CN107403650B - Secondary side passive waste heat discharging system of offshore floating nuclear power station - Google Patents
Secondary side passive waste heat discharging system of offshore floating nuclear power station Download PDFInfo
- Publication number
- CN107403650B CN107403650B CN201710740701.2A CN201710740701A CN107403650B CN 107403650 B CN107403650 B CN 107403650B CN 201710740701 A CN201710740701 A CN 201710740701A CN 107403650 B CN107403650 B CN 107403650B
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- steam
- condensate
- steam generator
- nuclear power
- secondary side
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- 239000002918 waste heat Substances 0.000 title claims abstract description 27
- 238000007599 discharging Methods 0.000 title claims abstract description 24
- 239000002826 coolant Substances 0.000 claims abstract description 54
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 23
- 238000002955 isolation Methods 0.000 claims description 26
- 238000005192 partition Methods 0.000 claims description 2
- 239000013535 sea water Substances 0.000 description 7
- 239000007788 liquid Substances 0.000 description 5
- 238000001816 cooling Methods 0.000 description 3
- 230000006978 adaptation Effects 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 238000009833 condensation Methods 0.000 description 1
- 230000005494 condensation Effects 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 239000013505 freshwater Substances 0.000 description 1
- 238000000034 method Methods 0.000 description 1
Classifications
-
- 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
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/24—Promoting flow of the coolant
- G21C15/253—Promoting flow of the coolant for gases, e.g. blowers
-
- 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
Abstract
The invention discloses a secondary side passive waste heat discharging system of a marine floating nuclear power station, and relates to the technical field of reactor safety facilities. The secondary passive heat rejection subsystem includes a first primary coolant loop, a second steam-condensate loop, a steam generator, and a steam condensate tank. A first primary coolant loop circulates heat between the reactor and the steam generator to the steam generator, and a second steam-condensate loop absorbs heat from the primary coolant in the steam generator and circulates heat between the steam generator and the steam condensate to water in the steam condensate. Wherein the steam condenser is located above the steam generator, and the steam generator is located above the reactor. The system can passively utilize the secondary circulation to discharge the waste heat of the reactor under the condition that the draft of the offshore floating nuclear power station is shallow.
Description
Technical Field
The invention relates to the technical field of safety facilities of reactors, in particular to a secondary side passive waste heat discharging system of a marine floating nuclear power station.
Background
A floating nuclear power plant with a small-sized reactor may provide a supply of heat, electric energy, and fresh water for offshore oil rigs, islands, and the like. The method is closer to the demands of users, and has the advantages of small total investment, short construction period and great development potential.
The land nuclear power station adopts a primary side passive waste heat discharging system scheme, the scheme requires a main pipeline to be perforated, and high performance requirements are provided for the main pipeline. The floating nuclear power station can not use land to supply power like a land nuclear power station, when the floating nuclear power station adopts a land system scheme and is far away from land, the floating nuclear power station floats on the sea with complex environment, and when an accident situation such as full-platform outage occurs, active equipment in the traditional active waste heat discharging system can not work normally, so that the core waste heat after the unit is shut down can be accumulated, the safe operation of the unit is jeopardized, and finally the accident is caused.
If the passive waste heat discharging system uses seawater as a cold source: seawater flows through the shell side of the shell-and-tube condenser, the density of the heated seawater is reduced and the heated seawater is pushed to an upper pipe orifice, and the scheme of the condensing system requires that the position of the condenser is higher than a certain value of the liquid level of the steam generator, so that the high-pressure seawater-level condensation system has high requirements on the draft of the carried ship. The marine floating nuclear power station cannot adopt a passive waste heat discharging scheme for cooling seawater because of shallow draft, small arrangement space and high reliability requirement.
Disclosure of Invention
Aiming at the limitation of the use condition in the prior art, the invention aims to provide a secondary side passive waste heat discharging system of an offshore floating nuclear power station, which can be used for discharging waste heat in a reactor by passive secondary circulation under the condition that the draft of the offshore floating nuclear power station is shallow.
