CN107403650A - The Passive residual heat removal system of floating nuclear power plant - Google Patents
The Passive residual heat removal system of floating nuclear power plant Download PDFInfo
- Publication number
- CN107403650A CN107403650A CN201710740701.2A CN201710740701A CN107403650A CN 107403650 A CN107403650 A CN 107403650A CN 201710740701 A CN201710740701 A CN 201710740701A CN 107403650 A CN107403650 A CN 107403650A
- Authority
- CN
- China
- Prior art keywords
- steam
- steam generator
- main coolant
- nuclear power
- power plant
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Granted
Links
- 239000002826 coolant Substances 0.000 claims abstract description 54
- 238000001816 cooling Methods 0.000 claims abstract description 34
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 27
- 238000000605 extraction Methods 0.000 claims abstract description 6
- 238000006243 chemical reaction Methods 0.000 claims description 4
- 238000009833 condensation Methods 0.000 abstract description 4
- 230000005494 condensation Effects 0.000 abstract description 4
- 238000005516 engineering process Methods 0.000 abstract description 2
- 239000002918 waste heat Substances 0.000 abstract 1
- 239000007788 liquid Substances 0.000 description 5
- 239000013535 sea water Substances 0.000 description 5
- 238000007599 discharging Methods 0.000 description 4
- 239000003795 chemical substances by application Substances 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 239000002699 waste material Substances 0.000 description 2
- 238000010521 absorption reaction Methods 0.000 description 1
- 238000009825 accumulation Methods 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 230000036461 convulsion Effects 0.000 description 1
- 238000005553 drilling Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000005611 electricity Effects 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 238000002955 isolation Methods 0.000 description 1
- 230000006641 stabilisation Effects 0.000 description 1
- 238000011105 stabilization Methods 0.000 description 1
- 238000010025 steaming 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
Landscapes
- 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
The invention discloses a kind of Passive residual heat removal system of floating nuclear power plant, is related to reactor safety facility technology field, including a reactor, at least one secondary passive heat extraction subsystem.Secondary passive heat extraction subsystem includes the first main coolant loop, the second steam condensation water loop, steam generator and steam cooling cylinder.First main coolant loop circulating transfer heat to steam generator, second steam condensation water loop between reactor and steam generator absorbs the heat of Main Coolant in steam generator and the water transferred heat in steam cooling cylinder is circulated between steam generator and steam cooling cylinder.Wherein steam condenser is located above steam generator, and steam generator is located above reactor.The system being capable of the at sea passive waste heat that reactor is discharged using secondary cycle in the case of floating nuclear power plant shallower draft.
Description
Technical field
The present invention relates to the safety devices technical field of reactor, and in particular to a kind of secondary side of floating nuclear power plant
Heat Discharging System of Chinese.
Background technology
The floating nuclear power plant for carrying Small reactor can be that offshore drilling platformses and island etc. are supplied to heat, electric energy
Source supplies and water supply.It is closer to user's request and gross investment is small, construction period is short, and development potentiality is huge.
Land nuclear power station uses primary side Heat Discharging System of Chinese scheme more, and program demand main pipeline perforate is right
Main pipeline proposes higher performance requirement.Floating nuclear power plant equally uses land power supply without the land nuclear power station of the image of Buddha, works as floating
Nuclear power station uses land system schema, and it is away from land, swims in the complicated sea of environment, breaks there is such as full platform
During the accident conditions of electricity, active equipment in traditional active residual heat removal system can not normal work, unit may be caused to stop
Residual heat of nuclear core accumulation after heap, endangers the safe operation of unit, ultimately causes accident.
If Heat Discharging System of Chinese is to use sea water as low-temperature receiver：Seawater flows through the shell-side of shell-and-tube cooler,
Density reduces after heated is pushed into upper orifice by rear seawater, and such condenser system scheme requires that the position of condenser is higher than steam
Generator liquid level certain value, there is higher requirement to the shipping draft of carrying.Floating nuclear power plant is because draft
It is shallow, arrangement space is small, reliable request is high, can not use seawater cooling passive residual heat removal scheme.
The content of the invention
For the limitation in use condition in the prior art, it is an object of the invention to provide a kind of floating nuclear power plant
Passive residual heat removal system, can utilization passive in the case of floating nuclear power plant shallower draft at sea it is secondary
Circulate the Residual heat removal in reactor.
