CN114999682A - Hydraulic test device and method for passive residual heat removal of polar region environment nuclear power device - Google Patents
Hydraulic test device and method for passive residual heat removal of polar region environment nuclear power device Download PDFInfo
- Publication number
- CN114999682A CN114999682A CN202210663304.0A CN202210663304A CN114999682A CN 114999682 A CN114999682 A CN 114999682A CN 202210663304 A CN202210663304 A CN 202210663304A CN 114999682 A CN114999682 A CN 114999682A
- Authority
- CN
- China
- Prior art keywords
- ice
- heat exchange
- test
- heat
- temperature
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Granted
Links
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/001—Mechanical simulators
-
- 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
Abstract
The test device comprises an ice making circulation loop and a pool type passive residual heat removal system test loop, wherein the ice making circulation loop in the ice making circulation loop is connected with a centrifugal pump through a check valve and an inlet of a test heat exchange water pool, and an outlet pipeline of the heat exchange water pool is connected with the centrifugal pump and then enters the inlet of the ice making circulation loop to form the circulation loop. An outlet pipeline of an electric heating evaporator in the test loop of the pool type passive residual heat removal system is connected with an inlet at the upper part of a tube bundle type heat exchanger, an outlet pipeline of the tube bundle type heat exchanger is connected with an inlet at the shell side of a shell-and-tube cooling system, and an outlet pipeline at the shell side of the shell-and-tube cooling system is connected with an inlet of the electric heating evaporation system to form a loop. The device can simulate the thermodynamic and hydraulic characteristics of the passive residual heat removal system of the nuclear power device in a motion and extreme low-temperature superposition environment, and provides an effective test device for the related research on the thermodynamic and hydraulic characteristics of the passive residual heat removal system in the extreme low-temperature environment.
Description
Technical Field
The invention belongs to the field of testing of the thermodynamic and hydraulic characteristics of a passive residual heat removal system of a polar environment nuclear power device, and particularly relates to a device and a method for testing the thermodynamic and hydraulic characteristics of the passive residual heat removal system of the polar environment nuclear power device.
Background
Along with global climate change, a long summer ice-free period appears in the arctic region sea area, and compared with a conventional power ship, the nuclear power device has the advantages of strong cruising ability, high energy density, small fuel volume and the like, and can execute various sailing tasks in the severe environment of the arctic region. At present, a polar region nuclear power device in China starts late, and is mostly based on an active safety system, when a safety accident occurs, mechanical devices such as a pump and the like are driven by external power input to provide enough cooling water for a reactor, and the melting accident caused by overhigh temperature of a reactor core is prevented. Three major historical nuclear accidents have represented the great limitations of active safety devices. The passive safety design aims to inject the coolant into the reactor core for cooling only by the aid of natural force effects of gravity, natural circulation of the coolant, expansion work of compressed air and the like within a period of time without external energy input, and then the heat of the coolant is led out, so that the reactor core is fully and continuously cooled. The passive residual heat removal system starts to be put into operation after the normal residual heat removal system fails, and natural circulation in a system loop is realized by utilizing the processes of coolant evaporation and condensation to derive the decay residual heat of the reactor core. In the low-temperature environment, solid ice crystals are mixed in seawater, so that a ship seawater system is easily blocked under the condition of poor heat exchange performance, cooling water cannot flow into the ship seawater system, and the heat exchanger cannot be effectively cooled.
Chinese patent application publication No. CN106653109A discloses a test research device for a secondary side passive residual heat removal system, which comprises three water tank simulation bodies, an evaporator simulation body and other devices, and is used for simulating the reliability of the design of the secondary side passive residual heat removal system in the third-generation reactor technology. The simulation object of the invention is a passive safety system of a reactor which is stationary on land, the influence of a marine motion environment on a passive waste heat discharge system cannot be simulated, and meanwhile, the invention adopts liquid water for cooling and is not suitable for a heat transfer flow test for simulating a waste heat discharge heat exchanger ice-water mixture under a low-temperature condition.
Chinese patent application publication No. CN209149828U discloses a multi-loop coupled passive residual heat removal system test apparatus. The passive residual heat removal system inlet condenser pipe is connected with a steam generator secondary side steam outlet, and a simulation test can be carried out on the natural circulation working conditions of the three loops. The device also uses the liquid water in the water tank to carry out a heat exchange test on the waste heat discharge heat exchanger, and the heat exchange simulation test under the low-temperature condition can not be carried out without an ice making loop.