In order to achieve the above purpose, the invention adopts the following technical scheme:
the secondary side passive waste heat discharging system of the marine floating nuclear power station is characterized by comprising:
a reactor comprising at least one reactor main coolant inlet and at least one reactor main coolant outlet;
at least one secondary passive heat rejection subsystem, comprising,
-a steam generator comprising a steam generator primary side comprising a steam generator primary coolant inlet and a steam generator primary coolant outlet, and a steam generator secondary side comprising a steam generator condensate inlet and a steam generator steam outlet, the steam generator primary side being located above the reactor;
-a first main coolant loop comprising a main coolant cold leg, which is connected to the steam generator main coolant outlet, the reactor main coolant inlet, and a main coolant hot leg, which is connected to the reactor main coolant outlet, the steam generator main coolant inlet;
-a steam condenser tank comprising a steam condenser, a steam condenser steam inlet and a steam condenser condensate outlet, the steam condenser being located above the secondary side of the steam generator;
-a second steam-condensate loop comprising a steam pipe connected to the steam condenser steam inlet, the steam generator steam outlet, and a condensate pipe connected to the steam condenser condensate outlet, the steam generator condensate inlet.
On the basis of the technical scheme, a partition plate is arranged in the steam condensing box.
On the basis of the technical scheme, the upper part of the steam condensing box is opened.
On the basis of the technical scheme, the second steam-condensate loop is provided with an electromagnetic valve.
On the basis of the technical scheme, the second steam-condensate loop is further provided with a manual valve, and the manual valve is arranged in parallel with the electromagnetic valve.
On the basis of the technical scheme, the electromagnetic valve and the manual valve are arranged on the condensate pipe.
On the basis of the technical scheme, the second steam-condensate loop is provided with a steam isolation valve, a condensate isolation valve and a check valve.
On the basis of the technical scheme, the steam isolation valve is arranged on the steam pipe, and the condensate isolation valve and the check valve are arranged on the condensate pipe.
On the basis of the technical scheme, the steam isolation valve and the condensate isolation valve can be opened and closed through remote information.
On the basis of the technical scheme, the reactor, the first main coolant loop and the steam generator are positioned in the containment, and the steam condensing box is positioned outside the containment.
Compared with the prior art, the invention has the advantages that:
(1) According to the secondary side passive waste heat discharging system of the offshore floating nuclear power station, the natural circulation established by the driving pressure head is generated by utilizing equipment arrangement potential difference and medium density difference, and when all power supply loss accidents of the offshore floating nuclear power station occur, reactor core decay heat and sensible heat after reactor shutdown are continuously led out, so that the safety of the offshore floating nuclear power station is improved.
(2) Compared with the traditional primary side passive waste heat discharging system, the secondary side passive waste heat discharging system of the offshore floating nuclear power station can discharge the waste heat of the reactor through phase change heat exchange of the secondary side by utilizing the steam generator and the steam condensing box, so that the waste heat discharging capacity of the system is improved, holes are avoided on a main coolant pipeline, the technical risk of the offshore floating nuclear power station is reduced, and the economy of the power station is improved.
(3) The secondary side passive waste heat discharging system of the offshore floating nuclear power station can complete system circulation by reasonably arranging the position of the steam condensing box in the hull structure under the condition of being limited by the draft of the floating nuclear power station.
(4) The secondary side passive waste heat discharging system of the marine floating nuclear power station realizes the waste heat discharging function by reasonably arranging the equipment positions in a limited space.
Drawings
Fig. 1 is a schematic structural diagram of a secondary passive residual heat removal system of a marine floating nuclear power plant according to an embodiment of the present invention.
In the figure: 1-reactor, 2-main pump, 3-steam generator, 31-steam generator primary side, 32-steam generator secondary side, 4-steam condenser, 5-steam condensing tank, 6-main coolant cold section, 7-main coolant hot section, 8-steam pipe, 9-condensate pipe, 10-steam isolation valve, 11-solenoid valve, 12-manual valve, 13-condensate isolation valve, 14-check valve, 15-baffle, 16-inboard, 17-ballast tank, 18-containment.
Detailed Description
The present invention will be described in further detail with reference to the accompanying drawings and examples.
Referring to fig. 1, an embodiment of the present invention provides a secondary passive residual heat removal system for a floating nuclear power plant at sea, which includes a reactor 1 and at least one secondary passive heat removal subsystem.