To achieve the above objectives, the present invention adopts the technical scheme that：
A kind of Passive residual heat removal system of floating nuclear power plant, it is characterised in that it includes：
One reactor, it includes at least one reactor Main Coolant entrance and at least one reactor Main Coolant goes out
Mouthful；
At least one secondary passive heat extraction subsystem, it includes,
- steam generator, it includes primary side of steam generator and steam generator secondary side, the steam generator one
Secondary side includes steam generator Main Coolant entrance and steam generator Main Coolant exports, the steam generator secondary side bag
Steam generator condensed water entrance and steam generator steam (vapor) outlet are included, the primary side of steam generator is located on reactor
Side；
- the first main coolant loop, it includes cold section of Main Coolant and Main Coolant hot arc, cold section of the Main Coolant with
The outlet of steam generator Main Coolant, reactor Main Coolant entrance connect, the Main Coolant hot arc and the main cooling of reactor
Agent outlet, steam generator Main Coolant entrance connect；
- steam cooling cylinder, it includes steam condenser, steam condenser vapor entrance and the outlet of steam condenser condensate,
The steam condenser is located above steam generator secondary side；
- the second steam-condensate loop, it includes steam pipe and condensate pipe, the steam pipe and steam condenser vapor
Entrance, steam generator steam (vapor) outlet connect, the condensate pipe and with steam condenser condensate outlet, steam generator condense
Water inlet connects.
On the basis of above-mentioned technical proposal, dividing plate is provided with the steam cooling cylinder.
On the basis of above-mentioned technical proposal, the steam cooling cylinder upper opening.
On the basis of above-mentioned technical proposal, second steam-condensate is provided with magnetic valve on loop.
On the basis of above-mentioned technical proposal, second steam-condensate loop is additionally provided with hand-operated valve, the hand-operated valve with
The magnetic valve is arranged in parallel.
On the basis of above-mentioned technical proposal, the magnetic valve and hand-operated valve are arranged on the condensate pipe.
On the basis of above-mentioned technical proposal, second steam-condensate loop is provided with steam isolating, condensate is isolated
Valve and check-valves.
On the basis of above-mentioned technical proposal, the steam isolating is on the steam pipe, the condensate isolating valve and only
Valve is returned on condensate pipe.
On the basis of above-mentioned technical proposal, the steam isolating and condensate isolating valve can be carried out by remote information
Open and close.
On the basis of above-mentioned technical proposal, the reactor, the first main coolant loop and steam generator are positioned at peace
In full shell, steam cooling cylinder is located at outside containment.
Compared with prior art, the advantage of the invention is that：
(1) Passive residual heat removal system of floating nuclear power plant of the present invention, using equipment arrange potential difference and
Media density difference produces the Natural Circulation that drive ram is established, when at sea floating nuclear power plant all power loses accident generation,
Reactor core decay heat after reactor shutdown and sensible heat are persistently exported, improve the security of floating nuclear power plant.
(2) Passive residual heat removal system of floating nuclear power plant of the present invention is non-compared to traditional primary side
Active residual heat removal system, steam generator and steam cooling cylinder can be utilized by the phase-change heat-exchange of secondary side by reactor waste
Discharge, improves the Residual heat removal ability of system, while avoids the perforate on Main Coolant pipeline, reduces marine floating core
The technical risk in power station, improve the economy in power station.
(3) Passive residual heat removal system of floating nuclear power plant of the present invention is eaten by floating type nuclear power station
Under the limited case of water depth, system circulation can be completed by the position of the reasonable Arrangement steam cooling cylinder in Ship Structure.
(4) Passive residual heat removal system of floating nuclear power plant of the present invention passes through reasonable in the confined space
Arrange that each device location realizes Residual heat removal function.
Brief description of the drawings
Fig. 1 is the structural representation of the Passive residual heat removal system of floating nuclear power plant of the embodiment of the present invention
Figure.
In figure：1- reactors, 2- main pumps, 3- steam generators, 31- primary side of steam generator, 32- steam generators two
Secondary side, 4- steam condensers, 5- steam cooling cylinders, cold section of 6- Main Coolants, 7- Main Coolant hot arcs, 8- steam pipes, 9- condensations
Water pipe, 10- steam isolatings, 11- magnetic valves, 12- hand-operated valves, 13- condensate isolating valves, 14- check-valves, 15- dividing plates, the 16- sides of a ship
Between, 17- ballast tanks, 18- containments.