Chinese patent application publication No. CN201589481U discloses a system for preparing fluidized ice from seawater, which mainly comprises a cooling compressor, a condenser, an ice-making heat exchanger, a drying filter, etc., and can continuously prepare a mixture of seawater and ice crystals by using the crystallization technical principle of seawater, but the system loop cannot regulate and control the proportion of ice crystals in seawater, and is not suitable for the research of low-temperature environment heat exchange test by precisely controlling the proportion of ice crystals.
Disclosure of Invention
The invention provides a passive residual heat hydraulic test device and method for a polar environment nuclear power device for the requirements of the thermal hydraulic characteristic test of nuclear power equipment in a superposition state of ocean motion conditions and low temperature conditions, and the device can simulate the motion working condition of ships on the ocean through corresponding motion platform equipment to study the influence of inclined swinging motion on the flowing heat exchange characteristic of a system. The simulation of low-temperature heat exchange conditions is realized by the coupling of an ice making loop and a passive residual heat removal system loop. The ice making loop can adjust the ice crystal proportion in the prepared ice-water mixture, and the requirements of different ice crystal concentrations on the influence of heat exchange characteristics in a test are met.
In order to meet the test purpose, the invention adopts the following technical scheme:
the utility model provides a passive surplus heat removal worker hydraulic test device of polar region environment nuclear power unit, includes ice-making circulation circuit and the passive surplus heat removal system test circuit of pond formula, and wherein ice-making circulation circuit includes ice-making circuit 11 and six degrees of freedom motion heat transfer ponds 12, and ice-making circuit 11 mainly contains ice machine 1, connects ice storage heat preservation container 2 and low temperature water tank 301 of ice machine. The low-temperature water tank 301 is mainly used for preparing seawater to provide sufficient water source for the ice making machine, and simultaneously, the low-temperature seawater can be injected into the ice storage heat preservation container 2 to prepare the ice water mixture with the ice crystal proportion required by the experiment.
The ice making loop 11 is located at the upstream of the ice-water mixture circulation loop, an output pipeline of the ice making loop is connected with the first centrifugal pump 401 through the second check valve 802, the prepared mixture with the fixed proportion is injected into a circulation loop pipeline, and an outlet pipeline at the downstream of the first centrifugal pump 401 is connected with the third control valve 703 and the first flow meter 901 and is used for controlling the flow input of an inlet pipeline of the test heat exchange water tank and detecting the flow at the upstream of the test circulation loop. The inlet of the test heat exchange water tank 5 is provided with a first temperature sensor 1001 for monitoring the temperature parameter of the inlet fluid. The bottom of the test heat exchange water tank 5 is connected with an upper supporting surface of a six-degree-of-freedom motion rack, the six-degree-of-freedom motion rack is fixed through bolts, a lower supporting surface of the six-degree-of-freedom motion rack is fixed on the ground through bolts, and the upper supporting surface and the lower supporting surface are connected through six piston hydraulic rods. The second temperature sensor 1002 is located at the outlet of the bottom of the test heat exchange water tank, monitors the temperature parameter of the fluid at the outlet of the test heat exchange water tank, the outlet pipeline of the test heat exchange water tank is connected with the second flowmeter 902 and the fourth connection control valve 704, and is used for monitoring the downstream flow of the test heat exchange water tank and adjusting the output flow of the test heat exchange water tank, and the differential pressure transmitter 18 is connected between the inlet pipeline and the outlet pipeline of the test heat exchange water tank and is used for measuring the pressure difference change of the fluid passing through the test heat exchange water tank. The outlet pipeline at the downstream of the fourth control valve 704 is connected with the second centrifugal pump 402 to provide enough driving force to realize the flow circulation of the ice-water mixture fluid, and the inlet pipeline of the ice storage thermal insulation container is connected at the downstream of the second centrifugal pump 402 to finally form a circulation loop.
