CN107845434B - Reactor core auxiliary cooling system of passive reactor - Google Patents

Reactor core auxiliary cooling system of passive reactor Download PDF

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Publication number
CN107845434B
CN107845434B CN201711023772.7A CN201711023772A CN107845434B CN 107845434 B CN107845434 B CN 107845434B CN 201711023772 A CN201711023772 A CN 201711023772A CN 107845434 B CN107845434 B CN 107845434B
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steam
pipeline
cooling system
water
auxiliary cooling
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CN107845434A (en
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元一单
于明锐
马卫民
朱晨
张丽
刘卓
邹文重
李炜
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China Nuclear Power Engineering Co Ltd
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China Nuclear Power Engineering Co Ltd
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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 the technical field of nuclear safety control, and relates to a reactor core auxiliary cooling system of a passive reactor. The passive reactor core auxiliary cooling system comprises a pressure vessel, an insulating layer, an annular space, a built-in refueling water tank, a water feeding pump, a steam turbine, a water feeding pipeline and a water discharging pipeline, wherein the closed annular space is formed between the outer wall of the pressure vessel and the insulating layer on the periphery of the pressure vessel; the built-in refueling water tank supplies water to the water feeding pump through the water feeding pipeline, and the water feeding pump injects cooling water into the annular space through the water discharging pipeline under the driving of the steam turbine. By utilizing the passive reactor core auxiliary cooling system, the reactor cavity submergence of the reactor can be accelerated by a passive means, and the critical heat flux density of a melt retention device in the reactor is improved, so that the boiling crisis on the wall surface of a pressure vessel is avoided, and the effectiveness of an IVR system is ensured.