Embodiment
The present invention is described in further detail below in conjunction with drawings and Examples.
Shown in Figure 1, the embodiment of the present invention provides a kind of secondary side passive residual heat removal of floating nuclear power plant
System, it includes a reactor 1 and at least one secondary passive heat extraction subsystem.
Its secondary passive heat extraction subsystem include steam generator 3, steam cooling cylinder 5, the first main coolant loop and
Second steam-condensate loop.Steam generator 3 includes primary side of steam generator 31 and steam generator secondary side 32, steam
Heat can be transmitted between generator secondary side 32 and primary side of steam generator 31.Main Coolant is in primary side of steam generator
Circulation forms the first main coolant loop between 31 and reactor 1, by the Residual heat removal of reactor；Water is with liquid or gaseous shape
State circulates between steam cooling cylinder 5 and steam generator secondary side 32 forms the second steam-condensate loop, out of containment 18
Portion is discharged by the heat of Main Coolant.Wherein primary side of steam generator 31 is located at the top of reactor 1, and steam condenser 4 is located at
The top of steam generator secondary side 32.
Specifically, primary side of steam generator 31 is located at the top of reactor 1, when the Decay heat removal of reactor 1 comes out, its is attached
Near Main Coolant is heated, and density diminishes, and is flowed up；Main Coolant after heating flows to primary side of steam generator 31
Heat is transmitted, density becomes big, because potential difference flowing, which returns to be heated in pressure reaction heap 1, forms circulation.Its reactor 1 flow direction is steamed
The pipeline of vapour generator primary side 31 is referred to as Main Coolant hot arc 7, and Main Coolant hot arc 7 is reaction with the connector of reactor 1
Heap Main Coolant exports, and Main Coolant hot arc 7 is steam generator Main Coolant with the connector of primary side of steam generator 31
Entrance；The pipeline that primary side of steam generator 31 flows to reactor 1 is referred to as cold section 6 of Main Coolant, and Main Coolant hot arc 6 is the same as reaction
The connector of heap 1 is reactor Main Coolant entrance, and Main Coolant hot arc 6 is steaming with the connector of primary side of steam generator 31
Vapour generator Main Coolant exports.Steam condenser 4 is located at the top of steam generator secondary side 32, therefore in steam cooling cylinder 5
The liquid level of condensed water is higher than the liquid level of condensed water in steam generator secondary side 32, and condensed water is inhaled in steam generator secondary side 32
Receive Main Coolant and be converted into steam after the heat that primary side of steam generator 31 discharges, and rise in steam cooling cylinder 5,
In steam cooling cylinder 5 discharge converting heat be condensed water after because height of liquid level difference is back to the shape of steam generator secondary side 32
Into circulation, the pipeline that its steam generator secondary side 32 flows to steam cooling cylinder 5 through containment 18 is referred to as steam pipe 8, steam
Pipe 8 is steam generator steam (vapor) outlet with the connector of steam generator secondary side 32, connector of the steam pipe 8 with cooling cylinder 5
Referred to as condenser vapor entrance；The pipeline that steam cooling cylinder 5 flows to steam generator secondary side 32 through containment 18 is referred to as cold
Condensate pipe 9, condensate pipe 9 are steam generator condensed water entrance with the connector of steam generator secondary side 32, condensate pipe 9
Connector with cooling cylinder 5 is referred to as the outlet of condenser condensate.
Wherein steam cooling cylinder 5 16 between the floating nuclear power plant side of a ship in, it includes steam condenser 4, and steam passes through steam
The water condensation transferred heat to after condenser 4 in steam cooling cylinder 5 is got off, and dividing plate 15 is preferably provided with steam cooling cylinder 5, will
Steam cooling cylinder 5 divides to have the side of steam condenser 4 and the side without steam condenser 4.When system operation, steam is cold
The heated water with no side of steam condenser 4 of water of the side of steam condenser 4 forms the cold and hot temperature difference in solidifying case 5, so as to accelerate
The flowing of water in steam cooling cylinder 5, improve the heat exchange efficiency of system.5 preferred upper opening of steam cooling cylinder so that water and
Air is directly contacted, and the heat of absorption is discharged into air.