Its secondary passive heat rejection subsystem comprises a steam generator 3, a steam condensate tank 5, a first main coolant loop and a second steam-condensate loop. The steam generator 3 comprises a steam generator primary side 31 and a steam generator secondary side 32, between which steam generator secondary side 32 and steam generator primary side 31 heat can be transferred. The primary coolant circulates between the primary side 31 of the steam generator and the reactor 1 to form a first primary coolant loop, discharging the residual heat of the reactor; the water circulates in liquid or gaseous form between the steam condensate tank 5 and the secondary side 32 of the steam generator forming a second steam-condensate circuit, removing the heat of the main coolant from the inside of the containment 18. Wherein the primary side 31 of the steam generator is located above the reactor 1 and the steam condenser 4 is located above the secondary side 32 of the steam generator.
Specifically, the primary side 31 of the steam generator is located above the reactor 1, and when the residual heat of the reactor 1 is released, the main coolant in the vicinity thereof is heated, the density becomes small, and flows upward; the heated primary coolant flows to the primary side 31 of the steam generator to transfer heat and become denser because the head flows back into the pressure reactor 1 to be heated to form a cycle. The pipeline of the reactor 1 flowing to the primary side 31 of the steam generator is called a main coolant heat section 7, the connection port of the main coolant heat section 7 and the reactor 1 is a main coolant outlet of the reactor, and the connection port of the main coolant heat section 7 and the primary side 31 of the steam generator is a main coolant inlet of the steam generator; the pipe line of the primary side 31 of the steam generator flowing to the reactor 1 is called a main coolant cold section 6, the connection port of the main coolant hot section 6 and the reactor 1 is a main coolant inlet of the reactor, and the connection port of the main coolant hot section 6 and the primary side 31 of the steam generator is a main coolant outlet of the steam generator. The steam condenser 4 is located above the secondary side 32 of the steam generator, so that the liquid level of condensed water in the steam condenser 5 is higher than the liquid level of condensed water in the secondary side 32 of the steam generator, the condensed water is converted into steam after the secondary side 32 of the steam generator absorbs heat released by the primary coolant on the primary side 31 of the steam generator and rises into the steam condenser 5, after the heat released by the steam condenser 5 is converted into condensed water, the liquid level difference flows back to the secondary side 32 of the steam generator to form a circulation, a pipeline of the secondary side 32 of the steam generator, which passes through the containment vessel 18 and flows to the steam condenser 5, is called a steam pipe 8, a connection port of the steam pipe 8 and the secondary side 32 of the steam generator is called a steam outlet of the steam generator, and a connection port of the steam pipe 8 and the condenser 5 is called a steam inlet of the condenser; the pipeline of the steam condensing box 5, which passes through the containment 18 and flows to the secondary side 32 of the steam generator, is called a condensate pipe 9, the connection port of the condensate pipe 9 and the secondary side 32 of the steam generator is a condensate water inlet of the steam generator, and the connection port of the condensate pipe 9 and the condensing box 5 is called a condensate water outlet of the condenser.
Wherein the steam condensing box 5 is located in the inter-board 16 of the floating nuclear power plant, and comprises a steam condenser 4, the steam passes through the steam condenser 4 to transfer heat to the water in the steam condensing box 5 to condense, and a baffle 15 is preferably arranged in the steam condensing box 5 to divide the steam condensing box 5 into one side with the steam condenser 4 and one side without the steam condenser 4. When the system is in operation, the water on one side of the steam condenser 4 in the steam condensing box 5 is heated and forms a cold-hot temperature difference with the water on the other side of the steam condenser 4, so that the flow of the water in the steam condensing box 5 is accelerated, and the heat exchange efficiency of the system is improved. The steam condensate tank 5 is preferably open above so that the water and the atmosphere are in direct contact, releasing the absorbed heat into the atmosphere.
During normal operation of the floating nuclear power plant, the system is in a standby state: referring to fig. 1, a main pump 2 provides kinetic energy to a first main coolant circuit; a solenoid valve 11 is provided on the second steam-condensate circuit, the solenoid valve 11 being in a closed state under normal power supply during normal operation. When all power supply loss accidents happen to the floating nuclear power station, the main pump 2 loses power and is only a channel of main coolant; the active waste heat discharging system and the main coolant system of the floating nuclear power station stop running, the reactor 1 is in emergency shutdown, but a large amount of reactor waste heat is still accumulated; the electromagnetic valve 11 is in an open state because of the loss of power supply, and the secondary side passive waste heat discharging system is automatically put into operation: the primary coolant absorbs heat at the reactor 1 side in the first primary coolant loop, flows to the steam generator primary side 31 of the steam generator 3, transfers heat to condensed water in the steam generator 3, and returns to the reactor 1 side. The condensed water in the steam generator 3 absorbs heat and is converted into steam, and the steam rises to the steam condenser 4 to be condensed and then flows back. The water in the steam condensate tank 5 absorbs heat and releases it to the atmosphere.
The solenoid valve 11 is preferably connected in parallel with a manual valve 12 which can be opened manually when the solenoid valve 11 fails or other reasons of the floating nuclear power plant require the secondary side passive residual heat removal system of the floating nuclear power plant of the present invention to be started.
The solenoid valve 11 and the manual valve 12, which are arranged in parallel, are preferably arranged on the line of the condensate pipe 9, the condensate being isolated from the steam generator 3 by the solenoid valve 11 and the manual valve 12 when the system is not in the active state.
The secondary side passive residual heat removal system of the floating nuclear power plant on the sea is preferably provided with a steam isolation valve 10, a condensate isolation valve 13 and a check valve 14. The steam isolation valve 10 is arranged on the pipeline of the steam pipe 8, the condensate isolation valve 13 is arranged on the condensate pipe 9, and the condensate isolation valve can isolate the steam generator from the damaged pipeline when the steam pipe 8, the condensate pipe 9 or the steam generator heat transfer pipe is broken, thereby indirectly playing a role in preventing radioactivity release. The check valve 14 is arranged on the condensed water pipe 9, so as to prevent the condensed water from leaking out of furnace water when the flow direction of the condensed water is reversed due to pressure and the system is leaked, and the steam isolation valve 10 and the condensed water isolation valve 13 can receive remote signals to control the on-off state. The steam isolation valve 10 and the condensate isolation valve 13 are closed when the system fails, isolating the steam generator 3 from the steam condensing tank 5.
The secondary passive residual heat removal system of the offshore floating nuclear power plant is preferably provided with a ballast water tank 17 below to keep the floating nuclear power plant stable.
In summary, since the offshore floating nuclear power plant cannot use the land power condition and the cooling environment, and does not have the condition that the draft of the conventional ship is large and the seawater can be directly used as the cooling source, the secondary passive waste heat discharging system of the offshore floating nuclear power plant takes away heat in the small space. The system equipment arrangement potential difference and the medium density difference generate natural circulation established by the driving pressure head, so that the reactor core decay heat and sensible heat after the reactor 1 is stopped are continuously led out, and the system has good feasibility and reliability.
The invention is not limited to the embodiments described above, but a number of modifications and adaptations can be made by a person skilled in the art without departing from the principle of the invention, which modifications and adaptations are also considered to be within the scope of the invention. What is not described in detail in this specification is prior art known to those skilled in the art.
Claims (8)
1. The secondary side passive waste heat discharging system of the marine floating nuclear power station is characterized by comprising:
a reactor (1) comprising at least one reactor main coolant inlet and at least one reactor main coolant outlet;
at least one secondary passive heat rejection subsystem, comprising,
-a steam generator (3) comprising a steam generator primary side (31) and a steam generator secondary side (32), the steam generator primary side (31) comprising a steam generator primary coolant inlet and a steam generator primary coolant outlet, the steam generator secondary side (32) comprising a steam generator condensate inlet and a steam generator steam outlet, the steam generator primary side (31) being located above the reactor (1);
-a first main coolant loop comprising a main coolant cold leg (6) and a main coolant hot leg (7), the main coolant cold leg (6) being in communication with the steam generator main coolant outlet, the reactor main coolant inlet, the main coolant hot leg (7) being in communication with the reactor main coolant outlet, the steam generator main coolant inlet;
-a steam condenser tank (5) comprising a steam condenser (4), a steam condenser steam inlet and a steam condenser condensate outlet, the steam condenser (4) being located above the steam generator secondary side (32);
-a second steam-condensate circuit comprising a steam pipe (8) and a condensate pipe (9), the steam pipe (8) being connected to a steam condenser steam inlet, a steam generator steam outlet, the condensate pipe (9) being connected to a steam condenser condensate outlet, a steam generator condensate inlet;
a steam isolation valve (10), a condensate isolation valve (13) and a check valve (14) are arranged on the second steam-condensate loop;
the steam isolation valve (10) is arranged on the steam pipe (8), the condensate isolation valve (13) and the check valve (14) are arranged on the condensate pipe (9), and the check valve (14) is arranged between the condensate isolation valve (13) and the steam generator (3);
when the steam pipe (8), the condensate pipe (9) or the steam generator (3) has break fault, the steam isolation valve (10) and the condensate isolation valve (13) are closed to isolate the steam generator (3) from the steam condensate tank (5);
the steam condensing box (5) is positioned in a space (16) between the floating nuclear power stations;
and a ballast water tank (17) is arranged below the secondary side passive waste heat discharging system of the offshore floating nuclear power station.
2. The secondary side passive residual heat removal system of a floating offshore nuclear power plant of claim 1, wherein: a partition plate (15) is arranged in the steam condensing box (5).
3. The secondary side passive residual heat removal system of a floating offshore nuclear power plant of claim 1, wherein: and an opening is formed above the steam condensing box (5).
4. The secondary side passive residual heat removal system of a floating offshore nuclear power plant of claim 1, wherein: an electromagnetic valve (11) is arranged on the second steam-condensate loop.
5. The secondary side passive residual heat removal system of a floating offshore nuclear power plant of claim 4, wherein: the second steam-condensate loop is also provided with a manual valve (12), and the manual valve (12) is arranged in parallel with the electromagnetic valve (11).
6. The secondary side passive residual heat removal system of a floating offshore nuclear power plant of claim 5, wherein: the electromagnetic valve (11) and the manual valve (12) are arranged on the condensate pipe (9).
7. The secondary side passive residual heat removal system of a floating offshore nuclear power plant of claim 1, wherein: the steam isolation valve (10) and the condensate isolation valve (13) can be opened and closed through remote information.
8. The secondary side passive residual heat removal system of a floating offshore nuclear power plant of claim 1, wherein: the reactor (1), the first main coolant loop and the steam generator (3) are located inside the containment, and the steam condensing tank (5) is located outside the containment.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201710740701.2A CN107403650B (en) | 2017-08-25 | 2017-08-25 | Secondary side passive waste heat discharging system of offshore floating nuclear power station |
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| CN201710740701.2A CN107403650B (en) | 2017-08-25 | 2017-08-25 | Secondary side passive waste heat discharging system of offshore floating nuclear power station |
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| CN107403650A CN107403650A (en) | 2017-11-28 |
| CN107403650B true CN107403650B (en) | 2023-11-03 |
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| CN110085334B (en) * | 2019-03-28 | 2022-06-14 | 中国船舶重工集团公司第七一九研究所 | Heat pipe type passive residual heat removal system |
| WO2021109136A1 (en) * | 2019-12-06 | 2021-06-10 | 中广核研究院有限公司 | Passive secondary side waste heat removal system for nuclear power plant |
| CN112768095A (en) * | 2021-01-25 | 2021-05-07 | 中国船舶重工集团公司第七一九研究所 | Containment shielding and cooling system for marine nuclear power platform |
| CN113345610A (en) * | 2021-05-08 | 2021-09-03 | 中国舰船研究设计中心 | Passive residual heat removal system of heat pipe reactor and control method thereof |
| CN114333545A (en) * | 2021-12-08 | 2022-04-12 | 中国船舶重工集团公司第七一九研究所 | Combined vertical natural circulation steam generator's experimental analog body |
| CN115107947B (en) * | 2022-06-20 | 2023-11-14 | 中核海洋核动力发展有限公司 | Nuclear power ship anti-rolling water tank with pressure-restraining spraying function |
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