CN112037944A - Two-loop heat exporting system suitable for ocean nuclear power platform - Google Patents
Two-loop heat exporting system suitable for ocean nuclear power platform Download PDFInfo
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- CN112037944A CN112037944A CN202010858982.3A CN202010858982A CN112037944A CN 112037944 A CN112037944 A CN 112037944A CN 202010858982 A CN202010858982 A CN 202010858982A CN 112037944 A CN112037944 A CN 112037944A
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- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 166
- 230000017525 heat dissipation Effects 0.000 claims abstract description 19
- 238000001816 cooling Methods 0.000 claims abstract description 3
- 238000009833 condensation Methods 0.000 claims description 39
- 238000001704 evaporation Methods 0.000 claims description 39
- 230000005494 condensation Effects 0.000 claims description 38
- 230000008020 evaporation Effects 0.000 claims description 38
- 239000013535 sea water Substances 0.000 claims description 14
- 230000001174 ascending effect Effects 0.000 claims description 10
- 238000002955 isolation Methods 0.000 claims description 7
- 238000010992 reflux Methods 0.000 abstract 1
- 238000000034 method Methods 0.000 description 9
- 239000002918 waste heat Substances 0.000 description 8
- 230000009471 action Effects 0.000 description 7
- 230000008569 process Effects 0.000 description 6
- 239000007788 liquid Substances 0.000 description 5
- 238000009795 derivation Methods 0.000 description 3
- 239000012530 fluid Substances 0.000 description 3
- 230000007774 longterm Effects 0.000 description 3
- 230000009257 reactivity Effects 0.000 description 3
- 230000001960 triggered effect Effects 0.000 description 2
- 230000008859 change Effects 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000005553 drilling Methods 0.000 description 1
- 239000013505 freshwater Substances 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 231100000817 safety factor Toxicity 0.000 description 1
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
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- 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)
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
Abstract
The invention discloses a two-loop heat exporting system suitable for an ocean nuclear power platform, which relates to the field of two-loop heat exporting of the ocean nuclear power platform and comprises a heat exporting assembly and a heat radiating assembly, wherein the heat exporting assembly comprises a water tank inlet pipeline which is connected with a steam generator and used for exporting steam in the steam generator, and a water tank outlet pipeline which is connected with the steam generator and used for refluxing cold water formed after the steam exported from the water tank inlet pipeline is cooled to the steam generator, and the steam generator is connected with a reactor pressure vessel; the heat dissipation part is a separated heat exchange part, one end of the heat dissipation part is connected with the water tank inlet pipeline to cool steam in the water tank inlet pipeline to form cold water, and the other end of the heat dissipation part is connected with the water tank outlet pipeline to guide the cold water formed by cooling to the water tank outlet pipeline. The invention can ensure the safety of the nuclear power device and also ensure the economy of heat conduction.
Description
Technical Field
The invention relates to the field of heat conduction of two loops of an ocean nuclear power platform, in particular to a heat conduction system of two loops suitable for an ocean nuclear power platform.
Background
The ocean nuclear power platform is a marine floating nuclear power station, one platform carries 1-2 reactors with certain nuclear power according to actual requirements to provide certain product services according to user requirements, such as power supply for a drilling platform, fresh water supply, island and reef supply, comprehensive guarantee for ocean fleet, power supply for deep sea exploration and exploitation, and the like, and the ocean nuclear power platform can greatly meet the requirements in the fields of scientific research, exploration and the like.
For a nuclear power device in an ocean nuclear power platform, the following three nuclear safety factors are required to be met in order to ensure the safety in operation and the nuclear safety after an accident: the control of reactivity, the derivation of reactor core waste heat and the containment of radioactivity. For reactivity control, the control rod will maintain the state of being inserted into the reactor core under the condition of shutdown or accident of the nuclear power plant, therefore, the reactivity is controllable; for the derivation of the reactor core waste heat, the onshore nuclear power and offshore floating small reactor are provided with a special heat derivation system, the reactor core waste heat can be rapidly derived in the middle and short periods after the accident, if the second-generation nuclear power requires that the heat can be derived in 24 hours, the third-generation nuclear power requires that the heat can be derived in 72 hours, extra measures need to be taken beyond the time range, and the cost of the consumed economic cost is high. Therefore, how to continuously conduct heat to the residual heat of the reactor core of the marine nuclear power platform is a problem which needs to be solved at present.