During normal operation, the system is in stand-by state to floating nuclear power plant：Shown in Figure 1, main pump 2 is that the first master is cold
But agent loop provides kinetic energy；Magnetic valve 11 is set on the second steam-condensate loop, in magnetic valve 11 during normal operation just
It is closed under normal electric power thus supplied.When all power, which occurs, for floating nuclear power plant loses accident, main pump 2 runs out of steam, only
For the passage of Main Coolant；The active residual heat removal system and main coolant system of floating nuclear power plant are out of service, and reactor 1 is tight
Jerk heap, but still there is substantial amounts of reactor waste to accumulate；Magnetic valve 11 is in opening, secondary side because losing power supply
Heat Discharging System of Chinese automatically engages operation：Main Coolant side of reactor 1 in the first main coolant loop absorbs heat,
The primary side of steam generator 31 of steam generator 3 is flowed to, is returned to after the condensed water transferred heat in steam generator 3
The side of reactor 1.Condensed water in steam generator 3 is converted into steam after absorbing heat, rises in steam condenser 4 after condensing
Backflow.Water in steam cooling cylinder 5 absorbs heat and discharged to air.
The preferred hand-operated valve 12 in parallel of magnetic valve 11, when the failure of magnetic valve 11 or floating nuclear power plant other reasonses need
, can be with the manually opened valve when starting the Passive residual heat removal system of floating nuclear power plant of the present invention.
The magnetic valve 11 and hand-operated valve 12 being arranged in parallel are preferably disposed on the pipeline of condensate pipe 9, when the system does not enable
During state, condensed water is isolated by magnetic valve 11 and hand-operated valve 12 with steam generator 3.
The Passive residual heat removal system of floating nuclear power plant is preferably provided with steam isolating 10, condensate isolation
Valve 13 and check-valves 14.Its steam isolating 10 is arranged at the pipeline of steam pipe 8, and condensate isolating valve 13 is arranged at condensate pipe 9, its
Steam generator and damaged pipeline can be isolated in steam pipe 8, condensate pipe 9 or steam generator tube rupture, picked up
To the effect for preventing radioactivity release.Its check-valves 14 is arranged at condensate pipe 9, for preventing condensed water because pressure considerations stream
To stove leaked water when reversing and system leaks, steam isolating 10 and condensate isolating valve 13 can receive remote signal control
On off state processed.In the system failure, steam isolating 10 and condensate isolating valve 13 are closed, and isolate steam generator 3 and steam
Cooling cylinder 5.
The preferred lower section of the Passive residual heat removal system of floating nuclear power plant is provided with ballast tank 17, keeps floating
The stabilization in kinetonucleus power station.
In summary, because floating nuclear power plant can not use land power conditions and cooler environment, and do not possess biography
System naval vessel draft is big, can directly use condition of the seawater as cooling source, and the secondary side of this floating nuclear power plant is non-
Aforesaid way that active residual heat removal system uses in less space takes away heat.The system equipment arranges potential difference and Jie
Matter density contrast produces the Natural Circulation that drive ram is established, and the reactor core decay heat after the shutdown of reactor 1 and sensible heat are persistently exported,
With good feasibility and reliability.
The present invention is not limited to the above-described embodiments, for those skilled in the art, is not departing from
On the premise of the principle of the invention, some improvements and modifications can also be made, these improvements and modifications are also considered as the protection of the present invention
Within the scope of.The content not being described in detail in this specification belongs to prior art known to professional and technical personnel in the field.
Claims (10)
1. a kind of Passive residual heat removal system of floating nuclear power plant, it is characterised in that it includes：
One reactor (1), it includes at least one reactor Main Coolant entrance and at least one reactor Main Coolant goes out
Mouthful；
At least one secondary passive heat extraction subsystem, it includes,
- steam generator (3), it includes primary side of steam generator (31) and steam generator secondary side (32), the steam
Generator primary side (31) includes steam generator Main Coolant entrance and steam generator Main Coolant exports, the steam hair
Raw device secondary side (32) includes steam generator condensed water entrance and steam generator steam (vapor) outlet, and the steam generator is once
Side (31) is located above reactor (1)；
- the first main coolant loop, it includes Main Coolant cold section (6) and Main Coolant hot arc (7), cold section of the Main Coolant
(6) connect with the outlet of steam generator Main Coolant, reactor Main Coolant entrance, the Main Coolant hot arc (7) and reaction
The outlet of heap Main Coolant, steam generator Main Coolant entrance connect；
- steam cooling cylinder (5), it includes steam condenser (4), steam condenser vapor entrance and steam condenser condensate and gone out
Mouthful, the steam condenser (4) is located above steam generator secondary side (32)；
- the second steam-condensate loop, it includes steam pipe (8) and condensate pipe (9), the steam pipe (8) and steam condenser
Steam inlet, steam generator steam (vapor) outlet connect, the condensate pipe (9) and with steam condenser condensate outlet, steam send out
Raw device condensing water inlet connects.
