CN110097982A - A kind of injection of npp safety and residual heat removal system - Google Patents
A kind of injection of npp safety and residual heat removal system Download PDFInfo
- Publication number
- CN110097982A CN110097982A CN201910384350.5A CN201910384350A CN110097982A CN 110097982 A CN110097982 A CN 110097982A CN 201910384350 A CN201910384350 A CN 201910384350A CN 110097982 A CN110097982 A CN 110097982A
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- Prior art keywords
- safety injection
- pressure
- infusion circuit
- outlet line
- tank
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Classifications
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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
-
- 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
- G21C15/182—Emergency cooling arrangements; Removing shut-down heat comprising powered means, e.g. pumps
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention belongs to nuclear safety control technology field, it is related to a kind of npp safety injection and residual heat removal system.The system includes high-pressure safety injection case infusion circuit, safety injection tank infusion circuit, safety injection pump infusion circuit, reactor pressure vessel.System of the invention can guarantee the safety of nuclear power plant when accident occurs for reactor, greatly improve the safety of nuclear power plant, combine residual heat removal system function when reactor start and stop heap, to greatly save the investment of nuclear power plant, improve the economy of nuclear power plant.
Description
Technical field
The invention belongs to nuclear safety control technology field, it is related to a kind of npp safety injection and residual heat removal system.
Background technique
Safety injection system belongs to nuclear power plant's engineered safeguards features, and loss of-coolant accident (LOCA) or master occurs in reactor coolant loop
When the accidents such as pipeline breaking occur for vapour system, reactor core emergency refrigerating function is completed, prevents reactor core from melting down, guarantees nuclear power plant
Safety.The system only use when accident occurs for nuclear power plant.
About safety injection system, there are some reports in the prior art.
Such as Chinese patent application 201310301651.X discloses a kind of non-passive safety note using Safety Injection case
Enter system.Passive safety injection system includes: containment;Reactor is mounted in containment;Safety Injection case, peace
In containment;Safety Injection pipeline, between reactor or reactor coolant loop and each Safety Injection case, with
The water being stored in Safety Injection case is guided when reducing the water level in reactor due to generation coolant loss accident
Into reactor;And pressure-equalizing line, between reactor or reactor coolant loop and Safety Injection case, to work as
Occur coolant loss accident when future autothermal reactor high-temperature steam be directed to Safety Injection case.Safety Injection pipeline is at it
It is upper that there is throttle orifice and check-valves, and pressure-equalizing line has throttle orifice and isolating valve on it.In Safety Injection case
Water steadily flows into a few hours into reactor.
For another example Chinese patent application 201510272061.8 discloses safety injection system, including middle pressure peace note subsystem,
Low pressure peace note subsystem and safety injection tank inject subsystem, and middle pressure pacifies note subsystem and one end of low pressure peace note subsystem passes through setting
Material-changing water tank water intaking in containment, the other end supply water to cold section of primary Ioops and hot arc;Middle pressure peace note subsystem and low pressure peace
Note subsystem respectively includes A column and B column;The A column of middle pressure peace note subsystem and the A column of low pressure peace note subsystem respectively include setting and exist
Safety injection pump and A2 low pressure safety injection pump and connecting pipeline are pressed in A1 outside containment;The B column and low pressure peace note of middle pressure peace note subsystem
The B column of subsystem, which respectively include being arranged in, presses safety injection pump and B2 low pressure safety injection pump and connecting pipeline in the B1 outside containment.
Residual heat removal system major function is during nuclear power plant's shutdown, through steam generator tentatively cooling and decompression
Afterwards, heat is discharged from reactor core and reactor coolant loop.
About residual heat removal system, there are also reports in the prior art.
Such as Chinese patent application 201710213255.X discloses a kind of used by nuclear reactor residual heat removal system, the waste heat
Discharge system includes the non-security grade Residual heat removal subsystem of primary Ioops, primary Ioops safety level Residual heat removal subsystem and inclusion body
Passive cooling subsystem, it is in parallel between three subsystems, it works according to safety accident grade, normally stops under zero defects
Heap is to carry out waste heat export by the non-security grade Residual heat removal subsystem of primary Ioops, when accident or full factory occur for reactor secondary circuit
When power-off, it is not available non-security grade residual heat removal system, the investment of primary Ioops safety level Residual heat removal subsystem discharge at this time makes
With, when accident is serious, the work of the triggering passive cooling subsystem of inclusion body at this time.