Description

Reactor core auxiliary cooling system of passive reactor
Technical Field
The invention belongs to the technical field of nuclear safety control, and relates to a reactor core auxiliary cooling system of a passive reactor.
Background
After a severe nuclear accident of a Sanriema and a Chernobeli nuclear power station, the nuclear power boundary starts to concentrate strength to research and attack the prevention and consequence alleviation of the severe nuclear accident, and a plurality of conclusions clearly define the requirements on the aspects of preventing and alleviating the severe nuclear accident, improving the safety and reliability of the nuclear, improving human factors engineering and the like. In order to avoid the release of large-scale radioactive substances caused by the reactor core of the reactor, the related design of the reactor core catcher is gradually generated, and nuclear power plants such as ACP1000, CAP1400 and ACPR1000 all adopt an in-reactor melt retention device (IVR) under the background that the autonomous design of the third generation nuclear power system in China achieves stage results.
There are many technical solutions for in-Core traps disclosed so far, such as US4442065 (retrofitable Nuclear reactor Core catcher), US5263066(Nuclear reactor equalized with a Core catcher), US 5343506(Nuclear reactor insulation with a Core catcher), US6353651(Core reactor by needle), US7558360(Core cooler), US8358732(Core catcher, reforming method heat of reactor Core), reactor controlled and reactor injected water, CN201310005308.0 (large scale reactor outside cooled reactor Core catcher), CN201310005342.8 (non-active Nuclear power plant reactor) and CN201310005342.8 (non-active Nuclear power plant) which are of the type; CN20140268437.9 (a melt retention system in a reactor after a nuclear power station accident) and the like are correspondingly disclosed, and the technical schemes are that a reactor core catcher is passively cooled by injecting water from a high-level water tank through gravity.
However, in the above-mentioned proposal, the flow rate of the passive cooling water is small, and the critical heat flux density of the wall surface of the reactor melt retention device is low. Therefore, the flow velocity of the cooling water can be increased by other passive water injection means except gravity water injection, so that the critical heat flux density of the wall surface is increased, the boiling crisis is avoided, and the system effectiveness is ensured.
Disclosure of Invention
The invention aims to provide a passive reactor core auxiliary cooling system, which can accelerate reactor cavity flooding through a passive means and improve the critical heat flux density of a melt retention device in a reactor, thereby avoiding boiling crisis on the wall surface of a pressure vessel and ensuring the effectiveness of an IVR system.
To achieve the object, in a basic embodiment, the present invention provides a passive reactor core auxiliary cooling system, which comprises a pressure vessel, an insulating layer, an annular space, a built-in refueling water tank, a water feed pump, a steam turbine, a water feed pipeline, and a water discharge pipeline,
a closed annular space is formed between the outer wall of the pressure container and the insulating layer on the periphery of the pressure container;
the built-in refueling water tank supplies water to the water feeding pump through the water feeding pipeline, and the water feeding pump injects cooling water into the annular space through the water discharging pipeline under the driving of the steam turbine.
In a preferred embodiment, the present invention provides a passive reactor core auxiliary cooling system, wherein the feedwater pump is connected to the steam turbine in a coaxial horizontal manner.
In a preferred embodiment, the present invention provides a passive reactor core secondary cooling system, wherein the secondary cooling system further comprises a pressure relief tank and a vent line, and steam is exhausted into the pressure relief tank through the vent line after performing work in the steam turbine.
In a more preferred embodiment, the present invention provides a passive reactor core auxiliary cooling system, wherein the auxiliary cooling system further comprises a steam generator main steam pipeline, a steam generator branch steam pipeline, and a steam injection pipeline, and steam is supplied to the steam turbine sequentially through the steam generator main steam pipeline, the steam generator branch steam pipeline, and the steam injection pipeline.
In a more preferred embodiment, the present invention provides a passive reactor core auxiliary cooling system, wherein the auxiliary cooling system further comprises an automatic pressure relief system, and an automatic pressure relief system branch line, and when the steam pressure in the steam generator main steam line is lower than 1MPa, the automatic pressure relief system is switched to supply steam to the steam turbine through the automatic pressure relief system branch line and the steam injection line in sequence.
In a more preferred embodiment, the present invention provides a passive reactor core secondary cooling system, wherein the secondary cooling system further comprises a first valve disposed on the steam generator branch steam line, a second valve disposed on the automatic pressure relief system branch line, a third valve disposed on the steam injection line for controlling the rotational speed of the steam turbine, and a fourth valve disposed on the exhaust line.
In a more preferred embodiment, the present invention provides a passive reactor core auxiliary cooling system, wherein the auxiliary cooling system further comprises a fifth valve disposed on the water discharge line and a sixth valve disposed on the water supply line.
In a more preferred embodiment, the invention provides a passive reactor core auxiliary cooling system, wherein the fourth valve, the fifth valve and the sixth valve are all normally open valves (the sixth valve is normally open to make the auxiliary cooling system be filled with water in a standby state, so as to shorten the starting time of the auxiliary cooling system and prevent the water hammer from damaging equipment and pipelines during starting).
In a more preferred embodiment, the present invention provides a passive reactor core auxiliary cooling system, wherein the auxiliary cooling system further comprises a battery for supplying power to all valves, and for activating the steam turbine and powering accessories of the steam turbine.
In a more preferred embodiment, the present invention provides a passive reactor core auxiliary cooling system, wherein the auxiliary cooling system further comprises a valve opening trigger switch arranged on the valve for controlling the opening of all valves, and the valve opening trigger switch can be manually triggered by manual or remote control.