The test loop of the pool type passive residual heat removal system comprises an electric heating evaporation system 13, a tube bundle type heat exchanger 14, a shell-and-tube type heat exchange system 17 and a water supply tank 303. The electric heating evaporation system 13 is mainly used for heating liquid water in the water supply tank 303 to steam required by a test, and controlling corresponding steam parameters according to test requirements, and a downstream pipeline of the electric heating evaporation system 13 is connected with a fifth control valve 705 and a third flow meter 903 and is used for monitoring and controlling steam flow. The downstream pipeline of the third flow meter 903 is connected with the pipe side inlet at the upper end of the pipe bundle heat exchanger 14, meanwhile, the pipe side inlet pipeline is provided with a third temperature sensor 1003, and the temperature parameter of steam entering the pipe side inlet of the pipe bundle heat exchanger is monitored. The tube bundle heat exchanger 14 is immersed in the ice-water mixture fluid in the test heat exchange water tank 5 for heat exchange, the heat exchange characteristic with the low-temperature fluid is studied, an outlet pipeline of the tube bundle heat exchanger is positioned at the lower end of the tube bundle heat exchanger 14, and a certain height difference is formed between the outlet pipeline and an inlet of the tube bundle heat exchanger, so that natural circulation can be formed conveniently. The outlet pipeline at the lower end of the tube bundle heat exchanger 14 is connected with a fourth flow meter 904 and a sixth control valve 706 to control and monitor the flow of the fluid at the outlet of the waste heat discharging heat exchanger, and meanwhile, the outlet pipeline at the lower end is provided with a fourth temperature sensor 1004 to monitor the temperature parameter of the fluid at the outlet of the tube bundle. The downstream of the sixth control valve 706 is connected to the shell-side inlet of the shell-and-tube heat exchange system 17, and the shell-and-tube heat exchange system 17 is used for condensing incompletely condensed steam in the pipeline into liquid water so as to be reheated into steam, and simultaneously, the steam is cooled when the temperature of the fluid in the test loop is too high, so that accidents are prevented. The downstream of the shell side of an electric heating evaporator 15 in a shell-and-tube heat exchange system 17 is connected with an inlet of an electric heating evaporation system 13, and condensed fluid is reintroduced into the electric heating evaporator to be heated to form a circulation loop. In the shell-and-tube heat exchange system 17, the tube side of the electric heating evaporator 15 sequentially passes through the seventh control valve 707, the water pump 16 and the cooling water tank 302 to form a closed loop, so that the shell side fluid circularly flows to lead out the heat of the tube side fluid.
The ice-making circuit 11 is capable of controlling the ice crystal content of the ice-water mixture.
A baffle is used in the heat exchange water tank 5 to divide the flowing space into two parts, and an outlet is positioned at the bottom of the heat exchange water tank 5.
The surfaces of the connecting pipelines in the ice making circulation loop are covered with heat insulation materials, so that the running temperature of the loop can be maintained within the range of-5 ℃ to 0 ℃.
The outside of the tube bundle type heat exchanger 14 is directly contacted with ice-water mixture with the temperature of minus 5 ℃ to 0 ℃, and steam with the temperature of 320 ℃ to 350 ℃ flows in the tube.
The heat exchange water tank 5 in the six-degree-of-freedom motion heat exchange water tank is provided with a transparent observation window for observing the flow pattern change of the ice-water mixture.
The six-freedom-degree motion rack 6 is provided with a plurality of piston support rods which are connected with an upper support surface and a lower support surface, and the heat exchange water tank 5 and the upper support surface are fixed by bolts.
The test method of the polar region environment nuclear power device passive residual heat hydraulic test device comprises the steps of starting an ice-making circulation loop when a polar region low-temperature environment simulation test is carried out, simultaneously starting an electric heating evaporator 15 to generate steam at 320-350 ℃, enabling high-temperature steam to pass through a tube bundle heat exchanger 14, enabling the tube bundle heat exchanger to be externally contacted with an ice-water mixture at-5-0 ℃, simulating a thermodynamic hydraulic characteristic process of a passive residual heat removal system under a polar region low-temperature environment superposition ocean inclination working condition by adjusting the horizontal angle of a supporting surface on a six-degree-of-freedom movement rack 6, and measuring flow, temperature and pressure parameters of each circulation loop through a first flow monitoring instrument, a first temperature monitoring instrument, a second temperature monitoring instrument, a third temperature monitoring instrument and a differential pressure sensor 18 in the process; the ice-water mixture is extracted from the ice storage heat-preservation container 2 for detection to determine the content of ice crystal particles in the test process, the flow pattern change of the ice-water mixture is observed and measured through an observation window of the heat exchange water tank 5, samples are respectively taken at an inlet and an outlet of the heat exchange water tank 5, and the content change of the ice crystal particles before and after the heat exchange process is detected to study the dynamic characteristics of the ice crystal particles in the heat exchange process.
Compared with the prior art, the invention has the following advantages:
1. the test system and the method can simulate the thermal hydraulic characteristics of the passive residual heat removal system of the nuclear power device in the superposition state of the marine motion environment and the low-temperature environment, and carry out sufficient test research on the performance and the reliability of the passive residual heat removal system in the special environment;
2. the ice-making circulation loop can research the influence of the flow pattern characteristics of different ice-water mixtures on the heat exchange characteristics and the dynamic behavior characteristics of ice crystals in the heat exchange and melting process through testing the sampling data in the transparent observation window of the heat exchange water tank and the ice storage heat-insulating container.
