CN212230087U - Pool type reactor waste heat discharge system controlled by floating ball valve - Google Patents

Pool type reactor waste heat discharge system controlled by floating ball valve Download PDF

Info

Publication number
CN212230087U
CN212230087U CN202021937917.1U CN202021937917U CN212230087U CN 212230087 U CN212230087 U CN 212230087U CN 202021937917 U CN202021937917 U CN 202021937917U CN 212230087 U CN212230087 U CN 212230087U
Authority
CN
China
Prior art keywords
cavity
cooling
reactor
container
top end
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.)
Active
Application number
CN202021937917.1U
Other languages
Chinese (zh)
Inventor
孙明
郁杰
戈道川
汪建业
杨子辉
陶龙龙
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Hefei Institutes of Physical Science of CAS
Original Assignee
Hefei Institutes of Physical Science of CAS
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Hefei Institutes of Physical Science of CAS filed Critical Hefei Institutes of Physical Science of CAS
Priority to CN202021937917.1U priority Critical patent/CN212230087U/en
Application granted granted Critical
Publication of CN212230087U publication Critical patent/CN212230087U/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Images

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

The utility model provides a pool type reactor waste heat discharge system controlled by a floating ball valve, which is suitable for a lead bismuth alloy cooling reactor; the reactor safety container is characterized in that a cooling container which is made of stainless steel and has a U-shaped longitudinal section is arranged, an inner cavity is closed and serves as a cooling cavity, liquid water coolant is injected, the closed reactor safety container is adaptively arranged in a cavity formed by the surrounding of the inner side wall of the cooling container, the side wall is attached to the inner side wall of the cooling container, and the top end of the closed reactor safety container is flush with the top end of the cooling container and is welded and sealed at the joint; the cooling cavity is separated by the adiabatic bucket of enclosing and forms outside cavity and inboard cavity, can pass through the delivery pipe by the storage water tank of top and pour into liquid water coolant into to the intracavity through the outside cavity, and inboard cavity top is equipped with the vapor escape pipe, and the pipe end is equipped with the chimney, communicates with each other with outside atmospheric environment, is equipped with the ball-cock assembly on the delivery pipe, and the stainless steel floater floats on inboard cavity liquid level. The utility model discloses structural design is succinct, the reliability is higher, is favorable to improving the security of reactor, reduces the economic cost of reactor.