In a more preferred embodiment, the present invention provides a passive reactor core auxiliary cooling system wherein all valves are automatic check valves or are used in conjunction with check valves.
The passive reactor core auxiliary cooling system has the advantages that the passive reactor core auxiliary cooling system is organically combined with a molten material retention system (IVR) in a nuclear power station of the third generation, the reactor cavity submergence is accelerated by a passive means, and the critical heat flux density of a molten material retention device (a pressure vessel lower end socket) in the reactor is improved, so that the boiling crisis on the outer wall surface of the pressure vessel is avoided, the IVR system is ensured to be effective, and the safety of a nuclear power plant is further improved.
Drawings
FIG. 1 is a block diagram of an exemplary passive reactor core auxiliary cooling system of the present invention.
Detailed Description
The following further describes embodiments of the present invention with reference to the accompanying drawings.
An exemplary passive reactor core auxiliary cooling system of the present invention is shown in fig. 1, and includes a pressure vessel 1, an insulating layer 2, an annular space 3, a pressurizer 4, an automatic pressure relief system 5 (connected to the pressure vessel 1 via the pressurizer 4 via a pipeline), a steam generator main steam pipeline 6, a pressure relief tank 7, a built-in refueling water tank 8, a feed water pump 9, a steam turbine 10, a steam generator branch steam pipeline 11, an automatic pressure relief system branch pipeline 12, a steam injection pipeline 13, a vent pipeline 14, a feed water pipeline 15, a vent pipeline 16, a first valve 17, a second valve 18, a third valve 19, a check valve 20, a fifth valve 22, a sixth valve 23, a fourth valve 21, a valve opening trigger switch 24, and a storage battery 25.
A closed annular space 3 is formed between the outer wall of the pressure vessel 1 arranged in the reactor pit and the insulating layer 2 on the periphery of the pressure vessel.
The built-in refueling water tank 8 supplies water to the water supply pump 9 through a water supply pipeline 15 (the built-in refueling water tank 8 is also directly connected with the annular space 3 through a branch pipeline, and a valve is arranged on the branch pipeline), and the water supply pump 9 injects cooling water into the annular space 3 through a water discharge pipeline 16 under the driving of a shaft of a steam turbine 10 which is coaxially and horizontally connected with the water supply pump.
The steam is supplied to the steam turbine 10 through the steam generator main steam line 6, the steam generator branch steam line 11, and the steam injection line 13 in this order. And when the steam pressure in the main steam pipeline 6 of the steam generator is lower than 1MPa, the steam is switched to the pressure stabilizer 4 (used for stabilizing the steam pressure) and the automatic pressure relief system 5 which are connected in sequence, and the steam is supplied to the steam turbine 10 through the branch pipeline 12 of the automatic pressure relief system and the steam injection pipeline 13 in sequence. The steam is discharged into the pressure relief tank 7 through the exhaust line 14 after performing work in the steam turbine 10.
The first valve 17 is arranged on a steam generator branch steam pipeline 11, the second valve 18 is arranged on an automatic pressure relief system branch pipeline 12, the third valve 19 is arranged on a steam injection pipeline 13 (the third valve 19 is initially at an opening position of a complete return seat and is preset to a rated rotating speed of the steam turbine 10, after the feed pump 9 is started, the rotating speed of the steam turbine 10 is adjusted through the third valve 19), the check valve 20 and the fourth valve 21 (normally open valves) are arranged on the exhaust pipeline 14, the fifth valve 22 (normally open valves) is arranged on the drainage pipeline 16, and the sixth valve 23 (normally open valves) is arranged on the feed pipeline 15. All valves are automatic check valves or are used in combination with check valves, and all valves are provided with valve opening trigger switches 24.
The accumulator 25 is used to supply power to all the valves (which can keep the valves in operation for at least 8 hours), and to activate the turbine 10 and power the turbine 10 accessories.
The above exemplary passive reactor core auxiliary cooling system of the present invention operates as follows.
When the nuclear power station has an accident, the pressure and the temperature of a primary loop are rapidly increased, after the set pressure is reached, the first valve 17 is opened, and steam is firstly supplied to the steam turbine 10 through the main steam pipeline 6 of the steam generator; when the steam pressure is lower than 1.0MPa, the second valve 18 is opened, and the automatic pressure relief system 5 is switched to supply steam to the steam turbine 10. Steam generated by reactor decay heat drives the steam turbine 10 and drives the feed pump 9 in operation. The exhaust steam after acting is injected into the pressure relief box 7 through an exhaust pipeline 14, and the exhaust steam is condensed in water in the pressure relief box 7. The water feeding pump 9 takes water from the built-in material replacing water tank 8, and finally injects cooling water into an annular space 3 formed between the outer wall of the pressure vessel 1 and the heat insulation layer 2. When an accident occurs in a nuclear power plant and the pressure vessel 1 is in overpressure, the passive reactor core auxiliary cooling system of the invention is automatically started, and auxiliary cooling can also be manually started by an operator.
It will be apparent to those skilled in the art that various changes and modifications may be made in the present invention without departing from the spirit and scope of the invention. Thus, if such modifications and variations of the present invention fall within the scope of the claims of the present invention and their equivalents, the present invention is intended to include such modifications and variations. The above-described embodiments are merely illustrative of the present invention, and the present invention may be embodied in other specific forms or other specific forms without departing from the spirit or essential characteristics thereof. The described embodiments are, therefore, to be considered in all respects as illustrative and not restrictive. The scope of the invention should be indicated by the appended claims, and any changes that are equivalent to the intent and scope of the claims should be construed to be included therein.

Claims (6)

1. A passive reactor core auxiliary cooling system is characterized in that: the auxiliary cooling system comprises a pressure container, a heat insulation layer, an annular space, a built-in refueling water tank, a water feeding pump, a steam turbine, a water feeding pipeline, a water discharging pipeline, a pressure relief box, an exhaust pipeline, a steam generator main steam pipeline, a steam generator branch steam pipeline, a steam injection pipeline, an automatic pressure relief system and an automatic pressure relief system branch pipeline;
a closed annular space is formed between the outer wall of the pressure container and the insulating layer on the periphery of the pressure container;
the built-in refueling water tank supplies water to the water feeding pump through the water feeding pipeline, and the water feeding pump injects cooling water into the annular space through the water discharging pipeline under the driving of the steam turbine; the steam is discharged into the pressure relief box through the exhaust pipeline after acting in the steam turbine;
the steam generator supplies steam to the steam turbine sequentially through the main steam pipeline of the steam generator, the branch steam pipeline of the steam generator and the steam injection pipeline;
when the steam pressure in the main steam pipeline of the steam generator is lower than 1MPa, switching to the automatic pressure relief system, and supplying steam to the steam turbine through the branch pipeline of the automatic pressure relief system and the steam injection pipeline in sequence;
the auxiliary cooling system also comprises a first valve arranged on a branch steam pipeline of the steam generator, a second valve arranged on a branch pipeline of the automatic pressure relief system, a third valve arranged on the steam injection pipeline and used for controlling the rotating speed of the steam turbine, and a fourth valve arranged on the exhaust pipeline.
2. The auxiliary cooling system according to claim 1, wherein: the water feeding pump is coaxially and horizontally connected with the steam turbine.
3. The auxiliary cooling system according to claim 1, wherein: the auxiliary cooling system also comprises a fifth valve arranged on the water discharge pipeline and a sixth valve arranged on the water supply pipeline,
and the fourth valve, the fifth valve and the sixth valve are all normally open valves.
4. The auxiliary cooling system according to claim 3, wherein: the auxiliary cooling system also comprises a storage battery which is used for providing power for all the valves, starting the steam turbine and supplying power for accessories of the steam turbine.
5. The auxiliary cooling system according to claim 3, wherein: the auxiliary cooling system also comprises a valve opening trigger switch arranged on the valve and used for controlling the opening of all the valves.
6. The auxiliary cooling system according to claim 3, wherein: all valves are automatic check valves or are used in conjunction with check valves.
CN201711023772.7A 2017-10-27 2017-10-27 Reactor core auxiliary cooling system of passive reactor Active CN107845434B (en)

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Publication number Priority date Publication date Assignee Title
CN110890162B (en) * 2018-09-07 2022-06-10 中广核（北京）仿真技术有限公司 Core cooling system and method
CN109273109B (en) * 2018-11-13 2020-01-31 中国核动力研究设计院 type molten material containment vessel retention system
CN109346196B (en) * 2018-11-13 2022-04-15 中国核动力研究设计院 Active and passive cooling combined molten material in-pile retention system

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CN204558037U (en) * 2015-04-17 2015-08-12 国核（北京）科学技术研究院有限公司 For the cooling system of nuclear power plant containment shell
EP2911156A1 (en) * 2014-02-21 2015-08-26 AREVA GmbH Decay heat removal system for a pressurized water reactor and corresponding pressurized water reactor
CN106373622A (en) * 2016-09-30 2017-02-01 中国核动力研究设计院 Active-and-passive-fusion reactor-core waste-heat leading-out system
WO2017080580A1 (en) * 2015-11-09 2017-05-18 Areva Gmbh Depressurization and cooling system for a containment of a nuclear power plant

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US9779840B2 (en) * 2013-10-28 2017-10-03 Bwxt Mpower, Inc. PWR decay heat removal system in which steam from the pressurizer drives a turbine which drives a pump to inject water into the reactor pressure vessel
CN105280249B (en) * 2015-09-16 2018-04-27 中广核工程有限公司 The combining structure of nuclear power plant reactor pressure vessel and barrier shield

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EP2911156A1 (en) * 2014-02-21 2015-08-26 AREVA GmbH Decay heat removal system for a pressurized water reactor and corresponding pressurized water reactor
CN204558037U (en) * 2015-04-17 2015-08-12 国核（北京）科学技术研究院有限公司 For the cooling system of nuclear power plant containment shell
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CN106373622A (en) * 2016-09-30 2017-02-01 中国核动力研究设计院 Active-and-passive-fusion reactor-core waste-heat leading-out system

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