2. the Passive residual heat removal system of floating nuclear power plant as claimed in claim 1, it is characterised in that：Institute
State in steam cooling cylinder (5) and be provided with dividing plate (15).
3. the Passive residual heat removal system of floating nuclear power plant as claimed in claim 1, it is characterised in that：Institute
State steam cooling cylinder (5) upper opening.
4. the Passive residual heat removal system of floating nuclear power plant as claimed in claim 1, it is characterised in that：Institute
State and magnetic valve (11) is provided with the second steam-condensate loop.
5. the Passive residual heat removal system of floating nuclear power plant as claimed in claim 4, it is characterised in that：Institute
State the second steam-condensate loop and be additionally provided with hand-operated valve (12), the hand-operated valve (12) is arranged in parallel with the magnetic valve (11).
6. the Passive residual heat removal system of floating nuclear power plant as claimed in claim 5, it is characterised in that：Institute
State magnetic valve (11) and hand-operated valve (12) is arranged on the condensate pipe (9).
7. the Passive residual heat removal system of floating nuclear power plant as claimed in claim 1, it is characterised in that：Institute
State the second steam-condensate loop and be provided with steam isolating (10), condensate isolating valve (13) and check-valves (14).
8. the Passive residual heat removal system of floating nuclear power plant as claimed in claim 7, it is characterised in that：Institute
Steam isolating (10) is stated on steam pipe (8), the condensate isolating valve (13) and check-valves (14) are located at condensate pipe (9)
On.
9. the Passive residual heat removal system of floating nuclear power plant as claimed in claim 8, it is characterised in that：Institute
Stating steam isolating (10) and condensate isolating valve (13) can be opened and closed by remote information.
10. the Passive residual heat removal system of floating nuclear power plant as claimed in claim 1, it is characterised in that：
The reactor (1), the first main coolant loop and steam generator (3) are located in containment, and steam cooling cylinder (5) is positioned at peace
Outside full shell.
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 |
Applications Claiming Priority (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 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN107403650A true CN107403650A (en) | 2017-11-28 |
| CN107403650B CN107403650B (en) | 2023-11-03 |
Family
ID=60397276
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201710740701.2A Active CN107403650B (en) | 2017-08-25 | 2017-08-25 | Secondary side passive waste heat discharging system of offshore floating nuclear power station |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN107403650B (en) |
Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110085334A (en) * | 2019-03-28 | 2019-08-02 | 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 |
| 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 |
| 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 |
| 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 |
| CN115107947A (en) * | 2022-06-20 | 2022-09-27 | 中核海洋核动力发展有限公司 | Nuclear power ship anti-rolling water tank with suppression spraying function |
| CN117095840A (en) * | 2023-06-16 | 2023-11-21 | 哈尔滨工程大学 | Self-supporting passive waste heat discharging system of floating nuclear power station |
Citations (18)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5106571A (en) * | 1989-03-20 | 1992-04-21 | Wade Gentry E | Containment heat removal system |
| KR970051468A (en) * | 1995-12-01 | 1997-07-29 | 윤덕용 | Passive containment chiller of nuclear reactor |
| KR19980029457A (en) * | 1996-10-26 | 1998-07-25 | 윤덕용 | Passive secondary side condensation system of pressurized water reactor |
| JP2003043176A (en) * | 2001-07-30 | 2003-02-13 | Mitsubishi Heavy Ind Ltd | Decay heat removing device of cooling system integrated nuclear reactor |