3. The simulation of the ship on the ocean working condition is realized through the motion platform, and the six-degree-of-freedom motion platform can simulate the influence of the motions of the ship in the ocean, such as rolling, pitching, rolling, pitching and the like along different coordinate axes of a coordinate system on the passive waste heat removal system in an inclined swinging mode.
Drawings
Fig. 1 is a system diagram of an ice making cycle.
Fig. 2 is a diagram of a passive residual heat removal system.
Detailed Description
The invention is described in detail below with reference to the following figures and examples:
as shown in fig. 1 and fig. 2, the passive residual heat hydraulic test device for the polar region environment nuclear power plant of the present invention comprises a second control valve 702 connected to the upstream of the outlet pipeline of the low temperature water tank 301, and a lower inlet of the ice storage thermal insulation container 2 located at a lower height connected to the downstream of the second control valve 702, wherein the main function of the arrangement is to inject low temperature seawater disposed in the low temperature water tank 301 into the ice storage thermal insulation container 2 by gravity to adjust the ratio of ice crystal particles to water. The outlet of the low-temperature water tank 301 passes through the first control valve 701 through the heat insulation pipeline and then is connected with the inlet pipeline of the ice maker 1 at a lower height, so that seawater required by ice making is provided for the ice maker 1. During the test, the first valve 701 between the low-temperature water tank 301 and the ice maker 1 is preferentially opened to inject the low-temperature seawater into the ice maker 1 to make ice, and after ice crystal particles in the ice maker meet the basic requirements of the test, the output port of the ice maker is opened to enable the mixture fluid to enter the heat-preservation ice storage container 2, and the ice crystal content of the ice-water mixture in the heat-preservation ice storage container is measured. In the process, the second control valve 702 of the outlet pipeline of the low-temperature water tank 301 is opened at the same time, and low-temperature seawater is injected into the ice storage heat-insulation container 2 to further regulate the ice crystal content. The first check valve 801 is arranged on the heat insulation pipeline between the ice maker 1 and the ice storage heat insulation container 2 to prevent the ice-water mixture from flowing backwards.
As shown in fig. 1, a second check valve 802 and a first centrifugal pump 401 are connected to the downstream of the outlet pipeline of the ice storage heat preservation container 2, an outlet of the ice storage heat preservation container 2 is closed in the ice water mixture blending process, after the ice crystal sampling result meets the test requirement, the outlet of the ice storage heat preservation container 2, a third control valve 703 and the first centrifugal pump 401 are opened to introduce the ice water mixture into the ice making circulation loop pipeline, the opening state of the third control valve 703 is kept controlled, the closing state of a fourth control valve 704 is kept, and when the water level of the ice water mixture fluid in the heat exchange water tank 5 reaches the test requirement, the opening degree of the fourth control valve 704 and the power of the second centrifugal pump 402 are adjusted to keep the flow of the inlet and the outlet of the heat exchange water tank 5 balanced, and the internal water level is always in the test requirement range. In the process of keeping the water level stable, the first flowmeter 901 and the second flowmeter 902 record the flow data of the inlet and the outlet of the heat exchange water pool 5, the temperature data of the fluid of the inlet and the outlet of the heat exchange water pool 5 is recorded through the first temperature sensor 1001 and the second temperature sensor 1002, and the pressure drop data of the fluid after passing through the test heat exchange water pool is recorded through the differential pressure transmitter 18.
Fig. 2 shows a test loop of the pool type passive residual heat removal system, and when the test operation is performed, the seventh control valve 707 and the water pump 16 are sequentially opened to circulate the cooling water on the tube side of the shell-and-tube heat exchange system 17. After the ice-making circulation loop can maintain the water level of the heat exchange water tank to be stable, the eighth control valve 708 is opened to enable the water supply tank 303 to inject corresponding water amount according to the steam parameter requirement of the test, then the fifth control valve 705 and the sixth control valve 706 are kept opened, the power of the electric heating evaporator is gradually increased to generate steam, the flow data displayed by the third flow meter 903 and the fourth flow meter 904 are recorded, the independent loop water pump 16 of the shell-and-tube heat exchange system 17 is closed after the steam requirement reaches the test requirement parameter, the steam in the tubes is cooled only by the test heat exchange water tank 5, and natural circulation is established. After the test device is completely started, the ice crystal melting phenomenon is observed through a transparent window of the heat exchange water tank 5, the flow pattern characteristics of the ice-water mixture are judged, and the changes of parameters of the heat exchange water tank 5, the tube bundle type heat exchanger 14, the inlet and outlet flow, the pressure and the temperature are recorded through various monitoring systems. And in the test shutdown stage, a shell-and-tube heat exchange system 17 independent loop water pump 16 is started to carry out additional condensation, and the power of the electric heating evaporation system 13 is gradually reduced. After the electric heating evaporation system 13 is completely closed, the ice maker 1 and the second control valve 702 of the low-temperature water tank are closed, the first control valve 701 and the first centrifugal pump 401 are closed at the same time, the fourth control valve 704 and the second centrifugal pump 402 are kept open until all the ice-water mixture in the loop pipeline is pumped into the ice storage heat-preservation container 2, finally the fourth valve 704 and the second centrifugal pump 402 are closed and controlled, and residual impurities at the bottom of the test heat exchange water tank are cleaned.
