CN109659043B - Ocean nuclear power's suppression test platform - Google Patents
Ocean nuclear power's suppression test platform Download PDFInfo
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- CN109659043B CN109659043B CN201710932986.XA CN201710932986A CN109659043B CN 109659043 B CN109659043 B CN 109659043B CN 201710932986 A CN201710932986 A CN 201710932986A CN 109659043 B CN109659043 B CN 109659043B
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Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/004—Pressure suppression
-
- 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 invention discloses a marine nuclear power pressure inhibition test platform, and relates to the technical field of marine small-sized modularized reactors and special safety facilities for containment. It includes experimental apparatus and rocking platform. The test device comprises a first shell and a second shell, wherein a simulation reactor and a loop simulation device with a steam generator are arranged in the first shell, and the second shell is at least partially filled with liquid. The first shell and the second shell are communicated through at least one communicating pipe, and one end of the communicating pipe, which is positioned in the shell, stretches into the liquid. The test device is fixed on the swing table and can simulate the running state under the ocean condition. When the main coolant or main steam pipeline of the ocean nuclear power platform breaks and loses water, the pressure generated by the accident can be timely restrained, the radioactive substances can be absorbed, the pressure peak value of the first shell can be restrained, and accident parameters can be recorded for reference of people.
Description
Technical Field
The invention relates to the technical field of ocean small-sized modularized reactors and safety facilities specially designed for safety shells, in particular to a marine nuclear power compression test platform.
Background
The ocean nuclear power platform is a small-sized nuclear power station which is a product of organically combining ship engineering and nuclear power engineering, and the main purpose of the ocean nuclear power platform is to supply power for an ocean oil drilling platform and an island.
Ocean nuclear power platform is a China initiative technology, and is still in a development stage, and space limitation and compression limitation exist. The technology is improved, data parameter support is provided for the ocean nuclear power platform, and a great deal of scientific experiments are needed besides a great deal of theoretical work. Because nuclear power is dangerous, the related experimental platform must also play a role in safety protection when an accident occurs in the test.
The existing land test platform firstly cannot simulate the offshore environment, and secondly, most of the facilities are medium-sized and large-sized reactors and a loop simulation device, and in addition, the existing land test platform adopts a technical scheme of combining an active mode and a passive mode, so that the design is complex and the manufacturing cost is high. If the scheme is applied to the offshore nuclear power facilities, when the condition of energy loss occurs, the offshore nuclear power facilities are difficult to quickly obtain other emergency energy sources like the onshore facilities, the dynamic mode of the scheme is easy to lose efficacy, and the whole protection scheme is further invalid. Therefore, it is relatively intuitive, safe and economical to provide a safety protection test platform that can simulate an offshore environment and is passive for an offshore small modular reactor.
In addition, when accidents or simulated accidents occur during related experiments, test parameters are collected for reference by people, so that corresponding countermeasures can be conveniently established.
Disclosure of Invention
Aiming at the defects in the prior art, the invention aims to provide the ocean nuclear power pressure inhibition test platform which can simulate the offshore environment, economically and conveniently carry out the nuclear test and timely control the pressure peak value of the containment when the test has accidents.
In order to achieve the above purpose, the invention adopts the following technical scheme:
the utility model provides a marine nuclear power's suppression test platform which characterized in that, it includes:
the test device comprises a first shell and a second shell, wherein a reactor and a loop simulation device are arranged in the first shell, liquid is at least partially filled in the second shell, the first shell and the second shell are communicated through at least one communicating pipe, and one end of the communicating pipe, which is positioned in the shell, extends into the liquid;
and the test device is fixed on the swinging table.
On the basis of the technical scheme, the liquid comprises water.
On the basis of the technical scheme, the liquid also contains boric acid.
On the basis of the technical scheme, the first shell, the second shell, the reactor and the loop simulation device are respectively provided with a pressure sensor and a thermocouple, and the pressure sensor and the thermocouple are connected with the terminal through the data collection processor.
On the basis of the technical scheme, the reactor and a loop simulation device comprise a steam generator, and the steam generator comprises a rupture disk and a nozzle.