| CN102867550A (en) * | 2012-08-20 | 2013-01-09 | 中国核电工程有限公司 | Passive heat removal device for dealing with station blackout accident |
| US20130077730A1 (en) * | 2011-07-20 | 2013-03-28 | Hitachi-Ge Nuclear Energy, Ltd. | Nuclear Power Plant |
| US20130259183A1 (en) * | 2008-02-29 | 2013-10-03 | Kabushiki Kaisha Toshiba | Passive cooling and depressurization system and pressurized water nuclear power plant |
| CN103456375A (en) * | 2013-07-31 | 2013-12-18 | 中科华核电技术研究院有限公司 | Secondary-side residual heat removal system with passive flow control device |
| CN203397712U (en) * | 2013-07-31 | 2014-01-15 | 中科华核电技术研究院有限公司 | Secondary side residual heat removal system with passive flow control device |
| CN103617815A (en) * | 2013-12-05 | 2014-03-05 | 哈尔滨工程大学 | Passive residual heat exhausting system of pressurized water reactor nuclear power plant |
| US20140362968A1 (en) * | 2012-01-18 | 2014-12-11 | Societe Technique Pour L'energie Atomique Technicatome | System for removing the residual power of a pressurised water nuclear reactor |
| KR20150014787A (en) * | 2013-07-30 | 2015-02-09 | 한국원자력연구원 | Passive safety system and nuclear reactor having the same |
| CN104361914A (en) * | 2014-11-19 | 2015-02-18 | 中科华核电技术研究院有限公司 | Passive safe cooling system |
| CN205035104U (en) * | 2015-08-31 | 2016-02-17 | 上海核工程研究设计院 | Nuclear power station sea water desalination |
| WO2016078285A1 (en) * | 2014-11-19 | 2016-05-26 | 中科华核电技术研究院有限公司 | Secondary side passive waste heat removal system |
| KR101624561B1 (en) * | 2015-01-29 | 2016-05-26 | 한국원자력연구원 | Containment cooling system and nuclear power plant having the same |
| CN105957567A (en) * | 2016-05-06 | 2016-09-21 | 中国核动力研究设计院 | Steam generator secondary side passive residual heat removal system |
| CN205656860U (en) * | 2016-01-20 | 2016-10-19 | 新核（北京）能源科技有限公司 | Active discharge system of reactor core waste heat non - is piled in heat supply of low temperature nuclear |
-
2017
- 2017-08-25 CN CN201710740701.2A patent/CN107403650B/en active Active
Patent Citations (18)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5106571A (en) * | 1989-03-20 | 1992-04-21 | Wade Gentry E | Containment heat removal system |
| KR970051468A (en) * | 1995-12-01 | 1997-07-29 | 윤덕용 | Passive containment chiller of nuclear reactor |
| KR19980029457A (en) * | 1996-10-26 | 1998-07-25 | 윤덕용 | Passive secondary side condensation system of pressurized water reactor |
| JP2003043176A (en) * | 2001-07-30 | 2003-02-13 | Mitsubishi Heavy Ind Ltd | Decay heat removing device of cooling system integrated nuclear reactor |
| US20130259183A1 (en) * | 2008-02-29 | 2013-10-03 | Kabushiki Kaisha Toshiba | Passive cooling and depressurization system and pressurized water nuclear power plant |
| US20130077730A1 (en) * | 2011-07-20 | 2013-03-28 | Hitachi-Ge Nuclear Energy, Ltd. | Nuclear Power Plant |
| US20140362968A1 (en) * | 2012-01-18 | 2014-12-11 | Societe Technique Pour L'energie Atomique Technicatome | System for removing the residual power of a pressurised water nuclear reactor |
| CN102867550A (en) * | 2012-08-20 | 2013-01-09 | 中国核电工程有限公司 | Passive heat removal device for dealing with station blackout accident |
| KR20150014787A (en) * | 2013-07-30 | 2015-02-09 | 한국원자력연구원 | Passive safety system and nuclear reactor having the same |
| CN203397712U (en) * | 2013-07-31 | 2014-01-15 | 中科华核电技术研究院有限公司 | Secondary side residual heat removal system with passive flow control device |
| CN103456375A (en) * | 2013-07-31 | 2013-12-18 | 中科华核电技术研究院有限公司 | Secondary-side residual heat removal system with passive flow control device |
| CN103617815A (en) * | 2013-12-05 | 2014-03-05 | 哈尔滨工程大学 | Passive residual heat exhausting system of pressurized water reactor nuclear power plant |
| CN104361914A (en) * | 2014-11-19 | 2015-02-18 | 中科华核电技术研究院有限公司 | Passive safe cooling system |
| WO2016078285A1 (en) * | 2014-11-19 | 2016-05-26 | 中科华核电技术研究院有限公司 | Secondary side passive waste heat removal system |