Claims (8)
1. A passive residual heat removal hydraulic test device for a polar region environment nuclear power device comprises an ice making circulation loop and a pool type passive residual heat removal system test loop;
the ice making circulation loop comprises an ice making loop (11) and a six-degree-of-freedom motion heat exchange water tank (12), the ice making loop (11) comprises an ice maker (1), an ice storage heat preservation container (2) and a low-temperature water tank (301) which are connected through a heat preservation pipeline, ice crystals in the ice storage heat preservation container (2) are used for storing ice water mixtures input by the ice maker (1), and a first check valve (801) is arranged on the heat preservation pipeline between the ice maker (1) and the ice storage heat preservation container (2) to prevent the ice water mixtures from flowing backwards; the low-temperature water tank (301) provides low-temperature seawater for the ice maker (1) and the ice storage heat preservation container (2) through a heat preservation pipeline, and the flow is controlled by a first control valve (701) and a second control valve (702) on the heat preservation pipeline respectively; ice-water mixture output by the ice storage heat-insulation container (2) enters an output pipeline and passes through a second check valve (802), and then is driven by a first centrifugal pump (401) to enter a main pipeline of an ice-making circulation loop; the six-degree-of-freedom motion heat exchange water tank (12) consists of a six-degree-of-freedom motion rack (6) and a test heat exchange water tank (5) arranged on the six-degree-of-freedom motion rack (6), and a differential pressure sensor (18) is arranged between an inlet and an outlet of the test heat exchange water tank (5); an ice-water mixture output by a first centrifugal pump (401) at the upstream of a six-degree-of-freedom motion heat exchange water tank (12) enters a main pipeline of an ice making circulation loop, then sequentially passes through a third control valve (703), a first flow monitoring instrument (901) and a first temperature monitoring instrument (1001) and then enters an inlet pipeline on the wall surface of a heat exchange water tank (5); fluid output by an outlet pipeline at the bottom of the test heat exchange water tank (5) enters a main pipeline of the ice making circulation loop and then sequentially passes through a second temperature monitoring instrument (1002), a second flow monitoring instrument (902), a fourth control valve (704) and a second centrifugal pump (402) and then enters an ice storage heat preservation container (2) to form a loop;
the test loop of the pool type passive residual heat removal system comprises an electric heating evaporation system (13), a tube bundle type heat exchanger (14), a shell-and-tube heat exchange system (17) and a water supply tank (303); the electric heating evaporation system (13) is mainly used for heating liquid water in the water supply tank (303) into steam required by a test and controlling corresponding steam parameters according to test requirements, and a downstream pipeline of the electric heating evaporation system (13) is connected with a fifth control valve (705) and a third flow meter (903) and is used for monitoring and controlling steam flow; a downstream pipeline of the third flow meter (903) is connected with a pipe side inlet at the upper end of the pipe bundle type heat exchanger (14), meanwhile, a pipe side inlet pipeline is provided with a third temperature sensor (1003), and temperature parameters of steam entering the pipe side inlet of the pipe bundle type heat exchanger are monitored; the tube bundle heat exchanger (14) is immersed in ice-water mixture fluid in the test heat exchange water pool (5) for heat exchange, the heat exchange characteristic with the low-temperature fluid is studied, an outlet pipeline of the tube bundle heat exchanger is positioned at the lower end of the tube bundle heat exchanger (14), and a certain height difference is formed between the outlet pipeline and an inlet of the tube bundle heat exchanger, so that natural circulation can be formed conveniently. The outlet pipeline at the lower end of the tube bundle heat exchanger (14) is connected with a fourth flowmeter (904) and a sixth control valve (706) to control and monitor the flow of fluid at the outlet of the waste heat discharging heat exchanger, and meanwhile, the outlet pipeline at the lower end is provided with a fourth temperature sensor (1004) to monitor the temperature parameter of the fluid at the outlet of the tube bundle; and the downstream of the sixth control valve (706) is connected with a shell-and-tube heat exchange system (17), the shell-and-tube heat exchange system (17) is used for condensing steam which is not completely condensed in the pipeline into liquid water so as to be reheated into steam, and meanwhile, when the temperature of fluid in a test loop is too high, the steam is cooled, so that accidents are prevented. The downstream of the shell side of an electric heating evaporator (15) in a shell-and-tube heat exchange system (17) is connected with an inlet of an electric heating evaporation system (13), and condensed fluid is reintroduced into the electric heating evaporation system to be heated to form a circulation loop; in the shell-and-tube heat exchange system (17), the tube side of the electric heating evaporator (15) sequentially passes through a seventh control valve (707), a water pump (16) and a cooling water tank (302) to form a closed loop, so that the fluid on the shell side circularly flows to lead out the heat of the fluid on the tube side.