For another example Chinese patent application 201811343185.0 discloses a kind of residual heat removal system, including reactor pressure holds
Device, reactor coolant pump and Residual heat removal cooler, the hot water in reactor pressure vessel flow into reactor coolant pump warp
Flow back to reactor pressure vessel after cooling again, the cold segment pipe of reactor coolant pump is also simultaneously and the stream of Residual heat removal cooler
Enter pipeline connection, the outflow pipeline of Residual heat removal cooler is connected with the hot arc pipeline of reactor pressure vessel.
Summary of the invention
The object of the present invention is to provide a kind of injection of npp safety and residual heat removal systems, can occur in reactor
The safety for guaranteeing nuclear power plant when accident, greatly improves the safety of nuclear power plant, combines waste heat row when reactor start and stop heap
System function out improves the economy of nuclear power plant to greatly save the investment of nuclear power plant.
In order to achieve this, the present invention provides a kind of injection of npp safety and waste heat row in the embodiment on basis
System out, the system include high-pressure safety injection case infusion circuit, safety injection tank infusion circuit, safety injection pump infusion circuit (waste heat row
Circuit out), reactor pressure vessel,
The high-pressure safety injection case infusion circuit includes sequentially connected high-pressure safety injection tank inlet pipeline, high-pressure safety injection case
(carrying out small flow moisturizing when minor break accident for primary Ioops), high-pressure safety injection case outlet line, the high-pressure safety injection box top
It is connected by the high-pressure safety injection tank inlet pipeline with reactor coolant loop cold tube section, the high-pressure safety injection bottom
Portion is connect by the high-pressure safety injection case outlet line with the reactor pressure vessel or and reactor coolant loop
Cold tube section connection;
The safety injection tank infusion circuit includes that the safety injection tank being connected to each other (carries out when big or middle cut accident for primary Ioops
Big flow moisturizing), safety injection tank outlet line, the safety injection tank bottom by the safety injection tank outlet line with it is described anti-
Core pressure vessel is answered to connect or connect with reactor coolant loop cold tube section;
The safety injection pump infusion circuit (residual heat removal loop) includes sequentially connected safety injection pump suction line, safety injection pump
(providing long-term cooling for reactor), safety injection pump outlet line and built-in material-changing water tank and heat exchanger in system (for holding
Reactor core heat is exported when row Safety Injection and Residual heat removal function), described built-in of the described safety injection pump suction line connection
Material-changing water tank and reactor coolant loop hot pipe section, the safety injection pump outlet line are cooling in the connection heat exchanger
It connect with the reactor pressure vessel or is connect with reactor coolant loop hot pipe section and cold tube section afterwards.
In a preferred embodiment, the present invention provides a kind of injection of npp safety and residual heat removal system,
Described in high-pressure safety injection case infusion circuit, safety injection tank infusion circuit, safety injection pump infusion circuit (residual heat removal loop) respectively be one
Column or multiple row.
In a kind of more preferred embodiment, the present invention provides a kind of npp safety injection and Residual heat removal system
System, wherein (Residual heat removal returns for high-pressure safety injection case infusion circuit, safety injection tank infusion circuit described in each column, safety injection pump infusion circuit
Road) by independent power supply power supply, and it is equipped with independent Emergency diesel.
In a preferred embodiment, the present invention provides a kind of injection of npp safety and residual heat removal system,
Described in safety injection tank inside top filled with high pressure nitrogen.
In a preferred embodiment, the present invention provides a kind of injection of npp safety and residual heat removal system,
Described in high-pressure safety injection case outlet line, safety injection tank outlet line, safety injection pump outlet line between any two or between three altogether
With part pipeline.