Description

Pool type reactor waste heat discharge system controlled by floating ball valve
Technical Field
The utility model relates to a reactor safety technical field, the more specifically pond formula reactor waste heat discharge system who utilizes ball valve control that says so.
Background
The reactor waste heat discharge system is a very important safety system of the reactor, when the reactor has accidents such as power failure of the whole plant, earthquake, tsunami and the like, the two-loop heat transfer system has faults, and heat generated in the reactor is discharged out of the reactor through the accident waste heat discharge system. The fukushima nuclear power accident is a typical example, due to the ultra-strong earthquake caused by tsunami, the fukushima nuclear power station has a whole plant power failure accident, the waste heat in the reactor cannot be effectively discharged in time through a normal two-loop heat transfer system, the temperature of the reactor core of the reactor gradually rises, then the fuel cladding-metal zirconium and the coolant water have a chemical reaction at a high temperature, a large amount of hydrogen is generated, and finally hydrogen explosion occurs.
Various reactor waste heat discharge systems exist in domestic and foreign nuclear power plants, and the reactor waste heat discharge systems are active, passive, active and passive combined, use water as a coolant and use air as a coolant. The method is characterized in that a reactor passive residual heat removal system using air as a heat-conducting medium is common; the Chinese experiment fast reactor is additionally provided with a main pump in the reactor for discharging waste heat in the reactor and the like.
At present, some existing reactor waste heat discharge systems in the world are complex in structure, high in manufacturing cost, limited in heat conduction capacity, low in reliability and low in practicability. Different pile types are also suitable for different types of accident waste heat discharge systems.
SUMMERY OF THE UTILITY MODEL
The utility model discloses aim at solving above-mentioned technical problem to a certain extent at least. Therefore, the utility model provides an utilize pond formula reactor waste heat discharge system of ball-cock assembly control is applicable to like the liquid metal refrigerated pond formula reactor of pond formula lead bismuth alloy cooling reactor, and structural design is succinct, the reliability is higher, is favorable to improving the security of reactor, and reduces the economic cost of reactor.
In order to achieve the above purpose, the utility model adopts the following technical scheme:
the utility model provides an utilize pond formula reactor waste heat discharge system of ball valve control which the structural feature is:
the pool type reactor is a lead-bismuth alloy cooling reactor, a reactor core is arranged in the bottom of an inner cavity of a sealed reactor safety container, and the top end part of the inner cavity is filled with inert gas;
the reactor safety container is arranged and made of stainless steel, the longitudinal section of the reactor safety container is U-shaped, the inner cavity of the reactor safety container is closed and serves as a cooling cavity, liquid water coolant is injected into the cooling cavity, the reactor safety container is adaptively arranged in a cavity formed by the surrounding of the inner side wall of the cooling container, the side wall is attached to the inner side wall of the cooling container, the top end of the reactor safety container is flush with the top end of the cooling container, and the joint of the top end of the reactor safety container and the cooling container is welded; the cooling cavity of the cooling container is divided into an outer cavity and an inner cavity by a heat insulation surrounding barrel arranged in the middle, the top end of the heat insulation surrounding barrel is fixedly arranged at the center of the top of the cooling cavity, a space is reserved between the bottom end of the heat insulation surrounding barrel and the bottom of the cooling cavity, so that the outer cavity is communicated with the inner cavity at the bottom, the cooling cavity can inject liquid water coolant into the cavity from a water storage tank communicated to the top end of the outer cavity through a water supply pipe, the water storage tank is positioned above the cooling container, a ball float valve is arranged on the water supply pipe, the ball float valve floats on the liquid level of the inner cavity through a stainless steel ball float, and the liquid water coolant in the cooling cavity; the initial liquid of the liquid water coolant in the cooling cavity is positioned immediately below the inert gas area in the reactor safety container in the height direction; the top end of the inner side cavity is provided with a vertically upward water vapor discharge pipeline, and the pipe end is provided with a chimney which is communicated with the external atmospheric environment and takes the external atmospheric environment as a final heat sink.
Further, the initial liquid level height of the cooling cavity is 4/5 height position of the total height of the cooling cavity.
Compared with the prior art, the utility model discloses beneficial effect embodies:
1. the passive property: the utility model discloses regard liquid water as the coolant, the cooling vessel who has annotated liquid water coolant encloses and locates outside the reactor safety container, when pool type reactor takes place the accident because of earthquake, tsunami, when the heat can not discharge to the heap outside through normal two return circuit heat transfer system, this system spontaneous start can rely on the liquid water coolant heat absorption vaporization in the cooling chamber cavity to discharge to the outside atmospheric environment through the vapor escape pipe, in time take away the waste heat in the pool type reactor, prevent that the reactor from taking place the accident because the heat can not discharge to the heap outside; in the waste heat discharging process, the stainless steel floating ball of the floating ball valve floats up and down along with the change of the liquid water coolant liquid level in the cooling cavity to control the opening and closing of the floating ball valve, so that the water storage tank can automatically supplement the liquid water coolant to the cooling cavity, the whole process does not need manual operation, the problem caused by manual operation errors is eliminated, and the waste heat discharging device is safe and reliable;
2. the heat allowance is large: the reactor safety container is internally arranged in a cavity formed by enclosing the side wall at the inner side of the cooling container filled with liquid water coolant with a certain liquid level, and the liquid water is used as the coolant, so that the reactor safety container has larger heat allowance compared with a waste heat discharge system adopting air cooling, and the reliability and the safety are further ensured;