2. The polar region environment nuclear power plant passive residual heat power hydraulic test device as claimed in claim 1, wherein the ice making circuit (11) can control the ice crystal content in the ice water mixture.
3. The test device for testing the hydraulic power of the passive residual heat removal power plant of the polar region environment nuclear power plant as claimed in claim 1, characterized in that a baffle is used in the test heat exchange water tank (5) to divide the flow space into two parts, and the outlet is positioned at the bottom of the test heat exchange water tank (5).
4. The device for testing the hydraulic power of the passive residual heat removal power plant of the nuclear power plant in the polar region according to claim 1, wherein the surfaces of the connecting pipelines in the ice-making circulation loop are covered with heat insulation materials, so that the operation temperature of the loop can be maintained within the range of-5 ℃ to 0 ℃.
5. The device for testing the hydraulic power of the passive residual heat removal power plant of the nuclear power plant in the polar environment according to claim 1, wherein the outside of the tube bundle heat exchanger (14) is directly contacted with an ice-water mixture at the temperature of-5 ℃ to 0 ℃, and steam at the temperature of 320 ℃ to 350 ℃ flows in the tube.
6. The polar region environment nuclear power plant passive residual heat hydraulic test device as claimed in claim 1, characterized in that the test heat exchange water tank (5) in the six-degree-of-freedom motion heat exchange water tank has a transparent observation window for observing the flow pattern change of the ice-water mixture.
7. The test device of the passive residual heat removal power hydraulic test of the polar region environment nuclear power plant as claimed in claim 1, characterized in that the six-degree-of-freedom motion rack (6) is provided with a plurality of piston support rods to connect the upper support surface and the lower support surface, and the test heat exchange water tank (5) is fixed with the upper support surface by bolts.
8. The test method of the passive residual heat removal hydraulic test device of the polar region environment nuclear power device according to any one of claims 1 to 7, characterized in that: when a polar low-temperature environment simulation test is carried out, an ice-making circulation loop is started, an electric heating evaporator (15) is started to generate steam at 320-350 ℃, high-temperature steam passes through the tube bundle heat exchanger tube 14, ice-water mixture at-5-0 ℃ is contacted outside the tube, the horizontal angle of a supporting surface on a six-freedom-degree motion rack (6) is adjusted to simulate the thermodynamic characteristic process of a passive waste heat discharge system under the polar low-temperature environment superposition ocean inclination working condition, and in the process, the flow, temperature and pressure parameters of each circulation loop are measured by a first flow monitoring instrument, a second flow monitoring instrument, a third temperature monitoring instrument, a fourth temperature monitoring instrument and a differential pressure sensor (18); the ice-water mixture is extracted from the ice storage heat-preservation container (2) in the test process to be detected to determine the content of ice crystal particles, the flow pattern change of the ice-water mixture is observed and measured through an observation window of the heat exchange water tank (5), samples are respectively taken at an inlet and an outlet of the heat exchange water tank (5), and the content change of the ice crystal particles before and after the heat exchange process is detected to study the dynamic characteristics of the ice crystal particles in the heat exchange process.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202210663304.0A CN114999682B (en) | 2022-06-13 | 2022-06-13 | Passive residual heat hydraulic test device and method for polar environment nuclear power device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202210663304.0A CN114999682B (en) | 2022-06-13 | 2022-06-13 | Passive residual heat hydraulic test device and method for polar environment nuclear power device |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN114999682A true CN114999682A (en) | 2022-09-02 |
| CN114999682B CN114999682B (en) | 2023-06-20 |
Family
ID=83033252