| KR101624561B1 (en) * | 2015-01-29 | 2016-05-26 | 한국원자력연구원 | Containment cooling system and nuclear power plant having the same |
| CN205035104U (en) * | 2015-08-31 | 2016-02-17 | 上海核工程研究设计院 | Nuclear power station sea water desalination |
| CN205656860U (en) * | 2016-01-20 | 2016-10-19 | 新核（北京）能源科技有限公司 | Active discharge system of reactor core waste heat non - is piled in heat supply of low temperature nuclear |
| CN105957567A (en) * | 2016-05-06 | 2016-09-21 | 中国核动力研究设计院 | Steam generator secondary side passive residual heat removal system |
Non-Patent Citations (1)
| Title |
|---|
| 史觊, 付明玉, 边信黔, 孙建华: "船舶核动力装置运行管理专家系统", 船舶工程, no. 02, pages 44 - 48 * |
Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110085334A (en) * | 2019-03-28 | 2019-08-02 | 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 |
| CN115107947A (en) * | 2022-06-20 | 2022-09-27 | 中核海洋核动力发展有限公司 | Nuclear power ship anti-rolling water tank with suppression spraying function |
| 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 |
| CN117095840A (en) * | 2023-06-16 | 2023-11-21 | 哈尔滨工程大学 | Self-supporting passive waste heat discharging system of floating nuclear power station |
| CN117095840B (en) * | 2023-06-16 | 2024-05-10 | 哈尔滨工程大学 | Self-supporting passive waste heat discharging system of floating nuclear power station |
Also Published As
| Publication number | Publication date |
|---|---|
| CN107403650B (en) | 2023-11-03 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN107403650A (en) | The Passive residual heat removal system of floating nuclear power plant | |
| CN105810256B (en) | A kind of nuclear power station passive residual heat removal system | |
| CN202887748U (en) | Passive heat discharge device for dealing with plant switch-off accident | |
| WO2016078421A1 (en) | Passive safe cooling system | |
| CN106816186A (en) | A kind of Integrated PWR Heat Discharging System of Chinese based on separate heat pipe | |
| CN105810257B (en) | A kind of passive nuclear power station pressure release condensation heat exchange system | |
| CN105957567B (en) | A kind of steam generator secondary side Heat Discharging System of Chinese | |
| CN107644693B (en) | Naval reactor and once through steam generator Passive residual heat removal system | |
| CN107464590A (en) | Marine PWR Passive residual heat removal system | |
| CN204480678U (en) | A kind of nuclear power station Heat Discharging System of Chinese | |
| CN104733060A (en) | Passive residual heat removal system of marine nuclear power device | |
| CN107393605A (en) | The passive air-cooling apparatus and method of a kind of modular small nuclear reactor | |
| GB2531190A (en) | Passive concrete containment cooling system | |
| CN104916334A (en) | Separated heat pipe type passive residual heat removal system for pressurized water reactor nuclear power plant | |
| WO2014048289A1 (en) | Combined active and passive secondary-side reactor core heat removal apparatus | |
| CN107833641A (en) | A kind of marine PWR seawater cools down Passive residual heat removal system | |
| US20230197300A1 (en) | Passive waste heat removal system on secondary side of marine environmental reactor | |
| CN109545401A (en) | A kind of lead base fast reactor out-pile passive residual heat removal system | |
| CN107420878A (en) | It is a kind of to carry out vapour, heat, the system of CCHP using nuclear energy | |
| CN106297915B (en) | Passive safety injection system for nuclear power station | |
| US20230223160A1 (en) | Reactor secondary side passive residual heat removal system | |
| CN107833642A (en) | Heat exchanger is located at the outer marine PWR Passive residual heat removal system of water tank | |
| CN107665742A (en) | It is active with the passive naval reactor being combined meet an urgent need residual heat removal system | |
| CN207250149U (en) | The Passive residual heat removal system of floating nuclear power plant | |
| CN207624389U (en) | Heat exchanger is located at the outer marine PWR Passive residual heat removal system of water tank |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |