CN214671845U - Passive residual heat removal system of reactor - Google Patents

Passive residual heat removal system of reactor Download PDF

Info

Publication number
CN214671845U
CN214671845U CN202120831304.8U CN202120831304U CN214671845U CN 214671845 U CN214671845 U CN 214671845U CN 202120831304 U CN202120831304 U CN 202120831304U CN 214671845 U CN214671845 U CN 214671845U
Authority
CN
China
Prior art keywords
water
reactor
removal system
residual heat
heat removal
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
CN202120831304.8U
Other languages
Chinese (zh)
Inventor
姚尧
余俨
武方杰
张瑞祥
杨姣
侯加麟
张建刚
赖芳芳
胡智威
赵敬锴
王磊
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.)
Xian Thermal Power Research Institute Co Ltd
Original Assignee
Xian Thermal Power Research Institute Co Ltd
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 Xian Thermal Power Research Institute Co Ltd filed Critical Xian Thermal Power Research Institute Co Ltd
Priority to CN202120831304.8U priority Critical patent/CN214671845U/en
Application granted granted Critical
Publication of CN214671845U publication Critical patent/CN214671845U/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 discloses a reactor passive residual heat removal system, which comprises a water cooling pipe, a pressure vessel, an air cooler, a regulating valve and a chimney; the water-cooled tube twines on pressure vessel's outer wall, and the export of water-cooled tube is linked together through the entry of air cooler and governing valve, and the export of governing valve is linked together with the entry of water-cooled tube, and inside the air cooler was located the chimney, and the import department of chimney bottom installs the inlet air valve group, and the heat exchange efficiency of this system is high, and can improve pressure vessel cavity concrete's life.