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202210663304.0A Active CN114999682B (en) | 2022-06-13 | 2022-06-13 | Passive residual heat hydraulic test device and method for polar environment nuclear power device |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN114999682B (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN116884655A (en) * | 2023-09-08 | 2023-10-13 | 中国核动力研究设计院 | Method and device for determining influence of external force field on thermal safety, nuclear reactor and equipment |
Citations (17)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH07181279A (en) * | 1993-12-24 | 1995-07-21 | Hitachi Ltd | Floating type nuclear power plant |
| JP2003167089A (en) * | 2001-11-29 | 2003-06-13 | Toshiba Corp | Nuclear energy facility internal cooling system |
| JP2004084964A (en) * | 2002-08-22 | 2004-03-18 | Toyo Eng Works Ltd | Ice heat accumulator |
| CN201589481U (en) * | 2009-09-25 | 2010-09-22 | 天津商业大学 | Fluidizing ice making system by utilizing seawater |
| CN104021823A (en) * | 2014-05-23 | 2014-09-03 | 中国核动力研究设计院 | Waste heat long-term passive lead-out system of floating-type nuclear power station |
| CN106653109A (en) * | 2016-12-30 | 2017-05-10 | 福建福清核电有限公司 | Experimental research device for secondary side passive residual heat removal system (PRS) |
| KR101815958B1 (en) * | 2016-11-25 | 2018-02-21 | 한국과학기술원 | Passive containment cooling system for pressurized water reactor using phase-change material |
| CN108109708A (en) * | 2017-12-08 | 2018-06-01 | 西安交通大学 | Villiaumite cools down ball bed high-temperature heap reactor core fluid interchange experimental system for simulating |
| FR3061709A1 (en) * | 2017-01-08 | 2018-07-13 | Claude Favy | DEVICE FOR THE PRODUCTION OF A MIXTURE OF CRYSTALS OF ICE AND FRESHWATER. |
| CN110021447A (en) * | 2018-01-10 | 2019-07-16 | 中广核（北京）仿真技术有限公司 | A kind of secondary side passive residual heat deriving system |
| CN209149828U (en) * | 2018-11-13 | 2019-07-23 | 中国舰船研究设计中心 | A kind of passive residual heat removal system experimental rig of multiple-loop coupling |
| CN110164569A (en) * | 2019-05-14 | 2019-08-23 | 中国舰船研究设计中心 | A kind of long timeliness secondary circuit passive residual heat removal system of water surface atomic-powered ship |
| CN111446013A (en) * | 2020-04-24 | 2020-07-24 | 上海核工程研究设计院有限公司 | Marine environment secondary side passive waste heat removal system and use method |
| CN112885491A (en) * | 2021-01-11 | 2021-06-01 | 西安交通大学 | Loop cycle characteristic experiment system and method under six-degree-of-freedom motion condition |
| CN112880967A (en) * | 2021-01-11 | 2021-06-01 | 西安交通大学 | Multi-loop natural circulation experimental device and method under six-degree-of-freedom motion condition |
| CN112881386A (en) * | 2021-01-11 | 2021-06-01 | 西安交通大学 | Narrow slit channel visualization experiment device and method under six-degree-of-freedom motion condition |
| RU2758159C1 (en) * | 2020-12-29 | 2021-10-26 | Акционерное Общество "Атомэнергопроект" | Passive heat removal system |
-
2022
- 2022-06-13 CN CN202210663304.0A patent/CN114999682B/en active Active
Patent Citations (17)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH07181279A (en) * | 1993-12-24 | 1995-07-21 | Hitachi Ltd | Floating type nuclear power plant |
| JP2003167089A (en) * | 2001-11-29 | 2003-06-13 | Toshiba Corp | Nuclear energy facility internal cooling system |
| JP2004084964A (en) * | 2002-08-22 | 2004-03-18 | Toyo Eng Works Ltd | Ice heat accumulator |
| CN201589481U (en) * | 2009-09-25 | 2010-09-22 | 天津商业大学 | Fluidizing ice making system by utilizing seawater |
| CN104021823A (en) * | 2014-05-23 | 2014-09-03 | 中国核动力研究设计院 | Waste heat long-term passive lead-out system of floating-type nuclear power station |
| KR101815958B1 (en) * | 2016-11-25 | 2018-02-21 | 한국과학기술원 | Passive containment cooling system for pressurized water reactor using phase-change material |
| CN106653109A (en) * | 2016-12-30 | 2017-05-10 | 福建福清核电有限公司 | Experimental research device for secondary side passive residual heat removal system (PRS) |
| FR3061709A1 (en) * | 2017-01-08 | 2018-07-13 | Claude Favy | DEVICE FOR THE PRODUCTION OF A MIXTURE OF CRYSTALS OF ICE AND FRESHWATER. |
| CN108109708A (en) * | 2017-12-08 | 2018-06-01 | 西安交通大学 | Villiaumite cools down ball bed high-temperature heap reactor core fluid interchange experimental system for simulating |
| CN110021447A (en) * | 2018-01-10 | 2019-07-16 | 中广核（北京）仿真技术有限公司 | A kind of secondary side passive residual heat deriving system |