Disclosure of Invention
Aiming at the defects in the prior art, the invention aims to provide a two-loop heat exporting system suitable for an ocean nuclear power platform, which can ensure the safety of a nuclear power device and ensure the economy of heat export.
In order to achieve the above purposes, the technical scheme adopted by the invention is as follows:
the heat exporting assembly comprises a water tank inlet pipeline connected with the steam generator and used for exporting steam in the steam generator, and a water tank outlet pipeline connected with the steam generator and used for returning cold water formed after the steam exported by the water tank inlet pipeline is cooled to the steam generator, and the steam generator is connected with the reactor pressure vessel;
the heat dissipation component is a separated heat exchange component, one end of the heat dissipation component is connected with the water tank inlet pipeline to cool steam in the water tank inlet pipeline to form cold water, and the other end of the heat dissipation component is connected with the water tank outlet pipeline to guide the cold water formed by cooling to the water tank outlet pipeline.
On the basis of the technical scheme, the heat dissipation part comprises a water tank, an evaporation section and a condensation section, wherein the water tank is connected with a water tank inlet pipeline and a water tank outlet pipeline, the evaporation section is arranged in the water tank, the condensation section is arranged outside the water tank and used for being placed in seawater, and the evaporation section and the condensation section are connected through a pipeline to form a loop.
On the basis of the technical scheme, a plurality of heat transfer pipes are arranged in the evaporation section and the condensation section side by side.
On the basis of the technical scheme, the pipeline between the evaporation section and the condensation section comprises:
one end of the ascending section pipeline is connected with the top of the evaporation section and communicated with the inside of the evaporation section, and the other end of the ascending section pipeline is connected with the top of the condensation section and communicated with the inside of the condensation section;
and one end of the descending section pipeline is connected with the bottom of the evaporation section and communicated with the inside of the evaporation section, and the other end of the descending section pipeline is connected with the bottom of the condensation section and communicated with the inside of the condensation section.
On the basis of the technical scheme, a main steam pipeline is arranged between the water tank inlet pipeline and the steam generator, one end of the main steam pipeline is connected with the top of the steam generator and communicated with the interior of the steam generator, a main steam isolating valve is arranged at the other end of the main steam pipeline, one end of the water tank inlet pipeline is connected onto the main steam pipeline, and the other end of the water tank inlet pipeline is connected with the top of the water tank and communicated with the interior of the water tank.
On the basis of the technical scheme, an inlet electric valve is arranged on the water tank inlet pipeline and is close to the main steam pipeline.
On the basis of the technical scheme, a main water supply pipeline is arranged between the water tank outlet pipeline and the steam generator, one end of the main water supply pipeline is connected to the lower portion of the side wall of the steam generator and communicated with the interior of the steam generator, a main water supply isolation valve is arranged at the other end of the main water supply pipeline, one end of the water tank outlet pipeline is connected to the main water supply pipeline, and the other end of the water tank outlet pipeline is connected to the bottom of the water tank and communicated with the interior of the water tank.
On the basis of the technical scheme, an outlet electric valve is arranged on the outlet pipeline of the water tank and is close to the main water supply pipeline.
On the basis of the technical scheme, a heat pipe section and a cold pipe section are arranged between the steam generator and the reactor pressure vessel, one end of the heat pipe section is connected with the steam generator, the other end of the heat pipe section is connected with the reactor pressure vessel, one end of the cold pipe section is connected with the steam generator, the other end of the cold pipe section is reacted on the basis of the technical scheme, a main pump is arranged on the cold pipe section, and the main pump is close to the reactor pressure vessel.