Description

Passive residual heat removal system of reactor
Technical Field
The utility model belongs to the active waste heat of reactor non-derives field relates to an active waste heat discharge system of reactor non-.
Background
The current third-generation and fourth-generation advanced reactors all require a safety-level passive waste heat removal system for conducting waste heat derivation without depending on active equipment in an emergency state, so that the fault safety of the reactors is improved.
A safety-level passive waste heat discharge system adopted by the pressurized water reactor leads out coolant from a loop heat pipe section, cools and cools the coolant, and returns the coolant to the loop heat pipe section. Because the passive residual heat removal system of the pressurized water reactor is communicated with a primary circuit, the pressure of the primary circuit of the pressurized water reactor generally exceeds 15MPa, the required pressure-bearing grade of a heat transfer pipe is high, the material needs to be made of special materials, and the cost is very high; due to the fact that the equipment range of the pressure boundary of the primary circuit is enlarged, damage of the heat transfer pipe can cause small LOCA of the primary circuit, and uncertainty risks are increased.
The safety-level passive residual heat removal system of the high-temperature gas cooled reactor adopts the idea of radiation heat exchange, namely, the outer surface of a reactor pressure vessel is not provided with a heat insulation layer, a metal heat transfer pipe is arranged outside the reactor pressure vessel, and heat exchange is carried out by radiation and natural convection between the outer surface of the reactor pressure vessel and the metal heat transfer pipe, so that the reactor core residual heat is led out. Although the passive residual heat removal system avoids the high cost of the pressurized water reactor residual heat removal system and the risk of a primary circuit LOCA, the outer surface of a pressure container is about 250 ℃, the efficiency of a radiation and natural convection heat exchange mode is too low, and the residual heat removal capacity of a reactor core is influenced; the radiation heat exchange mode can form a high-temperature environment with the temperature of more than 150 ℃ in the pressure container cavity, and the long-time high-temperature effect can cause the high-temperature aging of the concrete in the pressure container cavity, thereby influencing the service life of the concrete.
SUMMERY OF THE UTILITY MODEL
An object of the utility model is to overcome above-mentioned prior art's shortcoming, provide an active waste heat discharge system of reactor non-, the heat exchange efficiency of this system is high, and can improve the life of pressure vessel cavity concrete.
In order to achieve the purpose, the passive residual heat removal system of the reactor comprises a water-cooled tube, a pressure vessel, an air cooler, a regulating valve and a chimney;
the water-cooled pipe is wound on the outer wall of the pressure container, the outlet of the water-cooled pipe is communicated with the inlet of the regulating valve through an air cooler, the outlet of the regulating valve is communicated with the inlet of the water-cooled pipe, the air cooler is positioned inside the chimney, and the inlet air valve group is installed at the inlet of the bottom of the chimney.
The water cooling pipe is spiral.
The outlet of the water cooling pipe is communicated with the inlet of the air cooler through a flowmeter.
The expansion tank is also included, and the outlet of the expansion tank is communicated with the inlet of the regulating valve.
The expansion water tank is filled with water, and nitrogen is filled between the water surface and the inner wall of the top of the expansion water tank.
The outer wall of the water-cooling pipe is wrapped with a heat-insulating layer.
The air cooler is positioned above the pressure vessel.
The inlet air valve group is formed by connecting a plurality of air valves in parallel.
The utility model discloses following beneficial effect has:
the passive waste heat discharge system of reactor when concrete operation, utilize the water-cooling tube to adopt during heat-conducting mode transmits the cold water in the reactor pressure vessel for heat absorption of cold water in the water-cooling tube becomes hot water, then send into the air cooler and cool down, send into the water-cooling tube again at last in, derive efficiency and ability with the improvement waste heat, avoid the ageing problem of pressure vessel cavity concrete high temperature, improve the life of pressure vessel cavity concrete. Meanwhile, the whole system is not communicated with a loop, so that the pressure bearing grade and the material requirement of the heat transfer pipe can be reduced, the cost is saved, the small LOCA of the loop caused by the damage of the heat transfer pipe is avoided, and the operation risk of the system is reduced.
Drawings
Fig. 1 is a schematic structural diagram of the present invention.
Wherein, 1 is a pressure vessel, 2 is an insulating layer, 3 is a water cooling pipe, 4 is a flow meter, 5 is a chimney, 6 is an air cooler, 7 is an inlet air valve, 8 is an expansion water tank, 8-1 is nitrogen, 8-2 is water, and 9 is an adjusting valve.
Detailed Description
In order to make the technical solution of the present invention better understood, the following figures in the embodiments of the present invention are combined to clearly and completely describe the technical solution in the embodiments of the present invention, and it is obvious that the described embodiments are only some embodiments of the present invention, not all embodiments, and do not limit the scope of the present invention. Moreover, in the following description, descriptions of well-known structures and techniques are omitted so as to not unnecessarily obscure the concepts of the present disclosure. Based on the embodiments in the present invention, all other embodiments obtained by a person skilled in the art without creative efforts shall belong to the protection scope of the present invention.
A schematic structural diagram according to an embodiment of the present disclosure is shown in the drawings. The figures are not drawn to scale, wherein certain details are exaggerated and possibly omitted for clarity of presentation. The shapes of various regions, layers and their relative sizes and positional relationships shown in the drawings are merely exemplary, and deviations may occur in practice due to manufacturing tolerances or technical limitations, and a person skilled in the art may additionally design regions/layers having different shapes, sizes, relative positions, according to actual needs.
Referring to fig. 1, the passive residual heat removal system for a reactor according to the present invention includes a pressure vessel 1, a heat insulating layer 2, a water cooling pipe 3, a flow meter 4, a chimney 5, an air cooler 6, an inlet air valve 7, an expansion water tank 8, and a regulating valve 9;
the water-cooling pipe 3 is a copper pipe, the water-cooling pipe 3 is spirally wound on the outer wall of the pressure container 1, the outlet of the water-cooling pipe 3 is communicated with the inlet of the regulating valve 9 through the flowmeter 4 and the air cooler 6, the outlet of the expansion water tank 8 is communicated with the inlet of the regulating valve 9, and the outlet of the regulating valve 9 is communicated with the inlet of the water-cooling pipe 3; water 8-2 is filled in the expansion water tank 8, and nitrogen 8-1 is filled between the water surface and the inner wall of the top of the expansion water tank 8;
the outer wall of water-cooled tube 3 is wrapped up by heat preservation layer 2, and when the work is carried out, water flow at the outlet of water-cooled tube 3 is detected by flow meter 4, and the flow of water entering water-cooled tube 3 is controlled by regulating valve 9.
The air cooler 6 is positioned in the chimney 5, and the position of the air cooler 6 is higher than that of the pressure container 1. An inlet air valve group 7 is arranged at the inlet of the bottom of the chimney 5, and the inlet air valve group 7 is formed by connecting a plurality of air valves in parallel.
The expansion water tank 8 is arranged at the upstream of the regulating valve 9, nitrogen 8-1 in the expansion water tank 8 is used for maintaining the pressure of the system at 1.5-2MPa, and water 8-2 in the expansion water tank 8 is used for compensating small leakage, expansion caused by heat and contraction caused by cold of the system.
The utility model discloses a concrete working process does:
when the passive residual heat removal system is not used, the inlet air valve 7 and the regulating valve 9 are completely closed, no cooling water flows in the system, water 8-2 in the expansion water tank 8 is used for compensating small leakage and expansion and contraction of the system, and nitrogen 8-1 in the expansion water tank 8 is used for maintaining the pressure of the system at 1.5-2 MPa.
When the passive residual heat removal system is put into use, the inlet air valve 7 and the regulating valve 9 are automatically opened, hot water output by the water-cooled tube 3 enters the air cooler 6, cold air in the chimney 5 is heated by the hot water in the air cooler 6 and then rises to discharge the chimney 5, a suction effect is formed, the cold air is sucked into the chimney 5 from the inlet air valve 7, the hot water in the air cooler 6 releases heat and then becomes cooling water, and then the cooling water enters the water-cooled tube 3 to absorb decay heat conducted by the reactor pressure vessel 1 so as to lead out the residual heat of the reactor core.
The opening degree of the inlet air valve 7 is adjusted, so that the temperature of water entering the water cooling pipe 3 is higher than 80 ℃, the opening degree of the adjusting valve 9 is adjusted to control the waste heat discharge capacity of the reactor core, and the phenomenon that the temperature of a primary loop of the reactor is too fast is avoided.

Claims (8)

1. A reactor passive residual heat removal system is characterized by comprising a water cooling pipe (3), a pressure container (1), an air cooler (6), a regulating valve (9) and a chimney (5);
the water cooling pipe (3) is wound on the outer wall of the pressure container (1), the outlet of the water cooling pipe (3) is communicated with the inlet of the regulating valve (9) through the air cooler (6), the outlet of the regulating valve (9) is communicated with the inlet of the water cooling pipe (3), the air cooler (6) is positioned inside the chimney (5), and the inlet of the bottom of the chimney (5) is provided with the inlet air valve group (7).
2. The reactor passive residual heat removal system according to claim 1, characterized in that the water cooling tubes (3) are helical.
3. The reactor passive residual heat removal system according to claim 1, characterized in that the outlet of the water cooling pipe (3) is communicated with the inlet of the air cooler (6) through a flowmeter (4).
4. The reactor passive residual heat removal system according to claim 1, further comprising an expansion tank (8), wherein an outlet of the expansion tank (8) is communicated with an inlet of the regulating valve (9).
5. The reactor passive residual heat removal system according to claim 4, characterized in that the expansion tank (8) is filled with water, and nitrogen (8-1) is filled between the water surface and the inner wall of the top of the expansion tank (8).
6. The passive residual heat removal system of the reactor according to claim 1, characterized in that the outer wall of the water cooling tube (3) is wrapped with an insulating layer (2).
7. The reactor passive residual heat removal system according to claim 1, wherein the air cooler (6) is located at a higher position than the pressure vessel (1).
8. The reactor passive residual heat removal system according to claim 1, characterized in that the inlet air valve group (7) is formed by connecting a plurality of air valves in parallel.
CN202120831304.8U 2021-04-21 2021-04-21 Passive residual heat removal system of reactor Active CN214671845U (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202120831304.8U CN214671845U (en) 2021-04-21 2021-04-21 Passive residual heat removal system of reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202120831304.8U CN214671845U (en) 2021-04-21 2021-04-21 Passive residual heat removal system of reactor

Publications (1)

Publication Number Publication Date
CN214671845U true CN214671845U (en) 2021-11-09

Family

ID=78465489

Family Applications (1)

Application Number Title Priority Date Filing Date
CN202120831304.8U Active CN214671845U (en) 2021-04-21 2021-04-21 Passive residual heat removal system of reactor

Country Status (1)

Country Link
CN (1) CN214671845U (en)

Similar Documents

Publication Publication Date Title
CN206210405U (en) Nuclear reactor safety system
CN104952497B (en) Passive residual heat removal heat exchanger testing device
CN202615805U (en) Non-dynamic safety case cooling system
CN102637465B (en) Passive safety shell cooling system
CN110739090B (en) Passive heat pipe stack waste heat discharge system utilizing wall surface of pressure container for cooling
CN106328223B (en) A kind of novel passive containment energy management system
CN104103325B (en) Heat derivation system for long-term passive containment
CN102623072A (en) Compound accident residual heat removal system for accelerator-driven sub-critical reactor
CN202887745U (en) Active and passive combined safety shell heat extraction device
CN104269194A (en) Temperature-triggered passive accident residual heat removal system for pool type reactor
CN102637464A (en) Strengthened heat exchange method and device of double-layer concrete containment passive heat derived system
CN204178729U (en) A kind of long-term passive containment thermal conduction system
CN210271804U (en) Emergent waste heat discharge system of water injection formula lead bismuth fast reactor
CN104867526A (en) Passive containment cooling system provided with heat pipe liquid guide devices
CN205376251U (en) Oil -immersed transformer heat sink
CN214671845U (en) Passive residual heat removal system of reactor
CN113053548A (en) High-temperature gas cooled reactor with natural circulation reactor core waste heat derivation function
CN204834063U (en) Active waste heat discharge heat exchanger test device of non -
CN113096837A (en) Passive residual heat removal system of reactor
CN204596432U (en) A kind of Passive containment cooling system with heat pipe drainage set
CN110849205B (en) Water-cooling constant-pressure liquid supplementing water tank system and application method thereof
CN208315211U (en) Passive residual heat removal system for molten salt reactor
CN113593733A (en) Passive steel containment heat exporting system
CN111383782B (en) Passive safety system and pressurized water reactor with same
CN112951456A (en) Reactor cavity water injection system

Legal Events

Date Code Title Description
GR01 Patent grant
GR01 Patent grant