| CN209149828U (en) * | 2018-11-13 | 2019-07-23 | 中国舰船研究设计中心 | A kind of passive residual heat removal system experimental rig of multiple-loop coupling |
| CN110164569A (en) * | 2019-05-14 | 2019-08-23 | 中国舰船研究设计中心 | A kind of long timeliness secondary circuit passive residual heat removal system of water surface atomic-powered ship |
| CN111446013A (en) * | 2020-04-24 | 2020-07-24 | 上海核工程研究设计院有限公司 | Marine environment secondary side passive waste heat removal system and use method |
| RU2758159C1 (en) * | 2020-12-29 | 2021-10-26 | Акционерное Общество "Атомэнергопроект" | Passive heat removal system |
| CN112885491A (en) * | 2021-01-11 | 2021-06-01 | 西安交通大学 | Loop cycle characteristic experiment system and method under six-degree-of-freedom motion condition |
| CN112880967A (en) * | 2021-01-11 | 2021-06-01 | 西安交通大学 | Multi-loop natural circulation experimental device and method under six-degree-of-freedom motion condition |
| CN112881386A (en) * | 2021-01-11 | 2021-06-01 | 西安交通大学 | Narrow slit channel visualization experiment device and method under six-degree-of-freedom motion condition |
Non-Patent Citations (15)
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN116884655A (en) * | 2023-09-08 | 2023-10-13 | 中国核动力研究设计院 | Method and device for determining influence of external force field on thermal safety, nuclear reactor and equipment |
| CN116884655B (en) * | 2023-09-08 | 2023-11-10 | 中国核动力研究设计院 | Method and device for determining influence of external force field on thermal safety, nuclear reactor and equipment |
Also Published As
| Publication number | Publication date |
|---|---|
| CN114999682B (en) | 2023-06-20 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN109473187B (en) | LAYER FLUID stirs and make muddy process and heat-transfer character experimental system visualizing and method under ocean condition | |
| CN107402231A (en) | One kind is applied under dynamic condition hot-working hydraulic characteristic research experiment device in heating rod beam passage | |
| CN108918175B (en) | Thermal performance test system | |
| CN101576518B (en) | Experimental device for evaporation, absorption and mass transferring of falling film of vertical tube | |
| CN114999682B (en) | Passive residual heat hydraulic test device and method for polar environment nuclear power device | |
| CN113670979A (en) | Experimental system and method for researching flow heat transfer characteristics of lead-bismuth alloy under ocean conditions | |
| CN102360183A (en) | Refrigeration heating system semi-physical simulation experimental method | |
| CN108956072B (en) | Test platform for offshore adaptability of floating natural gas liquefaction system | |
| CN113686497B (en) | Visual experimental device for researching pipeline flowing safe hydrate characteristics and leakage monitoring | |
| CN114441587A (en) | Experimental device for measuring performance of phase-change material in temperature difference energy utilization process | |
| CN208795624U (en) | A kind of hydrate slurry flow behavior test device | |
| CN106370453A (en) | Leakage blockage experiment system for LNG (liquefied natural gas)/NG (natural gas) pipeline leakage | |
| CN208736687U (en) | A kind of thermal performance test system | |
| CN207380574U (en) | Cold thermostat in the spraying of two close cycles independent control | |
| CN114383838B (en) | High-temperature steam test system | |
| CN108489841A (en) | A kind of phase-change material cold cycling endurance testing device and test method | |
| Luo et al. | Experiment Study on the Exhaust-Gas Heat Exchanger for Small and Medium-Sized Marine Diesel Engine | |
| CN100443852C (en) | Liquid-supplementing type low-temperature boiling heat exchanger with stable level indication | |
| CN107860704A (en) | A kind of salt resistance class erosion test device | |
| CN115059952B (en) | Ice source heat pump system and device utilizing phase change density difference for heat exchange | |
| CN218867214U (en) | Medium-and-large-sized heat pump energy storage liquid cooling device suitable for high-and-low temperature environment | |
| CN116106360A (en) | Experimental system for multifunctional supercritical low-temperature nitrogen flow heat transfer research | |
| CN216284342U (en) | Aviation kerosene equipment test system | |
| CN201673045U (en) | Water circulation device of diesel engine test bed | |
| CN216204500U (en) | Siphon oil cooling device |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |