is meant to include three side-by-side schemes, for example, "A and/or B" including the A scheme, or the B scheme, or the scheme where A and B are satisfied simultaneously. Furthermore, for ease of description, spatially relative terms, such as "above," "below," "top," "bottom," and the like, may be used herein merely to describe the spatial positional relationship of one device or feature to another device or feature as illustrated in the figures, and should be understood to encompass different orientations in use or operation in addition to the orientation depicted in the figures.
Sodium cooled fast reactors are fast neutron spectrum reactors using liquid sodium metal as the reactor coolant. In the traditional sodium-cooled fast reactor system, a single reactor core is adopted, the temperature rise of the reactor core is large, and the sodium temperature of the reactor core outlet is low, so that the power generation thermal efficiency of the reactor is low, and the economical efficiency is poor.
Embodiments of the present invention provide a sodium cooled reactor system. Fig. 1 shows a schematic diagram of a sodium cooled reactor system according to one embodiment of the invention. Fig. 2 shows a schematic structural diagram of a sodium cooled reactor system according to another embodiment of the present invention.
As shown in fig. 1 and 2, the sodium cooled reactor system in the embodiment of the present invention includes a plurality of reactors 100, sodium pipes 210, a heat exchange means 220, and a sodium driving means 230. The reactor 100 includes a core 110, a reactor vessel 120, and a sodium coolant contained within the reactor vessel 120, the core 110 being disposed within the reactor vessel 120, the sodium coolant being for absorbing heat of the core 110. Sodium tubing 210 is connected between the stack containers 120 of the plurality of reactors 100 for serially connecting the stack containers 120 of the plurality of reactors 100 to form a sodium circulation loop, and sodium coolant circulates in the stack containers 120 of the plurality of reactors 100 and the sodium tubing 210. The heat exchange device 220 is connected to the sodium tubes 210 for cooling the sodium coolant after absorbing heat from the core 110. A sodium drive 230 is connected to the sodium tubing 210 for driving the sodium coolant in circulation in the sodium circulation loop.
In this embodiment, the reactor is a small loop type sodium-cooled fast reactor, and a plurality of small loop type sodium-cooled fast reactors are connected in series and share one sodium circulation loop. The sodium cooling reactor system in this embodiment breaks through the traditional single-core design, and utilizes the characteristic that the temperature difference between the sodium coolant of a single small reactor and the inlet and outlet of a reactor container is small, so that the reactor cores 110 of a plurality of small reactors are operated in series, and the reactor cores 110 share a sodium circulation loop, thereby being more beneficial to the cooling control of the reactor cores 110, improving the safety of the reactor system, reducing the temperature rise of the single reactor core 110, being beneficial to the safety and long-term use of the reactor system, greatly improving the temperature of the sodium coolant in the sodium heat exchange device 220 in the sodium loop, and improving the thermal efficiency of the reactor system.
Taking the example of 4 reactors 100 in series as shown in fig. 1 and 2, the inlet sodium temperature of the first stage reactor core 110 is designed to be 330 ℃, the temperature of the single core 110 is 80 ℃, and the outlet sodium temperature of the fourth stage reactor core 110 is designed to be 650 ℃. Compared with the traditional sodium-cooled fast reactor adopting a single reactor core, the reactor system in the embodiment reduces the temperature rise of the single reactor core, improves the temperature of the outlet of the final reactor core and improves the thermal efficiency of the reactor system, wherein the sodium temperature of the inlet of the reactor core is 358 ℃ and the sodium temperature of the outlet of the reactor core is 540 ℃.
In this embodiment, the reactor 100 uses liquid sodium metal as the coolant, the sodium has high thermal conductivity and boiling point, can operate at low pressure, has a small neutron absorption cross section, and can efficiently conduct out the heat of the core 110 of the reactor 100. In some embodiments, uranium dioxide is selected as fuel in the core 110.
In some embodiments, the reactor 100 further includes an passive shutdown module for achieving safe shutdown in the event of an abnormal or accident condition of the reactor 100. In this embodiment, the passive shutdown module includes a control rod, a control rod driving device, and an electromagnet. The electromagnet is connected between the control rod and the control rod driving device, so that the control rod and the control rod driving device are connected. In this embodiment, the electromagnet has a curie point temperature, i.e., a magnetic transition temperature.
During normal operation of the reactor 100, the control rod driving apparatus drives the control rods relative to the core 110, and when the control rods are inserted into the core 110, neutrons may be absorbed, controlling the rate of fuel fission reactions in the core 110, and thus controlling the power of the reactor 100. When the temperature in the reactor 100 is increased to the curie point temperature under abnormal or accident conditions, the magnetism of the electromagnet is reduced, so that the control rod is separated from the control rod driving device and falls into the reactor core 110, the reactor 100 is stopped, the reactor 100 after the reactor is stopped is gradually cooled, the safety accident of the reactor 100 is avoided, and the safety of the reactor 100 is ensured.
In some embodiments, the reactor 100 further includes an passive waste heat removal module for removing waste heat from the core 110 when the heat in the reactor 100 cannot be properly removed through the sodium recycle loop. Specifically, the waste heat discharging module includes a waste heat discharging heat exchanger and a cooling water tank, cooling water circulates between the cooling water tank and the waste heat discharging heat exchanger, and sodium coolant circulates between the waste heat discharging heat exchanger and the stack container 120.
When the reactor 100 is operating normally, the waste heat removal module is in a standby state, the temperature of the sodium coolant in the waste heat removal heat exchanger is equal to the temperature of the cooling water in the cooling water tank, and the pressure of the sodium coolant in the waste heat removal heat exchanger is consistent with the pressure of the sodium coolant in the reactor vessel 120 of the reactor 100. When the reactor 100 is in an abnormal or accident condition, the waste heat discharging module is in an operation state, the sodium coolant in the waste heat discharging heat exchanger is low in temperature and high in density due to cooling of cooling water, the sodium coolant in the reactor vessel 120 is high in temperature and low in density due to the fact that the sodium coolant cannot be normally cooled through a sodium circulation loop, and the waste heat discharging heat exchanger and the sodium coolant in the reactor vessel 120 flow in a natural circulation mode due to the pressure difference effect, so that heat of the reactor core 110 is led out.
In the embodiment of the invention, the passive waste heat discharging module is arranged in the reactor 100, the driving force is provided by the pressure difference formed by the density difference of the cold working medium and the hot working medium in the waste heat discharging module, the waste heat of the reactor 100 is guided out by natural circulation, and the safety of the reactor 100 is ensured.
As shown in fig. 1 and 2, in some embodiments, the sodium-cooled reactor system further includes a plurality of sodium coolant branches 240, each sodium coolant branch 240 being disposed outside of each reactor 100, and the sodium coolant branches 240 being connected in parallel to the reactor vessel 120 of the reactor 100. By controlling the switching of each sodium coolant leg 240, a different number of reactors 100 can be selected for series connection.
The present embodiment bypasses a single reactor design for multiple reactors 100 in series, and during a refueling service of one of the reactors 100, the other reactors 100 may still be operated. The embodiment adopts a loop type small-sized reactor core design and a bypass single-reactor design, so that the reactor core container and auxiliary system equipment are replaceable, the problem that the whole unit is required to be stopped when equipment in the traditional single-reactor core reactor is damaged and overhauled is avoided, and the safety and long-term use of a reactor system are facilitated. In addition, the cooling capacity of the sodium circulation loop is redundantly designed in the embodiment, and the cooling of each reactor core can be ensured under the condition of single loop leakage flow.
In some embodiments, each reactor 100 may be deployed underground, with obvious advantages for containment of radioactive materials in severe accident conditions, simplifying off-site emergency planning, with technical possibilities to eliminate off-site emergency response zones.
Further, the plurality of reactors 100 may be separately disposed in different underground spaces, thereby separating the plurality of reactors 100 and avoiding the influence on the operation safety of other reactors 100 when a sodium leak accident occurs in a single reactor 100.
Fig. 3 shows a schematic structural view of a reactor according to an embodiment of the present invention. As shown in fig. 3, the reactor 100 in this embodiment further includes an outlet pipe 250 and at least one control valve 260. An outlet pipe 250 is provided on the reactor vessel 120, the outlet pipe 250 being used to communicate the reactor vessel 120 of the reactor 100 with the sodium pipe 210 outside the reactor 100. At least one control valve 260 is provided on the delivery tube 250 for controlling the flow of sodium coolant in the delivery tube 250.
In this embodiment, the sodium coolant in the reactor vessel 120 is led out into the sodium pipe 210 by setting the lead-out pipe 250, and meanwhile, the on-off of the lead-out pipe 250 is controlled by the control valve 260 set on the lead-out pipe 250, so that when the reactor 100 is subjected to refueling maintenance, the circulation of the sodium coolant in the reactor 100 can be stopped, and other reactors 100 can be operated normally.
In some embodiments, the reactor vessel 120 of the reactor 100 contains sodium coolant, the core 110 is disposed in the sodium coolant, and two outlet pipes 250 are disposed on the reactor vessel 120, and both outlet pipes 250 are in communication with the sodium coolant in the reactor vessel 120, thereby facilitating the outlet of the sodium coolant in the reactor vessel 120. And, two eduction tubes 250 are respectively disposed at the height of the bottom of the core 110 and the top of the core 110. In this embodiment, sodium coolant enters the core 110 from the bottom of the core 110 and absorbs heat from the core 110 to cool the core 110; after the warmed sodium coolant flows out from the top of the reactor core 110, the coolant is delivered into the sodium pipe 210 outside the reactor 100 through the delivery pipe 250 at the top of the reactor core 110 and cooled in the heat exchanger; the cooled sodium coolant is delivered to the bottom of the core 110 within the stack vessel 120 via another delivery tube 250, thereby effecting the circulation of the sodium coolant.
In some embodiments, the number of control valves 260 is two, with two control valves 260 being connected in series on the delivery tube 250 to better seal the sodium coolant within the stack vessel 120 when the control valves 260 are closed. For example, a first control valve 260 and a second control valve 260 are connected in series with the delivery tube 250, the first control valve 260 being closer to the stack vessel 120 than the second control valve 260. In some embodiments, the control valve 260 is a shut-off valve.
In some embodiments, the sodium tubing 210 and the delivery tube 250 are seamless stainless steel tubing, with the tubing being welded to reduce sodium leakage. In some embodiments, at least a portion of the walls of the delivery tube 250 and sodium tubing 210 are double-layered to reduce the likelihood of sodium leakage. For example, the wall of the portion of the delivery tube 250 between the first control valve 260 and the orifice located in the stack container 120 may be double-layered.
In some embodiments, the delivery tube 250 is provided with a siphon break apparatus 270 at the orifice within the stack container 120 for limiting leakage of sodium coolant within the stack container 120. When the sodium pipe 210 outside the reactor 100 is broken or ruptured, the sodium coolant in the reactor vessel 120 leaks out of the reactor through the siphon action from the break of the sodium pipe 210, and in this embodiment, the siphon breaking device 270 is disposed at the orifice of the delivery pipe 250 to break the siphon action, thereby stopping the discharge of the sodium coolant in the reactor vessel 120 out of the reactor, and thus limiting the leakage amount of the sodium coolant in the reactor vessel 120.
In some embodiments, the sodium cooled reactor system further comprises at least one sodium process cell 400, the sodium tubing 210 being disposed within the sodium process cell 400, the sodium process cell 400 being filled with an inert gas. It should be noted that, the sodium process room 400 in the embodiment of the present invention refers to a room or a place where sodium leakage may occur through the sodium pipe 210. In some embodiments, the inert gas is nitrogen.
In this embodiment, the sodium cooling reactor system may be disposed underground, and the sodium process chamber 400 is disposed underground by utilizing the characteristic that the underground space is beneficial to the construction of an inert gas environment, and a low-oxygen or oxygen-free environment in the underground sodium process chamber 400 is constructed by means of nitrogen flooding, so as to strictly control the cleanliness in the sodium process chamber 400, avoid sodium combustion accidents when sodium leaks, and ensure the safety of the sodium cooling reactor system.
In some embodiments, the sodium cooled reactor system further includes an alarm module disposed in part within the sodium process chamber 400 for alerting an operator to timely take a sodium fire emergency treatment when sodium combustion occurs within the sodium process chamber 400.
In some embodiments, the alarm module includes a gas detection device 510, an alarm device, and an alarm control device. As shown in fig. 4, the gas detection device 510 is disposed in the sodium processing chamber 400, and is used for detecting the gas component in the sodium processing chamber 400. The alarm device is used for alarming, and for example, the alarm device can adopt at least one mode of sound, light and electric signals for alarming prompt. The alarm control device is respectively connected with the gas detection device 510 and the alarm device, and is used for receiving the detection signal of the gas detection device 510 and controlling the alarm device according to the detection signal.
In this embodiment, the gas detecting device 510 may detect the gas component in the sodium process chamber 400 in real time, and the detection signal of the gas detecting device 510 may be used as the input signal of the alarm control device and transmitted to the alarm control device in real time. The alarm control device judges whether a sodium fire accident occurs in the sodium technology room 400 according to the detection signal. Specifically, when the detection signal of the gas detection device 510 indicates that the gas component in the sodium technology room 400 is abnormal, or indicates that the sodium technology room 400 contains other components with higher concentration except inert gas (such as nitrogen), the alarm control device sends an alarm signal to the alarm device to control the alarm device to carry out alarm prompt, so that emergency measures can be taken in time when sodium fire occurs, and safety accidents are avoided.
As shown in fig. 4, in some embodiments, the sodium process room 400 is provided with a smoke exhaust device 600, and the smoke exhaust device 600 is used for exhausting smoke when a sodium combustion accident occurs in the sodium process room 400, so that combustion products in the sodium process room 400 can be exhausted in time after a fire disaster occurs, and radioactive sodium aerosol generated by sodium combustion is prevented from diffusing to an adjacent process room.
In some embodiments, smoke evacuation device 600 includes smoke evacuation duct 610, smoke evacuation fan 620, and at least one filter 630. The smoke exhaust duct 610 is partially disposed inside the sodium process chamber 400 and communicates with the outside of the sodium process chamber 400. The smoke exhaust fan 620 is disposed on the smoke exhaust duct 610, and is used for sucking the smoke in the sodium technology room 400 into the smoke exhaust duct 610. The filter 630 is disposed on the smoke exhaust duct 610 for filtering sodium aerosol in the gas, and the smoke exhaust duct 610 is used for exhausting the filtered smoke.
In this embodiment, at least one filter 630 is disposed on the smoke exhaust duct 610 to filter sodium aerosol generated by sodium combustion, and the sodium combustion products are discharged into the filter 630 for purification and then discharged outwards, so as to avoid pollution caused by discharge of sodium aerosol to the outside.
The embodiment of the invention utilizes the underground sodium process room 400 to establish an inert gas environment, thereby greatly reducing the design of a sodium leakage sodium fire protection system and improving the design economy of the protection system.
As shown in fig. 1 and 2, in some embodiments, a supercritical carbon dioxide power generation module 300 is further included, and carbon dioxide circulates within the supercritical carbon dioxide power generation module 300. Wherein, the heat exchange device 220 is connected to the supercritical carbon dioxide power generation module 300, and the heat exchange device 220 is used for transferring heat of the sodium coolant to the carbon dioxide.
In some embodiments, a hot fluid chamber and a cold fluid chamber are formed within the heat exchange device 220, with sodium coolant flowing within the hot fluid chamber and carbon dioxide flowing within the cold fluid chamber, thereby effecting heat transfer between the sodium coolant and the carbon dioxide within the heat exchange device 220.
The embodiment of the invention adopts two loops of sodium-supercritical carbon dioxide to replace three loops of sodium-water in the traditional reactor 100 system, and is used for Na and CO between the two loops 2 Heat exchange device 220 for heat exchange directly transfers heat from the sodium recycle loop to the CO of the two loops 2 The hot end temperature of the power cycle is improved while sodium water reaction is avoided.
In some embodiments, the supercritical carbon dioxide power generation module 300 includes a turbine 310 and a power generation device 320. The turbine unit 310 is connected to the heat exchange unit 220, and carbon dioxide circulates between the turbine unit 310 and the heat exchange unit 220, and the turbine unit 310 is used to convert thermal energy of the carbon dioxide into mechanical energy. The power generation unit 320 is connected to the turbine unit 310 for converting mechanical energy into electrical energy to thereby effect power generation of the sodium cooled reactor system.
As shown in fig. 1, in some embodiments, supercritical carbon dioxide power generation module 300 further includes a first compression device 350, a first heat regeneration device 330, and a cooling device 340. The first compression device 350 is connected between the turbine device 310 and the heat exchange device 220, and is used for compressing carbon dioxide discharged from the turbine device 310, and the compressed carbon dioxide is sent to the heat exchange device 220 to absorb heat of the sodium coolant. The first heat regenerator 330 is connected between the turbine device 310 and the first compressor device 350, and is used for cooling the carbon dioxide discharged from the turbine device 310, and the cooled carbon dioxide is delivered to the first compressor device 350. The cooling device 340 is connected between the first heat returning device 330 and the first compressing device 350 for cooling the carbon dioxide.
In this embodiment, the carbon dioxide discharged from the turbine 310 flows through the first heat regenerator 330, the cooling device 340 and the first compressor 350 in order for cooling and compressing. The carbon dioxide discharged from the turbine unit 310 is cooled and then compressed, so that the inlet temperature of the first compression unit 350 is prevented from being excessively high.
As shown in fig. 1, the first heat recovery device 330 is further connected between the first compression device 350 and the heat exchange device 220, and the first heat recovery device 330 is used for transferring the residual heat of the carbon dioxide discharged from the turbine device 310 to the carbon dioxide compressed by the first compression device 350. The carbon dioxide discharged from the turbine device 310 sequentially flows through the first heat recovery device 330, the cooling device 340 and the first compression device 350 for cooling and compression, the carbon dioxide compressed by the first compression device 350 sequentially flows through the first heat recovery device 330 and the heat exchange device 220 for heating, and the compressed and heated carbon dioxide flows into the turbine device 310 again.
In some embodiments, the cooling device 340 may be a heat exchanger, and the carbon dioxide and the cooling fluid flow in a hot fluid cavity and a cold fluid cavity of the cooling device 340, respectively, and the cooling fluid is used to cool the carbon dioxide. In this embodiment, the cooling device 340 cools the carbon dioxide, so that a temperature difference exists between the compressed carbon dioxide and the carbon dioxide exhausted from the turbine device 310, so that the first heat regenerator 330 is convenient to heat the compressed carbon dioxide by using the carbon dioxide exhausted from the turbine device 310.
Further, the first heat recovery device 330 is a heat exchanger having a hot fluid chamber (i.e., hot end) and a cold fluid chamber (i.e., cold end), in which the hot fluid and the cold fluid flow, respectively.
In this embodiment, the outlet of the turbine device 310 is connected to the hot side inlet of the first heat recovery device 330, the hot side outlet of the first heat recovery device 330 is connected to the inlet of the cooling device 340, the outlet of the cooling device 340 is connected to the inlet of the first compression device 350, the outlet of the first compression device 350 is connected to the cold side inlet of the first heat recovery device 330, and the cold side outlet of the first heat recovery device 330 is connected to the carbon dioxide inlet of the heat exchange device 220.
The carbon dioxide discharged from the turbine device 310 firstly enters the hot fluid cavity of the first heat regenerator 330, then enters the cooling device 340 for cooling, and then enters the first compression device 350 for compression, so that the pressure of the carbon dioxide is increased. Next, the compressed carbon dioxide enters the cold fluid chamber of the first heat recovery device 330 to heat up, and the residual heat of the carbon dioxide discharged from the turbine device 310 is used to heat up the compressed carbon dioxide, so that the residual heat of the carbon dioxide is fully utilized while the temperature of the compressed carbon dioxide is increased, and the utilization rate of heat energy and the thermal efficiency of the reactor 100 system are improved.
In this embodiment, the first compression device 350 and the heat exchange device 220 compress and heat the carbon dioxide discharged from the turbine device 310, so as to maintain the carbon dioxide in a supercritical state, thereby realizing the recycling of the carbon dioxide. It should be noted that, the supercritical carbon dioxide in the embodiment of the present invention refers to carbon dioxide having a temperature higher than the critical temperature and a pressure higher than the critical pressure.
In some embodiments, the supercritical carbon dioxide power generation module 300 may employ a recompression brayton cycle to generate power. As shown in fig. 2, the supercritical carbon dioxide power generation module 300 further includes a second heat regenerator 360. The second heat recovery device 360 is connected between the turbine device 310 and the first heat recovery device 330 for cooling the carbon dioxide discharged from the turbine device 310. The second heat recovery device 360 is further connected between the first heat recovery device 330 and the heat exchange device 220, and is used for transferring the residual heat of the carbon dioxide discharged from the turbine device 310 to the compressed carbon dioxide.
In this embodiment, the carbon dioxide discharged from the turbine device 310 flows through the second heat recovery device 360, the first heat recovery device 330 and the first compression device 350 in sequence for cooling and compressing, and then flows into the first heat recovery device 330, the second heat recovery device 360 and the heat exchange device 220 again for heating, so as to ensure that the carbon dioxide in the supercritical carbon dioxide power generation module 300 maintains a supercritical state.
In some embodiments, the second heat recovery device 360 is a heat exchanger, the second heat recovery device 360 having a hot fluid chamber (i.e., hot end) and a cold fluid chamber (i.e., cold end), the hot fluid and the cold fluid flowing within the hot fluid chamber and the cold fluid chamber, respectively, of the second heat recovery device 360.
In this embodiment, the outlet of the turbine device 310 is connected to the hot side inlet of the second heat recovery device 360, the hot side outlet of the second heat recovery device 360 is connected to the hot side inlet of the first heat recovery device 330, the hot side outlet of the first heat recovery device 330 is connected to the inlet of the cooling device 340, the outlet of the cooling device 340 is connected to the inlet of the first compression device 350, the outlet of the first compression device 350 is connected to the cold side inlet of the first heat recovery device 330, the cold side outlet of the first heat recovery device 330 is connected to the cold side inlet of the second heat recovery device 360, and the cold side outlet of the second heat recovery device 360 is connected to the carbon dioxide inlet of the heat exchange device 220.
Specifically, the carbon dioxide discharged from the turbine 310 sequentially enters the second heat regenerator 360 and the first heat regenerator 330 to release heat, then enters the cooling device 340 to cool, and then enters the first compression device 350 to compress, thereby increasing the pressure of the carbon dioxide. Next, the compressed carbon dioxide sequentially enters the first heat recovery device 330 and the second heat recovery device 360 again to heat up, and the compressed carbon dioxide is heated by the residual heat of the carbon dioxide discharged from the turbine device 310.
By arranging the second heat recovery device 360 in this embodiment, the heat exchange efficiency between the carbon dioxide discharged by the turbine device 310 and the compressed carbon dioxide can be improved, the high efficiency of the sodium cooling reactor system during the change of the power supply requirement is ensured, and the thermal efficiency of the reactor 100 system is improved.
As shown in fig. 2, in some embodiments, the supercritical carbon dioxide power generation module 300 further includes a second compression device 370, where the second compression device 370 is connected between the first heat recovery device 330 and the second heat recovery device 360, and is used for compressing a portion of carbon dioxide cooled by the first heat recovery device 330, and the carbon dioxide compressed by the second compression device 370 is sent to the second heat recovery device 360 for heating. The first compression device 350 is configured to compress another portion of the carbon dioxide cooled by the first heat regenerator 330.
In this embodiment, the carbon dioxide discharged from the turbine 310 sequentially enters the second heat recovery device 360 and the first heat recovery device 330 to release heat. Wherein, part of the carbon dioxide cooled by the first heat regenerator 330 enters the cooling device 340 to be cooled, and then enters the first compression device 350 to be compressed; the other part of the carbon dioxide cooled by the first heat returning device 330 directly enters the second compression device 370 for compression. In this embodiment, by providing two compression devices and a heat regenerator, the circulation efficiency of carbon dioxide is enhanced, and the thermoelectric efficiency of the entire reactor 100 system is improved.
In some embodiments, the inlet of the second compression device 370 is connected to the hot side outlet of the first regenerator 330 and the outlet of the second compression device 370 is connected to the cold side inlet of the second regenerator 360. As shown in fig. 2, a diversion point a is disposed at the hot end outlet of the first heat recovery device 330, and the carbon dioxide flowing out of the first heat recovery device 330 is diverted at the diversion point a, wherein a part of the carbon dioxide flows into the cooling device 340 for cooling and then flows into the first compression device 350 for compression, and another part of the carbon dioxide flows into the second compression device 370 for compression.
Meanwhile, as shown in fig. 2, a collecting point B is disposed at the cold end inlet of the second heat regenerator 360, and the carbon dioxide compressed by the first compressor 350 enters the first heat regenerator 330 to be regenerated, so that the temperature of the carbon dioxide is the same as the temperature of the carbon dioxide compressed by the second compressor 370. The carbon dioxide after being regenerated by the first regenerator 330 is mixed with the carbon dioxide compressed by the second compressor 370 at the convergence point B, and the mixed carbon dioxide flows into the second regenerator 360 together for regeneration.
In the supercritical carbon dioxide power generation module 300 of the present embodiment, after the carbon dioxide exhausted from the turbine device 310 is cooled by the second heat recovery device 360 and the first heat recovery device 330 in sequence, a part of the carbon dioxide directly flows into the second compression device 370 to be compressed, and another part of the carbon dioxide is cooled by the cooling device 340 and then enters the first compression device 350 to be compressed, and is recovered by the first heat recovery device 330. The carbon dioxide after being regenerated by the first regenerator 330 and the carbon dioxide after being compressed by the second compressor 370 are mixed and then sequentially enter the second regenerator 360 and the heat exchanger 220 to be heated, so that the carbon dioxide with high temperature and high pressure is formed to flow into the turbine 310 to do work, and a closed power generation cycle is formed.
Taking the sodium cooled reactor system as shown in fig. 2 as an example, in the case where the sodium coolant branch 240 is not operated in the reactor system, 4 reactors 100 are connected in series, the inlet sodium temperature of the first stage reactor core 110 is designed to be 330 ℃, the temperature of the single core 110 is 80 ℃, and the outlet sodium temperature of the fourth stage reactor core 110 is designed to be 650 ℃. The heat in the sodium recycle loop is then transferred directly to the CO of the two loops by heat exchange device 220 2 The two-loop supercritical carbon dioxide power generation module 300 adopts a recompression brayton cycle, and the cycle power generation efficiency can reach about 50%.
In the case of sodium coolant legs 240 in a reactor system, for example, where only one reactor 100 is operated, the sodium temperature at the inlet of the core 110 is designed to be 330 c, the temperature of the single core 110 is 80 c, and the outlet sodium temperature of the core 110 is 410 c. The heat in the sodium recycle loop is then transferred directly to the CO of the two loops by heat exchange device 220 2 The two-circuit supercritical carbon dioxide power generation module 300 uses the recompression brayton cycle as described above to generate power with a cycle power generation efficiency of about 38%.
In the embodiment of the invention, a supercritical carbon dioxide recompression circulation power generation mode is adopted to replace a traditional steam power generation system, so that the factory building volume of a sodium cooling reactor system can be reduced, and the protection cost is reduced. Compared with the traditional sodium-cooled fast reactor, the power generation efficiency of the loop-type sodium-cooled fast reactor with the multi-reactor connected in series in the embodiment is improved by about 10%, and the benefit is greatly improved. The sodium cooling reactor system in the embodiment realizes higher safety of the whole system, improves thermal efficiency and economy, and promotes large-scale commercial application of the sodium cooling fast reactor.
It should also be noted that, in the embodiments of the present invention, the features of the embodiments of the present invention and the features of the embodiments of the present invention may be combined with each other to obtain new embodiments without conflict.
The present invention is not limited to the above embodiments, but the scope of the invention is defined by the claims.

Claims (13)

1. A sodium cooled reactor system, comprising:
a plurality of reactors including a reactor vessel, a core, and a sodium coolant contained within the reactor vessel, the core disposed within the reactor vessel, the sodium coolant for absorbing heat of the core;
a sodium conduit connected between the reactor vessels of the plurality of reactors for connecting the reactor vessels of the plurality of reactors in series to form a sodium circulation loop, the sodium coolant circulating in the reactor vessels of the plurality of reactors and the sodium conduit;
the heat exchange device is connected in the sodium pipeline and used for cooling the sodium coolant after absorbing the heat of the reactor core;
and the sodium driving device is connected in the sodium pipeline and is used for driving the sodium coolant to circulate in the sodium circulation loop.
2. The system of claim 1, further comprising:
and the sodium coolant branches are correspondingly arranged outside the reactors and are connected in parallel with the reactor containers of the reactors.
3. The system of claim 1, further comprising:
the supercritical carbon dioxide power generation module is internally provided with carbon dioxide in a circulating way;
wherein, the heat exchange device is connected to supercritical carbon dioxide power generation module, the heat exchange device is used for with the heat transfer of sodium coolant to the carbon dioxide.
4. The system of claim 3, wherein the supercritical carbon dioxide power generation module comprises:
the turbine device is connected with the heat exchange device, the carbon dioxide circulates between the turbine device and the heat exchange device, and the turbine device is used for converting the heat energy of the carbon dioxide into mechanical energy;
and the power generation device is connected with the turbine device and is used for converting the mechanical energy into electric energy.
5. The system of claim 4, wherein the supercritical carbon dioxide power generation module further comprises:
the first compression device is connected between the turbine device and the heat exchange device and is used for compressing carbon dioxide discharged by the turbine device, and the compressed carbon dioxide is conveyed to the heat exchange device to absorb heat of the sodium coolant;
the first heat recovery device is connected between the turbine device and the first compression device and is used for cooling carbon dioxide discharged by the turbine device, and the cooled carbon dioxide is conveyed to the first compression device;
the cooling device is connected between the first heat returning device and the first compression device and is used for cooling the carbon dioxide;
the carbon dioxide exhausted by the turbine device flows through the first heat returning device, the cooling device and the first compression device in sequence to be cooled and compressed.
6. The system of claim 5, wherein the first heat regenerator is further connected between the first compression device and the heat exchanger, and the first heat regenerator is used for transferring the residual heat of the carbon dioxide discharged from the turbine device to the carbon dioxide compressed by the first compression device;
the carbon dioxide exhausted by the turbine device flows through the first heat recovery device, the cooling device and the first compression device in sequence for cooling and compressing, the carbon dioxide compressed by the first compression device flows through the first heat recovery device and the heat exchange device in sequence for heating, and the carbon dioxide compressed and heated flows into the turbine device again.
7. The system of claim 6, wherein the supercritical carbon dioxide power generation module further comprises:
the second heat recovery device is connected between the turbine device and the first heat recovery device and is used for cooling carbon dioxide exhausted by the turbine device;
the second heat recovery device is further connected between the first heat recovery device and the heat exchange device and is used for transmitting the waste heat of the carbon dioxide discharged by the turbine device to the compressed carbon dioxide;
carbon dioxide exhausted by the turbine device flows through the second heat recovery device, the first heat recovery device and the first compression device in sequence for cooling and compressing, and then flows into the first heat recovery device, the second heat recovery device and the heat exchange device again for heating.
8. The system of claim 7, wherein the supercritical carbon dioxide power generation module further comprises:
the second compression device is connected between the first heat recovery device and the second heat recovery device and is used for compressing part of carbon dioxide cooled by the first heat recovery device, and the carbon dioxide compressed by the second compression device is conveyed to the second heat recovery device for heating;
the first compression device is used for compressing the other part of carbon dioxide cooled by the first heat returning device.
9. The system of claim 1, wherein the reactor further comprises:
the eduction pipe is arranged on the reactor container and is used for communicating the reactor container of the reactor with a sodium pipeline outside the reactor;
at least one control valve is arranged on the eduction tube and is used for controlling the circulation of sodium coolant in the eduction tube.
10. The system of claim 9, wherein the delivery tube is provided with siphon break apparatus at a nozzle in the stack vessel for restricting leakage of sodium coolant in the stack vessel.
11. The system of claim 9, further comprising:
and at least one sodium process chamber, wherein the sodium pipeline is arranged in the sodium process chamber, and inert gas is filled in the sodium process chamber.
12. The system of claim 11, further comprising: and the alarm module is partially arranged in the sodium process room and is used for alarming when sodium combustion occurs in the sodium process room.
13. The system of claim 12, wherein the alarm module comprises:
the gas detection device is arranged in the sodium process chamber and is used for detecting gas components in the sodium process chamber;
the alarm device is used for alarming;
and the alarm control device is respectively connected with the gas detection device and the alarm device and is used for receiving the detection signal of the gas detection device and controlling the alarm device according to the detection signal.
CN202310348065.4A 2023-04-03 2023-04-03 Sodium cooled reactor system Pending CN116364318A (en)

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Application Number Priority Date Filing Date Title
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Publications (1)

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CN116364318A true CN116364318A (en) 2023-06-30

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