On the basis of the technical scheme, the test device further comprises a high-speed camera, and the shooting area of the high-speed camera is the area where the communicating pipe is located in the opening of the second shell.
On the basis of the technical scheme, the high-speed camera is located outside the second shell, the second shell is a transparent PVC plate, and a transparent window shot by the high-speed camera is arranged on the second shell.
On the basis of the technical scheme, the second shell is arranged inside the first shell.
On the basis of the technical scheme, the second shell is arranged beside the first shell.
Compared with the prior art, the invention has the advantages that:
(1) According to the ocean nuclear power pressure inhibition test platform, the communicating pipe is used for guiding the internal pressure of the containment vessel after a test accident into the second shell, and the peak pressure is passively limited within the design threshold of the containment vessel, so that the safety of the test platform is ensured; it is more economical and safer than the combined active and passive solutions.
(2) According to the ocean nuclear power pressure inhibition test platform, the containment pressure peak control and pressure inhibition system design can be optimized by reasonably setting the capacity, the liquid volume and the number of the second shells.
(3) According to the ocean nuclear power pressure inhibition test platform, the plurality of communicating pipes are used for communicating the first shell and the second shell, so that the response time of pressure inhibition after an accident is reduced, and the break position can be judged by comparing the pressure in different pressure inhibition pipelines.
(4) According to the ocean nuclear power pressure inhibition test platform, the holes are formed in the communication pipeline, so that the gas cooling time can be shortened, and the pressure inhibition test platform can effectively condense steam.
(5) According to the ocean nuclear power pressure inhibition test platform, the nozzles on the steam generator can be rotated to simulate different position cracks, and different flow velocity in different pressure inhibition pipelines can be observed and different experimental phenomena can be compared.
(6) The ocean nuclear power pressure inhibition test platform provided by the invention can simulate ocean conditions by changing the swing angles, the swing periods and the like of the roll and pitch shafts on the swing platform.
Drawings
FIG. 1 is a schematic structural diagram of a marine nuclear power depression test platform of the invention.
In the figure: 1-test device, 10-reactor and a loop simulation device, 11-first casing, 12-second casing, 13-liquid, 14-communicating pipe, 15-steam generator, 16-nozzle, 17-pressure sensor, 18-thermocouple, 2-swing platform, 3-data collection processor, 4-terminal, 5-high-speed camera.
Detailed Description
Embodiments of the present invention are described in further detail below with reference to the accompanying drawings.
Referring to fig. 1, the embodiment of the invention provides a marine nuclear power depression test platform, which comprises a test device 1 and a swing table 2 fixed below the test device.
The test device 1 comprises a first shell 11 provided with a reactor and a loop simulation device 10 inside and a second shell 12 at least partially filled with liquid 13 inside, wherein the first shell 11 and the second shell 12 are communicated through at least one communicating pipe 14, and one end of the communicating pipe 14 positioned in the second shell 12 stretches into the liquid 13 filled in the second shell 12.
The rocking platform 2 preferably comprises a pitch axis and a roll axis, the test device 1 rocking perpendicular to the pitch axis when the pitch axis rolls; when the roll shaft rolls, the test device 1 shakes perpendicular to the roll shaft. Preferably, the magnitude of the impact of the marine environment to the simulation test apparatus 1 and the shaking of the simulation test apparatus 1 in any direction along the horizontal plane are simulated by simultaneously setting different shaking amplitudes of the pitch axis and the roll axis. Further, by setting pitch and roll axis rocking intervals and rocking durations, the test device 1 is simulated to be rocked at different intervals and durations in various directions in the marine environment. The pitch shaft and the roll shaft arranged in this way can effectively provide a marine test environment.
When the reactor and a loop simulation apparatus 10 contained in the first housing 11 in the test are subjected to an accident, such as a water loss accident due to the breakage of the main coolant or the main steam pipe, the temperature in the first housing 11 is rapidly increased, the non-condensable gas in the first housing 1 is rapidly expanded due to the high temperature, and the substances such as water are gasified due to the high temperature and also expanded due to the high temperature, so that the pressure in the first housing 11 is suddenly increased. The pressure in the first casing 11 increases, and a pressure difference is formed between the first casing and the second casing, so that the gas in the first casing 11 leaves the first casing 11 from the end of the communication pipe 14 provided in the first casing 11, enters the communication pipe 14, passes through the communication pipe 14, and enters the second casing 12 from the end of the communication pipe 14 embedded in the liquid 13. The condensable gas such as water passes through the liquid 13 and is absorbed by the heat, so that the condensable gas is converted into a liquid state or a solid state, and the volume is greatly reduced; the non-condensable gas expanded by high temperature passes through the liquid 13, and is absorbed by the liquid 13, the volume of the non-condensable gas is reduced and floats to the middle upper part of the second shell 12, so that the problem of excessive pressure in the first shell 11 is well relieved. It is thereby deduced that the volume of the second housing 12 and the volume of the liquid 13 are reasonably set, and that the pressure can be absorbed more effectively.
The cross-sectional area of the communication pipe 14 connecting the first housing 11 and the second housing 12 ranges from 0.1 to 1 square meter, the number of communication pipes 14 is 1 or more, and preferably, the number of communication pipes 14 is 3 or more. The larger the sectional area of the communication pipe 14, the larger the number of the communication pipes, the more high-temperature and high-pressure gas can pass through the communication pipe in unit time, and the faster the passive depressurization reaction rate is when an accident occurs in the reactor and the first-circuit simulation device 10 in the first casing 11. The communication pipe 14 is preferably provided with a plurality of holes in the liquid in the second casing 12 and the pipe in the first casing 11, so that the reaction rate of passive depressurization can be increased.
The test device 1 is preferably provided with a plurality of second housings 12, the number of which is such as to ensure maximum absorption of the substances suddenly gasified in the first housing 11 and of the gases expanding as a result of the high temperatures. The liquid 13 in the second housing 12 is preferably water because of its higher specific heat capacity, which absorbs more heat and thus converts more material. Further, boric acid is preferably added to the water because boric acid can better neutralize the radiation substances and absorb the emitted harmful rays, so that the invention absorbs the radiation substances and reduces the hazard degree of test accidents while absorbing condensable gas and gas.
The materials used for the first housing 11 and the second housing 12 are preferably combined materials capable of supporting the first housing 11 and the second housing 12 and withstanding the positive pressure and the negative pressure of the first housing 11 and the second housing 12 at the time of an accident. The exterior of the first housing 11 and the second housing 12 is preferably provided with a lead coating for shielding gamma rays and reducing the influence of accidents on the environment.
The first shell 11 and the second shell 12 are preferably provided with a pressure sensor 17 and a thermocouple 18, the pressure sensor 17 and the thermocouple 18 are respectively arranged at different heights and are connected with the terminal 4 through a data collecting processor 3, the data collecting processor 3 processes the data transmitted by the thermocouple 18 and the pressure sensor 17 and transmits the data to the terminal 4, the terminal 4 records the pressure data of each layer, and records parameters such as the internal pressure, the temperature and the like of the shell during normal test under the simulated marine environment, so that test personnel can conveniently check the implemented test data; when an accident happens, the pressure sensor 17 and the thermocouple 18 can record the pressure and temperature changes when the accident happens, so that the tester can conveniently find the accident reason. After the accident, the pressure sensor 17 and the thermocouple 18 maintain monitoring the reactor to prevent the occurrence of a secondary accident: the data sensed by the pressure sensor 17 and the thermocouple 18 are transmitted to the terminal 4 through data collection processing, and an alarm signal is sent out after the terminal 4 finds that the data is abnormal.
The ocean nuclear power pressure inhibition test platform can be used as an experimental reactor and a test platform of a loop simulation device 10, and can also be used as an accident simulation test platform to simulate related data when an accident happens: the reactor and a loop simulation device 10 comprise a steam generator 15, wherein a thermocouple 18, a pressure sensor 17 and a rupture disk are arranged on the steam generator 15, and after the internal pressure of the steam generator 15 exceeds a threshold value, the rupture disk can break the rupture disk on the steam generator 15 to release the pressure. The steam generator 15 is preferably provided with a nozzle 16, which nozzle 16 is capable of adjusting the rate and direction of the steam jet, and by adjusting the steam jet direction and rate of the nozzle 16, the reactor and a circuit break size and the occurrence position are simulated. In addition to the data recording by the pressure sensor 17 and thermocouple 18, the high speed camera 5 is provided on the side of the second housing 12, where the second housing 12 uses a transparent high temperature and high pressure resistant material, preferably a transparent PVC plate: in the event of an accident, the high-speed camera 5 is capable of observing the form of bubbles of the substance entering the liquid 13 in the second housing 12 through the communicating tube 14, and recording the disturbance and influence of the high-temperature substance being pressed into the second housing 12 by the high pressure on the communicating tube 14, the orifice of the communicating tube 14, the region of the second housing 12 near the orifice of the communicating tube 14, and the second housing 12.
The first housing 11 and the second housing 12 may be separate and independent, may be closely attached, or the first housing 11 may include the second housing 12, and the configuration thereof may be set according to the test requirements.
The invention is not limited to the above-mentioned best mode, any person can obtain other various products under the teaching of the invention, but any change in shape or structure is within the scope of protection of the invention, and all the technical schemes are the same or similar to the invention.
Claims (7)
1. The utility model provides a marine nuclear power's suppression test platform which characterized in that, it includes:
the test device (1) comprises a first shell (11) and a second shell (12), wherein a reactor and a loop simulation device (10) are arranged in the first shell (11), liquid (13) is at least partially filled in the second shell (12), the first shell (11) and the second shell (12) are communicated through at least one communicating pipe (14), and one end of the communicating pipe (14) positioned in the shell stretches into the liquid (13);
the test device comprises a swinging table (2), wherein the test device (1) is fixed on the swinging table (2);
the liquid (13) comprises water; the reactor and a circuit simulation device (10) comprise a steam generator (15), the steam generator (15) comprising a rupture disk and a nozzle (16).
2. The ocean nuclear power depression test platform of claim 1, wherein: the liquid (13) further comprises boric acid.
3. The ocean nuclear power depression test platform of claim 1, wherein: pressure sensors (17) and thermocouples (18) are arranged in the first shell (11) and the second shell (12) and on the reactor and a loop simulation device (10), and the pressure sensors (17) and the thermocouples (18) are connected with the terminal (4) through the data collection processor (3).
4. The ocean nuclear power depression test platform of claim 1, wherein: the test device (1) further comprises a high-speed camera (5), and the shooting area of the high-speed camera (5) is the area where the communicating pipe (14) is positioned in the opening of the second shell (12).
5. The ocean nuclear power depression test platform of claim 4, wherein: the high-speed camera (5) is located outside the second shell (12), the second shell (12) is a transparent PVC plate, and a transparent window for shooting by the high-speed camera (5) is arranged on the second shell (12).
6. The ocean nuclear power depression test platform of any one of claims 1-5, wherein: the second housing (11) is disposed inside the first housing (12).
7. The ocean nuclear power depression test platform of any one of claims 1-5, wherein: the second shell (12) is arranged beside the first shell (11).
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| CN201710932986.XA CN109659043B (en) | 2017-10-10 | 2017-10-10 | Ocean nuclear power's suppression test platform |
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| CN201710932986.XA CN109659043B (en) | 2017-10-10 | 2017-10-10 | Ocean nuclear power's suppression test platform |
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| CN109659043A CN109659043A (en) | 2019-04-19 |
| CN109659043B true CN109659043B (en) | 2023-10-03 |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN112071454B (en) * | 2020-09-15 | 2023-01-03 | 哈尔滨工程大学 | Passive combined heat removal system with integrated heat release trap |
| CN112053791B (en) * | 2020-09-15 | 2023-01-03 | 哈尔滨工程大学 | Non-time-limit passive combined heat removal system with integrated heat release trap |
| CN114333545A (en) * | 2021-12-08 | 2022-04-12 | 中国船舶重工集团公司第七一九研究所 | Combined vertical natural circulation steam generator's experimental analog body |
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