Compared with the prior art, the invention has the advantages that: the heat in the reactor pressure vessel is led into the water tank through the heat leading-out component and the heat dissipation component, then the heat in the water tank is led into seawater, the rapid leading-out of the heat of the reactor core is realized, and the fluid in the heat leading-out component and the heat dissipation component has great density difference in the operation process, so that the passive dynamic circulation can be well realized without additional assistance of other power, and finally, the heat sink is seawater, and the long-term leading-out of the waste heat of the reactor core can be realized.
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 description of the embodiments are briefly introduced 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 creative efforts.
Fig. 1 is a schematic structural diagram of a two-loop heat removal system according to an embodiment of the present invention.
In the figure: 1-steam generator, 2-water tank inlet pipeline, 3-water tank outlet pipeline, 4-reactor pressure vessel, 5-water tank, 6-evaporation section, 7-condensation section, 8-ascending section pipeline, 9-descending section pipeline, 10-main steam pipeline, 11-inlet electric valve, 12-main water supply pipeline, 13-main steam isolation valve, 14-main water supply isolation valve, 15-outlet electric valve, 16-heat pipe section, 17-cold pipe section, 18-main pump, 19-marine nuclear power platform and 20-sea level.
Detailed Description
The embodiment of the invention provides a two-loop heat exporting system suitable for an ocean nuclear power platform, which realizes passive export of reactor core heat after a non-breach accident of the ocean nuclear power platform 19 through a heat exporting assembly and a heat radiating assembly, improves the reliability and economy of a platform nuclear power device, and can greatly reduce the operation risk of the subsequent ocean nuclear power platform 19.
In order to make the objects, technical solutions and advantages of the embodiments of the present application clearer, the technical solutions in the embodiments of the present application will be clearly and completely described below with reference to the drawings in the embodiments of the present application, and it is obvious that the described embodiments are some embodiments of the present application, but not all embodiments. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present application.
Referring to fig. 1, a two-loop heat dissipation system suitable for an offshore nuclear power platform according to an embodiment of the present invention includes a heat dissipation assembly and a heat dissipation assembly.
The heat export assembly comprises a water tank inlet pipeline 2 connected with the steam generator 1 and used for exporting steam in the steam generator 1, and a water tank outlet pipeline 3 connected with the steam generator 1 and used for enabling cold water formed after the steam exported from the water tank inlet pipeline 2 is cooled to flow back to the steam generator 1, wherein the steam generator 1 is connected with a reactor pressure vessel 4. The reactor pushing pressure vessel is a reactor core of a nuclear reactor, heat generated by the reactor core is conducted to the steam generator 1, steam of the steam generator 1 is led out through the water tank inlet pipeline 2 to achieve the purpose of leading out the heat in the steam generator 1, the steam led out from the steam generator 1 is cooled to form cold water, then the cold water flows back into the steam generator 1 through the water tank outlet pipeline 3 to form a change cycle of steam-cold water, and the heat of the reactor core is led out in the cycle process.
The ocean nuclear power platform 19 generally carries 1-2 nuclear power reactors, and the cabin space is narrower and smaller than the space of a land nuclear power plant, so that the equipment arranged on the platform is compact. The reactor cabin is arranged in the middle of the ocean nuclear power platform 19, and the water level of the platform draft is generally 5-8 m.
The heat dissipation part comprises a water tank 5, an evaporation section 6 and a condensation section 7, wherein the water tank 5 is connected with a water tank inlet pipeline 2 and a water tank outlet pipeline 3, the evaporation section 6 is arranged in the water tank 5, the condensation section 7 is arranged outside the water tank 5 and used for being placed in seawater, and the evaporation section 6 is connected with the condensation section 7 through a pipeline to form a loop. A plurality of heat transfer pipes are arranged in parallel in the evaporation section 6 and the condensation section 7. Steam introduced into the water tank 5 through the tank inlet line 2 is cooled to form cold water through the evaporation stage 6 and then returned to the steam generator 1 through the tank outlet line 3.