In a kind of more preferred embodiment, the present invention provides a kind of npp safety injection and Residual heat removal system
System, wherein the high-pressure safety injection case infusion circuit further include:
The the first normally closed motor-driven valve being arranged in parallel on the high-pressure safety injection case outlet line non-common part and
Two motor-driven valves and first check-valve;
The normally opened third motor-driven valve being arranged on the high-pressure safety injection tank inlet pipeline.
In a kind of more preferred embodiment, the present invention provides a kind of npp safety injection and Residual heat removal system
System, wherein the safety injection tank infusion circuit further include:
Normally opened the 4th motor-driven valve and second being arranged in series on the safety injection tank outlet line non-common part stops
Return valve.
In a kind of more preferred embodiment, the present invention provides a kind of npp safety injection and Residual heat removal system
System, wherein the safety injection pump infusion circuit further include:
The 5th normally closed motor-driven valve and the 6th normally opened motor-driven valve being arranged on the safety injection pump suction line;
The 7th normally opened motor-driven valve, the 4th non-return being arranged in series on the safety injection pump outlet line non-common part
Valve and the 5th check-valves.
In a kind of more preferred embodiment, the present invention provides a kind of npp safety injection and Residual heat removal system
System, wherein the system further includes in the high-pressure safety injection case outlet line and the safety injection tank outlet line common portion
Divide the upper third check-valves being arranged.
The beneficial effects of the present invention are npp safety injection of the invention and residual heat removal system are using passive
High-pressure safety injection case, safety injection tank infusion circuit and active safety injection pump infusion circuit, can guarantee nuclear power when accident occurs for reactor
The safety of factory greatly improves the safety of nuclear power plant, combines residual heat removal system function when reactor start and stop heap, thus
The investment for greatling save nuclear power plant improves the economy of nuclear power plant.
Detailed description of the invention
Fig. 1 is the composition figure of illustrative npp safety injection of the invention and residual heat removal system.
Specific embodiment
A specific embodiment of the invention is further illustrated below in conjunction with attached drawing.
The composition of illustrative npp safety injection and residual heat removal system of the invention is as shown in Figure 1, include high pressure
Safety injection tank infusion circuit, safety injection pump infusion circuit (residual heat removal loop), reactor pressure vessel 5, steams safety injection tank infusion circuit
Vapour generator 6, main pump 7.
When nuclear power station is run, the high temperature coolant in reactor pressure vessel 5 enters steam hair by major loop hot pipe section
Raw device 6 is cooled, passes through changeover portion after cooling and returns to reactor pressure vessel 5 via main pump 7.
High-pressure safety injection case infusion circuit includes that sequentially connected high-pressure safety injection tank inlet pipeline 11, high-pressure safety injection case 12 are (small
Carry out small flow moisturizing when cut accident for primary Ioops), high-pressure safety injection case outlet line 13, pass through height at the top of high-pressure safety injection case 12
Pressure safety injection tank suction line 11 is connected with reactor coolant loop cold tube section, and 12 bottom of high-pressure safety injection case passes through high-pressure safety injection
Case outlet line 13 connect with reactor pressure vessel 5 or connect with reactor coolant loop cold tube section.
Safety injection tank infusion circuit includes that the safety injection tank 21 being connected to each other (is flowed greatly when big or middle cut accident for primary Ioops
Measure moisturizing), safety injection tank outlet line 22,21 inside top of safety injection tank passes through safety injection tank filled with high pressure nitrogen, 21 bottom of safety injection tank
Outlet line 22 connect with reactor pressure vessel 5 or connect with reactor coolant loop cold tube section.
Safety injection pump infusion circuit (residual heat removal loop) includes sequentially connected safety injection pump suction line 31, safety injection pump 32
(providing long-term cooling for reactor), safety injection pump outlet line 33 and built-in material-changing water tank 34 and heat exchanger 35 (are used for
System exports reactor core heat when executing Safety Injection and Residual heat removal function), safety injection pump suction line 31 connects built-in reload
Water tank 34 and reactor coolant loop hot pipe section, safety injection pump outlet line 33 after connection heat exchanger 35 is cooling with reactor
Pressure vessel 5 is connected or is connect with reactor coolant loop hot pipe section and cold tube section.
Above-mentioned high-pressure safety injection case infusion circuit, safety injection tank infusion circuit, safety injection pump infusion circuit (residual heat removal loop) are each
For 1-4 column.Each column high-pressure safety injection case infusion circuit, safety injection tank infusion circuit, safety injection pump infusion circuit (residual heat removal loop) are equal
By independent power supply power supply, and it is equipped with independent Emergency diesel.
High-pressure safety injection case outlet line 13,22 common sparing pipeline of safety injection tank outlet line, set on common sparing pipeline
Setting third check-valves 18 (prevents reactor coolant from reversely flowing into high-pressure safety injection case 12, safety injection tank 21 and guaranteeing nuclear power plant just
The leakproofness of reactor coolant loop during often running).
Normally closed the first motor-driven valve 14 and the second electricity are arranged in parallel on 13 non-common part of high-pressure safety injection case outlet line
Dynamic valve 15 (guarantee high-pressure safety injection case 12 is isolated with reactor coolant loop) and first check-valve 16 (prevent reactor
Coolant reversely flows into high-pressure safety injection case 12 and guarantees the sealing of nuclear power plant's reactor coolant loop during normal operation
Property).Normally opened third motor-driven valve 17 is arranged on high-pressure safety injection tank inlet pipeline 11 (makes 12 top of high-pressure safety injection case and reactor
Coolant system connection).
It is arranged in series the 4th normally opened motor-driven valve 23 on 22 non-common part of safety injection tank outlet line and (guarantees that reactor is cold
But can be timely by the liquid piii reactor coolant system in safety injection tank 21 when accident occurs for agent system) and the second non-return
Valve 24 (prevents reactor coolant when normal reactor operation from blowing back into safety injection tank 21 and guaranteeing nuclear power plant during normal operation
The leakproofness of reactor coolant loop).
The 5th normally closed motor-driven valve 36 is set on safety injection pump suction line 31 and (executes normal Residual heat removal function in system
When open the valve, and close the 6th motor-driven valve 37 between safety injection pump 32 and built-in material-changing water tank 34 simultaneously, reactor is cooling
Agent is cooling from reactor and system hot pipe section is extracted out, and the piii reactor pressure vessel 5 or cold after over-heat-exchanger 35 is cooling
Pipeline section) and normally opened 6th motor-driven valve 37 (safety injection pump 32 can directly fetch water from built-in material-changing water tank 34 after guarantee accident, in time
Realize Core cooling).Be arranged in series on safety injection pump outlet line 33 normally opened 7th motor-driven valve 38 (for system equipment every
From maintenance), (concatenated check-valves is for guaranteeing that nuclear power plant reacts during normal operation for the 4th check-valves 39 and the 5th check-valves 30
The leakproofness of reactor coolant system).
The major advantage of above system is: the major loop (portions such as major loop hot arc, changeover portion and cold section are occurring
Position) cut accident conditions when, when major loop pressure is higher can by high-pressure safety injection case realize major loop moisturizing, in pressure
When being reduced to the injection pressure of safety injection tank, filled the water by safety injection tank to major loop, when the injection pressure head of pressure reduction to safety injection pump
When, water when reloading built in containment in water tank is injected by major loop by safety injection pump, to guarantee the safety of reactor;Simultaneously
The heat exchanger exported by safety injection pump exports reactor core heat outside containment, thus the pressure after control accident in containment
And temperature;In reactor normal shutdown, reactor core heat can be exported by safety injection pump and its heat exchanger of outlet, from
And realize normal Residual heat removal function.
Obviously, various changes and modifications can be made to the invention without departing from essence of the invention by those skilled in the art
Mind and range.If in this way, belonging to the model of the claims in the present invention and its equivalent technology to these modifications and changes of the present invention
Within enclosing, then the present invention is also intended to include these modifications and variations.Above embodiment only illustrates to of the invention
Bright, the present invention can also be implemented with other ad hoc fashions or other particular forms, without departing from the gist of the invention or originally
Matter feature.Therefore, the embodiment of description is regarded as illustrative and non-limiting in any way.Model of the invention
Enclosing should be illustrated by appended claims, and any variation equivalent with the intention and range of claim should also be included in the present invention
In the range of.
Claims (9)
1. a kind of npp safety injection and residual heat removal system, it is characterised in that: the system includes high-pressure safety injection case note
Entry loop, safety injection tank infusion circuit, safety injection pump infusion circuit, reactor pressure vessel,
The high-pressure safety injection case infusion circuit includes sequentially connected high-pressure safety injection tank inlet pipeline, high-pressure safety injection case, high pressure
Safety injection tank outlet line, the high-pressure safety injection box top pass through the high-pressure safety injection tank inlet pipeline and reactor coolant
System cold tube section is connected, and the high-pressure safety injection bottom portion is reacted by the high-pressure safety injection case outlet line with described
Core pressure vessel is connected or is connect with reactor coolant loop cold tube section;
The safety injection tank infusion circuit includes the safety injection tank being connected to each other, safety injection tank outlet line, the safety injection tank bottom
Connect by the safety injection tank outlet line with the reactor pressure vessel or with reactor coolant loop cold tube section
Connection;
The safety injection pump infusion circuit includes sequentially connected safety injection pump suction line, safety injection pump, safety injection pump outlet line, with
And built-in material-changing water tank and heat exchanger, the safety injection pump suction line connection built-in material-changing water tank and reactor are cold
But agent system hot pipe section, the safety injection pump outlet line react stacking pressure with described after the connection heat exchanger is cooling
Force container is connected or is connect with reactor coolant loop hot pipe section and cold tube section.
2. system according to claim 1, it is characterised in that: the high-pressure safety injection case infusion circuit, safety injection tank injection
Circuit, safety injection pump infusion circuit are respectively one or more columns per page.
3. system according to claim 2, it is characterised in that: high-pressure safety injection case infusion circuit, safety injection tank described in each column
Infusion circuit, safety injection pump infusion circuit are equipped with independent Emergency diesel by independent power supply power supply.
4. system according to claim 1, it is characterised in that: the safety injection tank inside top is filled with high pressure nitrogen.
5. system according to claim 1, it is characterised in that: the high-pressure safety injection case outlet line, safety injection tank outlet
Pipeline, safety injection pump outlet line common sparing pipeline between any two or between three.
6. system according to claim 5, which is characterized in that the high-pressure safety injection case infusion circuit further include:
The the first normally closed motor-driven valve being arranged in parallel on the high-pressure safety injection case outlet line non-common part and the second electricity
Dynamic valve and first check-valve;
The normally opened third motor-driven valve being arranged on the high-pressure safety injection tank inlet pipeline.
7. system according to claim 5, which is characterized in that the safety injection tank infusion circuit further include:
Normally opened the 4th motor-driven valve and second check-valve being arranged in series on the safety injection tank outlet line non-common part.
8. system according to claim 5, which is characterized in that the safety injection pump infusion circuit further include:
The 5th normally closed motor-driven valve and the 6th normally opened motor-driven valve being arranged on the safety injection pump suction line;
The 7th normally opened motor-driven valve that is arranged in series on the safety injection pump outlet line non-common part, the 4th check-valves and
5th check-valves.
9. system according to claim 5, it is characterised in that: the system further includes going out in the high-pressure safety injection case
The third check-valves being arranged on mouth pipeline and the safety injection tank outlet line common sparing.
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CN201910384350.5A CN110097982B (en) | 2019-05-09 | 2019-05-09 | Safe injection and waste heat discharge system of nuclear power plant |
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CN201910384350.5A CN110097982B (en) | 2019-05-09 | 2019-05-09 | Safe injection and waste heat discharge system of nuclear power plant |
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Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN110752046A (en) * | 2019-10-12 | 2020-02-04 | 中国核电工程有限公司 | Safety device, nuclear power plant system and safe operation method of nuclear power plant |
CN111540483A (en) * | 2020-05-15 | 2020-08-14 | 中国核动力研究设计院 | Method for coping with small-sized crevasse loss of coolant accident in pressurized water reactor nuclear power plant |
CN111540486A (en) * | 2020-04-16 | 2020-08-14 | 中国核动力研究设计院 | Small pressurized water reactor and long-term passive heat discharge system of containment |
CN112582083A (en) * | 2020-12-09 | 2021-03-30 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | Heat conduction system and heat conduction method suitable for nuclear reactor containment system for ship |
CN113808764A (en) * | 2021-08-03 | 2021-12-17 | 中国核电工程有限公司 | Method and system for exporting residual heat of reactor core in containment |
Citations (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN102903404A (en) * | 2012-08-20 | 2013-01-30 | 中国核电工程有限公司 | Active-passive combined reactor core residual heat removal system for nuclear power station |
CN102903403A (en) * | 2012-09-27 | 2013-01-30 | 中国核电工程有限公司 | Active and non-active combined core water injection heat lead-out device |
US20140016734A1 (en) * | 2012-07-13 | 2014-01-16 | Korea Atomic Energy Research Institute | Passive safety system of integral reactor |
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 |
US20170098482A1 (en) * | 2015-10-02 | 2017-04-06 | Tokyo Electric Power Company Holdings, Inc. | Alternative circulation cooling method for emergency core cooling system, and nuclear power plant |
CN107945893A (en) * | 2017-10-09 | 2018-04-20 | 中广核研究院有限公司 | A kind of nuclear power plant's emergence core stacking cool system |
CN207529679U (en) * | 2017-12-11 | 2018-06-22 | 华龙国际核电技术有限公司 | A kind of safety injection system and nuclear power system |
-
2019
- 2019-05-09 CN CN201910384350.5A patent/CN110097982B/en active Active
Patent Citations (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US20140016734A1 (en) * | 2012-07-13 | 2014-01-16 | Korea Atomic Energy Research Institute | Passive safety system of integral reactor |
CN102903404A (en) * | 2012-08-20 | 2013-01-30 | 中国核电工程有限公司 | Active-passive combined reactor core residual heat removal system for nuclear power station |
CN102903403A (en) * | 2012-09-27 | 2013-01-30 | 中国核电工程有限公司 | Active and non-active combined core water injection heat lead-out device |
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 |
US20170098482A1 (en) * | 2015-10-02 | 2017-04-06 | Tokyo Electric Power Company Holdings, Inc. | Alternative circulation cooling method for emergency core cooling system, and nuclear power plant |
CN107945893A (en) * | 2017-10-09 | 2018-04-20 | 中广核研究院有限公司 | A kind of nuclear power plant's emergence core stacking cool system |
CN207529679U (en) * | 2017-12-11 | 2018-06-22 | 华龙国际核电技术有限公司 | A kind of safety injection system and nuclear power system |
Cited By (8)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN110752046A (en) * | 2019-10-12 | 2020-02-04 | 中国核电工程有限公司 | Safety device, nuclear power plant system and safe operation method of nuclear power plant |
CN110752046B (en) * | 2019-10-12 | 2022-01-11 | 中国核电工程有限公司 | Safety device, nuclear power plant system and safe operation method of nuclear power plant |
CN111540486A (en) * | 2020-04-16 | 2020-08-14 | 中国核动力研究设计院 | Small pressurized water reactor and long-term passive heat discharge system of containment |
CN111540483A (en) * | 2020-05-15 | 2020-08-14 | 中国核动力研究设计院 | Method for coping with small-sized crevasse loss of coolant accident in pressurized water reactor nuclear power plant |
CN111540483B (en) * | 2020-05-15 | 2022-02-11 | 中国核动力研究设计院 | Method for coping with small-sized crevasse loss of coolant accident in pressurized water reactor nuclear power plant |
CN112582083A (en) * | 2020-12-09 | 2021-03-30 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | Heat conduction system and heat conduction method suitable for nuclear reactor containment system for ship |
CN113808764A (en) * | 2021-08-03 | 2021-12-17 | 中国核电工程有限公司 | Method and system for exporting residual heat of reactor core in containment |
CN113808764B (en) * | 2021-08-03 | 2023-09-19 | 中国核电工程有限公司 | Method and system for guiding out residual heat of reactor core in containment |
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