3. the economic efficiency is as follows: the utility model discloses overall structure designs succinctly to have the passive, do not rely on manual operation, economic cost is low.
Drawings
Fig. 1 is a schematic structural diagram of the present invention.
In the figure, 1 a reactor safety vessel; 2, a reactor core; 3, cooling the container; 4, enclosing the barrel in a heat insulation way; 5 an outer chamber; 6 an inner chamber; 7, a water storage tank; 8 a water supply pipe; 9 a ball float valve; 10 stainless steel floating balls; 11 a connecting rod; 12 a water vapor discharge conduit; and 13, a chimney.
Detailed Description
To make the purpose, technical solution and advantages of the embodiments of the present invention clearer, the embodiments of the present invention are combined to clearly and completely describe the technical solution in the embodiments of the present invention, and obviously, the described embodiments are some embodiments of the present invention, not all embodiments. Based on the embodiments in the present invention, all other embodiments obtained by a person skilled in the art without creative efforts belong to the protection scope of the present invention.
Referring to fig. 1, the pool reactor waste heat removal system controlled by the float ball valve of the present embodiment cools by natural circulation, does not depend on manual operation, and has passive performance, safety and reliability, and the structure is set as follows:
the pool type reactor is a lead-bismuth alloy cooling reactor, a reactor core 2 is arranged in the bottom of an inner cavity of a sealed reactor safety container 1, and the top end part of the inner cavity is filled with inert gas;
the reactor safety container 1 is arranged in a cavity formed by surrounding the inner side wall of the cooling container 3 in a matched manner, the side wall is attached to the inner side wall of the cooling container 3, the top end of the reactor safety container is flush with the top end of the cooling container 3, the joint of the top end is welded and sealed, and the reactor safety container and the cooling container 3 integrally form a closed space; the cooling cavity of the cooling container 3 is separated by a heat insulation surrounding barrel 4 arranged in the middle to form an outer cavity 5 and an inner cavity 6, the top end of the heat insulation surrounding barrel 4 is fixedly arranged at the center of the top of the cooling cavity, a space is reserved between the bottom end and the bottom of the cooling cavity, the outer cavity 5 is communicated with the inner cavity 6 at the bottom, the cooling cavity can inject liquid water coolant into the cavity from a water storage tank 7 communicated to the top end of the outer cavity 5 through a water supply pipe 8, the water storage tank 7 is positioned above the cooling container 3, a ball float valve 9 is arranged on the water supply pipe 8, a stainless steel ball float 10 suspended by the ball float valve 9 through a connecting rod 11 floats on the liquid level of the inner cavity 6, and the liquid water coolant in the; the initial liquid of liquid water coolant in the cooling chamber is located immediately below the inert gas zone in the reactor containment vessel 1 in the height direction; the top end of the inner chamber 6 is provided with a water vapor discharge pipe 12 which is vertically arranged upwards, and the pipe end is provided with a chimney 13 which is communicated with the external atmosphere environment and is used as a final heat sink.
In this embodiment, the initial liquid level height of the cooling chamber is set to 4/5 of the total height of the cooling chamber according to the height occupied by the inert gas area in the reactor safety container 1 of the lead-bismuth alloy cooling reactor. The water storage tank 7 is set as a large-capacity tank body and provides liquid water coolant for the cooling cavity.
When the pool reactor is in a normal operation condition, the system is in a standby state;
when the reactor meets accident conditions such as outage of the whole plant, tornado, steam generator trouble, a return circuit boundary rupture accident, the heat that produces in the return circuit system can not discharge effectively through two return circuit heat transmission system, and this system automatic start opens operating condition, returns safe state or two return circuit heat transmission system when the reactor can normal operating, and this system bring into the stand-by state, specifically as follows:
when the waste heat can not be discharged out of the reactor through the normal two-loop heat transmission system, the temperature in the reactor rises, the heat is transferred to the liquid water coolant in the cavity 6 at the inner side of the cooling container 3 through the reactor safety container 1, the liquid water coolant in the cavity 6 at the inner side absorbs the heat of the reactor safety container 1, the temperature rises gradually, when the steam is vaporized into water vapor at the temperature of over 100 ℃, the water vapor is discharged to a final hot trap through a chimney 13 through a water vapor discharge pipeline 12, namely, in the external atmospheric environment, the waste heat in the pool type reactor is taken away, meanwhile, the liquid level in the inner side cavity 6 is gradually reduced, the stainless steel floating ball 10 is reduced along with the liquid level under the action of gravity, the valve of the floating ball valve 9 is opened, the opening degree is gradually increased along with the reduction degree of the stainless steel floating ball 10 until the stainless steel floating ball is completely opened, and the liquid water coolant in the water storage tank 7 is injected into the cooling cavity from the outer side cavity 5 through the water supply pipe 8 under the action of gravity. After waste heat in the reactor is effectively taken away, the speed of liquid water coolant vaporized into steam becomes slow, the liquid level rises gradually in the cooling chamber, when the stainless steel floater 10 rises to the initial liquid level height along with the liquid level, the ball float valve 9 is completely closed, the water storage tank 7 stops replenishing water to the cooling chamber, the system returns to a standby state, the reactor also returns to a safe state, and therefore the problem that the reactor is more serious because heat cannot be timely derived is avoided.
While embodiments of the present invention have been shown and described, it will be understood by those of ordinary skill in the art that: various changes, modifications, substitutions and alterations can be made to the embodiments without departing from the principles and spirit of the invention, the scope of which is defined by the claims and their equivalents.