The piping between the evaporation section 6 and the condensation section 7 includes an ascending section line 8 and a descending section line 9. One end of the ascending section pipeline 8 is connected with the top of the evaporation section 6 and communicated with the inside of the evaporation section 6, and the other end of the ascending section pipeline 8 is connected with the top of the condensation section 7 and communicated with the inside of the condensation section 7; one end of the descending pipeline 9 is connected with the bottom of the evaporation section 6 and communicated with the inside of the evaporation section 6, and the other end is connected with the bottom of the condensation section 7 and communicated with the inside of the condensation section 7. The pipeline between the evaporation section 6 and the condensation section 7 is filled with water, and the water in the pipeline between the evaporation section 6 and the condensation section 7 can be changed into water vapor at a lower temperature, so that the heat of the water in the water tank 5 is taken away.
The interior of the heat dissipation component is in a negative pressure state, when water in the heat dissipation component flows through the water tank 5, under the action of the evaporation section 6, water in the evaporation section 6 absorbs heat in the water tank 5 to form water vapor, the water vapor enters the condensation section 7 through the ascending section pipeline 8, the condensation section 7 is placed in seawater, because the temperature of the water vapor in the condensation section 7 is higher than that of the seawater, the water vapor releases heat under the action of low-temperature seawater, the condensation section 7 guides the heat into the seawater, the water vapor in the condensation section 7 is changed into low-temperature liquid water, under the action of density difference, the formed liquid water flows into the evaporation section 6 through the descending section pipeline 9, is changed into the water vapor after being heated, and takes away the heat of the steam guided into the water tank 5 by the water tank inlet pipeline 2, so that the steam in the water tank 5 is condensed into cold water, the water vapor formed in the evaporation section 6 enters the condensation section 7 through the ascending section pipeline 8, the waste heat in the water tank 5 is led into the seawater through the heat release and the sequential circulation, and the condensation section 7 is always placed in the seawater which is a final hot trap, so that the long-term lead-out of the waste heat of the reactor core can be realized. Steam in the steam generator 1 enters the water tank 5 and contacts the surface of the evaporation section 6, forms liquid cold water after being cooled, and then is guided into the steam generator 1 through the water tank outlet pipeline 3, so that heat in the steam generator 1 is led into the water tank 5, and the heat of a reactor core is led out.
Be equipped with main steam pipeline 10 between water tank inlet pipeline 2 and the steam generator 1, the top of steam generator 1 is connected and communicates in the steam generator 1 to the one end of main steam pipeline 10, is equipped with main steam isolating valve 13 on the other end, and the one end of water tank inlet pipeline 2 is connected on main steam pipeline 10, and the other end is connected the top of water tank 5 and is communicated in the water tank 5. An inlet electric valve 11 is arranged on the water tank inlet pipeline 2, and the inlet electric valve 11 is close to the main steam pipeline 10. The inlet electro valve 11 is closed at all times and opened when triggered by a signal.
A main water supply pipeline 12 is arranged between the water tank outlet pipeline 3 and the steam generator 1, one end of the main water supply pipeline 12 is connected to the lower portion of the side wall of the steam generator 1 and communicated with the inside of the steam generator 1, a main water supply isolation valve 14 is arranged at the other end of the main water supply pipeline 12, one end of the water tank outlet pipeline 3 is connected to the main water supply pipeline 12, and the other end of the water tank outlet pipeline 3 is connected to the bottom of the water tank 5 and communicated with the inside of. An outlet electric valve 15 is arranged on the water tank outlet pipeline 3, and the outlet electric valve 15 is close to the main water supply pipeline 12. The outlet electro valve 15 is closed at all times and opened when triggered by a signal.
A heat pipe section 16 and a cold pipe section 17 are arranged between the steam generator 1 and the reactor pressure vessel 4, one end of the heat pipe section 16 is connected with the steam generator 1, the other end of the heat pipe section is connected with the reactor pressure vessel 4, one end of the cold pipe section 17 is connected with the steam generator 1, and the other end of the cold pipe section is connected with the reactor pressure vessel 4. The cold leg section 17 is provided with a main pump 18, and the main pump 18 is located adjacent to the reactor pressure vessel 4.
The principle of the present invention will be specifically explained below.
When a non-break accident happens to a nuclear power device of an ocean nuclear power platform 19, the temperature and the pressure of a loop rise to trigger the system to operate, an inlet electric valve 11 and an outlet electric valve 15 can be opened by depending on the energy of a storage battery, a main steam isolation valve 13 and a main water supply isolation valve 14 are closed, steam in a steam generator 1 enters a water tank 5 through a main steam pipeline 10 and a water tank inlet pipeline 2, the temperature and the pressure of fluid in the water tank 5 rise to heat water in an evaporation section 6, so that water in the evaporation section 6 is changed into water vapor, the water vapor in the evaporation section 6 enters a condensation section 7 through an ascending section pipeline 8 under the driving action of density difference, and the water vapor in the condensation section 7 is condensed into liquid water due to the low external temperature, and the liquid water enters the evaporation section 6 through a descending section pipeline 9 to be heated continuously so as to realize dynamic circulation. For the water tank 5, because what its entry got into is steam, steam is water through the condensation of evaporation zone 6, water passes through water tank outlet pipeline 3 and main water supply line 12 and gets into steam generator 1, form closed circulation, because there is steam condensation for water, so there is very big density difference between water tank 5 and the steam generator 1, consequently can constantly realize through the density difference that passive waste heat is derived, finally realize leading to the heat in the reactor pressure vessel 4 in the water tank 5, then lead to the sea water with the heat in the water tank 5 again.
According to the two-loop heat exporting system, heat in the reactor pressure vessel 4 is led into the water tank 5 through the heat exporting assembly and the heat radiating assembly, then the heat in the water tank 5 is led into seawater, rapid exporting of reactor core heat is achieved, and fluid in the heat exporting assembly and the heat radiating assembly has great density difference in the operation process, so that passive dynamic circulation can be well achieved without additional assistance of other power, finally, a heat sink is seawater, and long-term exporting of reactor core waste heat can be achieved.
In the description of the present application, it should be noted that the terms "upper", "lower", and the like indicate orientations or positional relationships based on the orientations or positional relationships shown in the drawings, which are only for convenience in describing the present application and simplifying the description, and do not indicate or imply that the referred device or element must have a specific orientation, be constructed in a specific orientation, and operate, and thus, should not be construed as limiting the present application. Unless expressly stated or limited otherwise, the terms "mounted," "connected," and "connected" are intended to be inclusive and mean, for example, that they may be fixedly connected, detachably connected, or integrally connected; can be mechanically or electrically connected; they may be connected directly or indirectly through intervening media, or they may be interconnected between two elements. The specific meaning of the above terms in the present application can be understood by those of ordinary skill in the art as appropriate.
It is noted that, in the present application, relational terms such as "first" and "second", and the like, are used solely to distinguish one entity or action from another entity or action without necessarily requiring or implying any actual such relationship or order between such entities or actions. Also, the terms "comprises," "comprising," or any other variation thereof, are intended to cover a non-exclusive inclusion, such that a process, method, article, or apparatus that comprises a list of elements does not include only those elements but may include other elements not expressly listed or inherent to such process, method, article, or apparatus. Without further limitation, an element defined by the phrase "comprising an … …" does not exclude the presence of other identical elements in a process, method, article, or apparatus that comprises the element.
The above description is merely exemplary of the present application and is presented to enable those skilled in the art to understand and practice the present application. Various modifications to these embodiments will be readily apparent to those skilled in the art, and the generic principles defined herein may be applied to other embodiments without departing from the spirit or scope of the application. Thus, the present application is not intended to be limited to the embodiments shown herein but is to be accorded the widest scope consistent with the principles and novel features disclosed herein.
Claims (10)
1. A two-circuit heat removal system for use with an offshore nuclear power platform, comprising:
the heat exporting assembly comprises a water tank inlet pipeline (2) connected with the steam generator (1) and used for exporting steam in the steam generator (1), and a water tank outlet pipeline (3) connected with the steam generator (1) and used for enabling cold water formed after the steam exported from the water tank inlet pipeline (2) is cooled to flow back to the steam generator (1), wherein the steam generator (1) is connected with the reactor pressure vessel (4);
the heat dissipation assembly is a separated heat exchange component, one end of the heat dissipation component is connected with the water tank inlet pipeline (2) to cool steam in the water tank inlet pipeline (2) to form cold water, and the other end of the heat dissipation component is connected with the water tank outlet pipeline (3) to guide the cold water formed by cooling to the water tank outlet pipeline (3).
2. The two-circuit heat removal system for an offshore nuclear power platform of claim 1, wherein: the heat dissipation part comprises a water tank (5) connected with a water tank inlet pipeline (2) and a water tank outlet pipeline (3), an evaporation section (6) arranged in the water tank (5) and a condensation section (7) arranged outside the water tank (5) and used for being placed in seawater, wherein the evaporation section (6) is connected with the condensation section (7) through a pipeline to form a loop.
3. The two-circuit heat removal system for an offshore nuclear power platform of claim 2, wherein: and a plurality of heat transfer pipes are arranged in the evaporation section (6) and the condensation section (7) side by side.
4. A two-circuit heat removal system for an offshore nuclear power platform according to claim 2, wherein the piping between the evaporator section (6) and the condenser section (7) comprises:
one end of the ascending section pipeline (8) is connected with the top of the evaporation section (6) and communicated with the inside of the evaporation section (6), and the other end of the ascending section pipeline (8) is connected with the top of the condensation section (7) and communicated with the inside of the condensation section (7);
and one end of the descending section pipeline (9) is connected with the bottom of the evaporation section (6) and communicated with the inside of the evaporation section (6), and the other end of the descending section pipeline (9) is connected with the bottom of the condensation section (7) and communicated with the inside of the condensation section (7).
5. The two-circuit heat removal system for an offshore nuclear power platform of claim 2, wherein: be equipped with main steam pipeline (10) between water tank inlet pipeline (2) and steam generator (1), the top of steam generator (1) is connected to the one end of main steam pipeline (10) and with steam generator (1) interior intercommunication, be equipped with main steam isolating valve (13) on the other end, the one end of water tank inlet pipeline (2) is connected on main steam pipeline (10), the top of water tank (5) is connected to the other end and with water tank (5) interior intercommunication.
6. The two-circuit heat removal system for an offshore nuclear power platform of claim 5, wherein: an inlet electric valve (11) is arranged on the water tank inlet pipeline (2), and the inlet electric valve (11) is close to the main steam pipeline (10).
7. The two-circuit heat removal system for an offshore nuclear power platform of claim 2, wherein: a main water supply pipeline (12) is arranged between the water tank outlet pipeline (3) and the steam generator (1), one end of the main water supply pipeline (12) is connected to the lower portion of the side wall of the steam generator (1) and communicated with the interior of the steam generator (1), a main water supply isolation valve (14) is arranged at the other end of the main water supply pipeline, one end of the water tank outlet pipeline (3) is connected to the main water supply pipeline (12), and the other end of the water tank outlet pipeline is connected to the bottom of the water tank (5) and communicated with the interior of the water tank (5).
8. The two-circuit heat removal system for an offshore nuclear power platform of claim 7, wherein: an outlet electric valve (15) is arranged on the water tank outlet pipeline (3), and the outlet electric valve (15) is close to the main water supply pipeline (12).
9. The two-circuit heat removal system for an offshore nuclear power platform of claim 1, wherein: a heat pipe section (16) and a cold pipe section (17) are arranged between the steam generator (1) and the reactor pressure vessel (4), one end of the heat pipe section (16) is connected with the steam generator (1), the other end of the heat pipe section is connected with the reactor pressure vessel (4), one end of the cold pipe section (17) is connected with the steam generator (1), and the other end of the cold pipe section is connected with the reactor pressure vessel (4).
10. The two-circuit heat removal system for an offshore nuclear power platform of claim 9, wherein: and a main pump (18) is arranged on the cold pipe section (17), and the main pump (18) is close to the reactor pressure vessel (4).
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| CN202010858982.3A CN112037944A (en) | 2020-08-24 | 2020-08-24 | Two-loop heat exporting system suitable for ocean nuclear power platform |
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| CN202010858982.3A CN112037944A (en) | 2020-08-24 | 2020-08-24 | Two-loop heat exporting system suitable for ocean nuclear power platform |
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2020
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Application publication date: 20201204 |
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