Claims (2)

1. The utility model provides an utilize pond formula reactor waste heat discharge system of ball valve control, characterized by:
the pool type reactor is a lead-bismuth alloy cooling reactor, a reactor core (2) is arranged in the bottom of an inner cavity of a sealed reactor safety container (1), and the top end part of the reactor core is filled with inert gas;
the reactor safety container (1) is arranged in a cavity formed by surrounding the inner side wall of the cooling container (3) in a matched manner, the side wall is attached to the inner side wall of the cooling container (3), the top end of the reactor safety container is flush with the top end of the cooling container (3), and the reactor safety container is welded and sealed at the joint of the top ends; the cooling cavity of the cooling container (3) is divided into an outer cavity (5) and an inner cavity (6) by a heat insulation surrounding barrel (4) arranged in the middle, the top end of the heat insulation surrounding barrel (4) is fixedly arranged at the center of the top of the cooling cavity, a space is reserved between the bottom end and the bottom of the cooling cavity, the outer cavity (5) is communicated with the inner cavity (6) at the bottom, the cooling cavity can be filled with liquid water coolant into the cavity by a water storage tank (7) communicated to the top end of the outer cavity (5) through a water supply pipe (8), the water storage tank (7) is positioned above the cooling container (3), a ball float valve (9) is arranged on the water supply pipe (8), the ball float valve (9) floats on the liquid level of the inner cavity (6) through a stainless steel ball float (10), and is in a completely closed state when the liquid water coolant in the cooling cavity is; the initial liquid of the liquid water coolant in the cooling cavity is positioned immediately below the inert gas area in the reactor safety container (1) in the height direction; the top end of the inner side cavity (6) is provided with a vertically upward water vapor discharge pipeline (12), and the pipe end is provided with a chimney (13) which is communicated with the external atmospheric environment and takes the external atmospheric environment as a final heat trap.
2. The residual heat removal system of the pool type reactor controlled by the floating ball valve as claimed in claim 1, wherein: the initial liquid level height of the cooling chamber is 4/5 height of the total height of the cooling chamber.
CN202021937917.1U 2020-09-08 2020-09-08 Pool type reactor waste heat discharge system controlled by floating ball valve Active CN212230087U (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202021937917.1U CN212230087U (en) 2020-09-08 2020-09-08 Pool type reactor waste heat discharge system controlled by floating ball valve

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202021937917.1U CN212230087U (en) 2020-09-08 2020-09-08 Pool type reactor waste heat discharge system controlled by floating ball valve

Publications (1)

Publication Number Publication Date
CN212230087U true CN212230087U (en) 2020-12-25

Family

ID=73911594

Family Applications (1)

Application Number Title Priority Date Filing Date
CN202021937917.1U Active CN212230087U (en) 2020-09-08 2020-09-08 Pool type reactor waste heat discharge system controlled by floating ball valve

Country Status (1)

Country Link
CN (1) CN212230087U (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN111899902A (en) * 2020-09-08 2020-11-06 中国科学院合肥物质科学研究院 Pool type reactor waste heat discharge system controlled by floating ball valve

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN111899902A (en) * 2020-09-08 2020-11-06 中国科学院合肥物质科学研究院 Pool type reactor waste heat discharge system controlled by floating ball valve

Similar Documents

Publication Publication Date Title
CN101836262B (en) Nuclear reactor with improved cooling in an accident situation
CA2846055C (en) Pressurized water reactor with compact passive safety systems
US7983376B2 (en) Boiling water nuclear reactor and emergency core cooling system of the same
US5102616A (en) Full pressure passive emergency core cooling and residual heat removal system for water cooled nuclear reactors
CN103377728B (en) A kind of Flooded-type containment complete passive after-heat removal system
CN109545401B (en) Passive residual heat removal system outside lead-based fast reactor
CN110739090B (en) Passive heat pipe stack waste heat discharge system utilizing wall surface of pressure container for cooling
CN105047236A (en) Passive cooling system for retention of melts in serious accident state of reactor
CN103165199A (en) Emergency core cooling system (eccs) for nuclear reactor employing closed heat transfer pathways
CN104021824B (en) In-pile melts retention system after nuclear power station accident
CN113241200B (en) Fuel salt loop system and operation method
CN106251918B (en) A kind of long timeliness Passive containment cooling system
WO2022135245A1 (en) Passive safety system for reactor
CN212230087U (en) Pool type reactor waste heat discharge system controlled by floating ball valve
WO2024131546A1 (en) Nuclear reactor
CN111899902A (en) Pool type reactor waste heat discharge system controlled by floating ball valve
CN108932984B (en) Double-fluid molten salt fast reactor overflow tank system and control method thereof
CN101916594B (en) Passive nuclear power station LOCA (Loss of Coolant Accident) accident mitigating system
US20220392653A1 (en) External reactor vessel cooling system for floating nuclear power plants
KR102381886B1 (en) Nuclear reactor long-term cooling system
CN214012518U (en) Integrated passive reactor with double-layer shell on top of pressure vessel
CN113661547B (en) Nuclear power plant serious accident handling safety system and control method thereof
KR100238459B1 (en) Passive cooling system for concrete containment vessel of pressurized water reactors
CN113539529B (en) Pool type reactor waste heat discharging system and method
CN117253634A (en) Integrated reactor safety system and method

Legal Events

Date Code Title Description
GR01 Patent grant
GR01 Patent grant