CN113782236B - Test device for researching quick start of nuclear reactor - Google Patents
Test device for researching quick start of nuclear reactor Download PDFInfo
- Publication number
- CN113782236B CN113782236B CN202111053607.2A CN202111053607A CN113782236B CN 113782236 B CN113782236 B CN 113782236B CN 202111053607 A CN202111053607 A CN 202111053607A CN 113782236 B CN113782236 B CN 113782236B
- Authority
- CN
- China
- Prior art keywords
- water
- simulation body
- steam generator
- pressure
- pressure vessel
- 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
Links
- 238000012360 testing method Methods 0.000 title claims abstract description 30
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 134
- 238000004088 simulation Methods 0.000 claims abstract description 106
- 239000003381 stabilizer Substances 0.000 claims abstract description 45
- 230000001502 supplementing effect Effects 0.000 claims abstract description 42
- 239000007788 liquid Substances 0.000 claims abstract description 27
- 239000011347 resin Substances 0.000 claims abstract description 19
- 229920005989 resin Polymers 0.000 claims abstract description 19
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 claims abstract description 17
- 239000001301 oxygen Substances 0.000 claims abstract description 17
- 229910052760 oxygen Inorganic materials 0.000 claims abstract description 17
- 210000000476 body water Anatomy 0.000 claims abstract description 4
- 238000002955 isolation Methods 0.000 claims description 4
- 239000013589 supplement Substances 0.000 claims description 3
- 230000000007 visual effect Effects 0.000 claims description 3
- 238000005259 measurement Methods 0.000 claims description 2
- 238000010438 heat treatment Methods 0.000 abstract description 13
- 238000002347 injection Methods 0.000 abstract description 9
- 239000007924 injection Substances 0.000 abstract description 9
- 238000011156 evaluation Methods 0.000 abstract description 3
- 238000005457 optimization Methods 0.000 abstract description 3
- 238000000034 method Methods 0.000 description 15
- 239000007789 gas Substances 0.000 description 6
- 239000000243 solution Substances 0.000 description 4
- 238000000605 extraction Methods 0.000 description 2
- 239000012530 fluid Substances 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- 230000001105 regulatory effect Effects 0.000 description 2
- 238000011160 research Methods 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 1
- 230000001276 controlling effect Effects 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000002474 experimental method Methods 0.000 description 1
- 239000011521 glass Substances 0.000 description 1
- 230000000977 initiatory effect Effects 0.000 description 1
- 230000008646 thermal stress Effects 0.000 description 1
- 238000012795 verification Methods 0.000 description 1
Classifications
-
- 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
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention provides a test device for researching quick start of a nuclear reactor, which comprises a main loop, a water supplementing pipeline and an upper charging bypass. The main loop is sequentially connected with a main pump, a liquid flowmeter, a pressure vessel simulation body, an upper charge pump water inlet, a pressure stabilizer simulation body water outlet connecting pipe and a steam generator simulation body through pipelines. The water supplementing pipeline is sequentially connected with the water supplementing tank, the water supplementing pump, the liquid flowmeter, the resin deaerator and the main loop pipeline through pipelines. The upper charging bypass is sequentially connected with the main loop pipeline, the upper charging pump, the liquid flowmeter and the voltage stabilizer through pipelines. The invention can simulate the quick starting mode of the small-sized nuclear power device under various conditions of different water injection pressures, different water injection temperatures, different oxygen contents of injected water, different vacuum degrees of a loop, different heating powers of a pressure container, different heating powers of a voltage stabilizer, different heating powers of a steam generator and the like, and provides sufficient test data and reliable technical support for performance evaluation, optimization and improvement of the quick starting mode of the nuclear power device.
Description
Technical Field
The invention relates to a test device for researching quick start of a nuclear reactor, and belongs to the field of nuclear engineering.
Background
In the cold starting process of the traditional pressurized water reactor nuclear power plant, the dynamic exhaust process needs to repeatedly click the main pump to remove the dissolved oxygen in the main coolant system, so the starting time is long. The exhaust method has high requirements on the main pump and poor exhaust effect. For small nuclear power units, the use of special start-up means to substantially reduce start-up time is a preferred embodiment due to the small water capacity of the primary circuit. The system loop of the small-sized nuclear power device is simple, and the water content of the system is small, so that a foundation is provided for developing a quick start test research.
Currently, some methods for rapid start-up of nuclear power plants are disclosed in the patent and literature. The means and operations specifically adopted by these methods are not the same, but the principle is basically the same. Some of the methods stay at the theoretical level, and experiments are needed to verify the effectiveness of the method. Some rapid start methods are directly applied to the existing pressurized water reactor nuclear power plant, and because of the high actual reactor start cost, multiple start operations cannot be performed to find out the defects and the places needing to be optimized in the exhaust method.
Therefore, there is a need for a reliable, easy to operate, low cost test apparatus that can be used to study the rapid start of pressurized water reactors, which can simulate the manner in which a small nuclear power plant is started in a variety of rapid starts. The rapid start modes of the pressurized water reactor are comprehensively evaluated by comparing the different rapid start modes.
Disclosure of Invention
The invention aims to provide a test device for researching quick start of a nuclear reactor. The test device can simulate the quick starting mode of the small nuclear power device under various conditions of different water injection pressures, different water injection temperatures, different oxygen contents of injected water, different vacuum degrees of a loop, different heating powers of a pressure container, different heating powers of a voltage stabilizer, different heating powers of a steam generator and the like. Therefore, sufficient test data and reliable technical support are provided for performance evaluation and optimization improvement of a quick starting mode of the nuclear power plant.
The purpose of the invention is realized in the following way: the device comprises a main loop, a water supplementing pipeline and an upper charging bypass, wherein the main loop is sequentially connected with a main pump, a liquid flowmeter, a pressure vessel simulation body, an upper charging pump water inlet, a pressure stabilizer simulation body water outlet connecting pipe and a steam generator simulation body through pipelines; the water supplementing pipeline is sequentially connected with a water supplementing tank, a water supplementing pump, a liquid flowmeter, a resin deaerator and a main loop pipeline through pipelines; the upper charging bypass is sequentially connected with a main loop pipeline, an upper charging pump, a liquid flowmeter and a voltage regulator simulator body through pipelines, and electric heater elements are respectively arranged in the voltage regulator simulator body, the pressure container simulator body and the water supplementing tank; the vacuum pump is connected with the exhaust valve at the top of the pressure vessel simulation body, the exhaust valve at the top of the steam generator simulation body and the exhaust valve at the top of the pressure stabilizer simulation body through pipelines; an isolation loop is arranged around the main pump, a flange-connected visual observation port is arranged on an exhaust pipeline at the top of the pressure vessel simulation body and the steam generator simulation body, oxygen content measurement ports are arranged on the pressure regulator simulation body, the pressure vessel simulation body, the steam generator simulation body and a pipeline at the downstream of the resin deaerator, thermocouples are arranged in the water supplementing tank, the pressure vessel simulation body, the steam generator simulation body and the pressure regulator simulation body, differential pressure sensors are arranged on inlet and outlet pipelines of the pressure vessel simulation body, and liquid flow meters are arranged on the water supplementing loop, the main loop and the upper charging bypass.
The invention also includes such structural features:
1. the upper charging pump sends the water with the main loop in circulation to the voltage stabilizer simulator for mixing through an upper charging bypass; the water in the water supplementing tank is conveyed to the main loop to supplement water for the system after being deoxidized by the resin deoxidizer by the water supplementing pump; the pressure vessel simulator, the steam generator simulator and the pressure stabilizer simulator are located on the same horizontal plane.
2. The vacuum pump is higher than the exhaust valve at the top of the regulator analog body, the observation port at the top of the pressure vessel analog body and the observation port at the top of the steam generator analog body.
3. The top of the pressure vessel simulation body, the top of the steam generator simulation body and the top of the pressure stabilizer simulation body are respectively provided with an exhaust valve, and the vacuum pump is communicated with the pressure vessel simulation body, the steam generator simulation body and the pressure stabilizer simulation body by opening the exhaust valves during air suction so as to vacuumize the pressure vessel simulation body, the steam generator simulation body and the pressure stabilizer simulation body; when water is injected, after the chamber is determined to be full of water through the observation port, the exhaust valve is closed to stop injecting water into the chamber.
4. The inlet and outlet of the pressure vessel analog body and the inlet and outlet of the steam generator analog body are respectively provided with a throttle valve.
5. The bottom of the voltage stabilizer simulator is provided with a drain valve.
Compared with the prior art, the invention has the beneficial effects that: the device can simulate the quick start of the nuclear power plant under various conditions at low cost. The test device has high safety and simple operation, and can complete the verification of the effectiveness of the special starting mode of the pressurized water nuclear reactor by vacuumizing and injecting deoxygenated water in a matching manner so as to realize quick starting, thereby providing sufficient test data and reliable technical support for the performance evaluation and optimization improvement of the special starting mode of the quick starting of the nuclear power device. The device can realize:
(1) Water injection initiation at different vacuum levels of the test loop.
(2) Experimental study of rapid start-up of the system under different makeup water oxygen content conditions.
(3) Experimental study of rapid start-up of the system at different rates of water replenishment.
(4) And (3) experimental study on quick start of the system under the condition of different water injection temperatures.
(5) And (3) experimental research on quick start of the system under the conditions of different heating powers of the pressure vessel simulators, the voltage stabilizer simulators and the steam generator simulators.
(6) The test device designs the bypass loop of the main pump, and isolates the main pump from the main loop when the system is vacuumized, so that damage to the main pump is avoided.
(7) The test device designs the upper charging bypass, and the upper charging pump pumps circulating water in the main loop into the regulator analog body through the upper charging bypass, so that water in the regulator analog body can participate in the circulation of the main loop, and meanwhile, the condition that the temperature difference between fluid in the regulator analog body and fluid in the main loop is too large can be avoided, and the thermal stress is reduced.
(8) The top exhaust pipe of the pressure vessel simulation body and the steam generator simulation body are provided with observation ports for observing whether the simulation body is filled with water or not
(9) The inlet and outlet of the pressure vessel simulation body and the steam generator simulation body are provided with throttle valves, and the throttle valves are matched with a pressure difference meter, so that the flow resistance of the simulation body can be regulated to be matched with the actual reactor device.
Drawings
Fig. 1 is a schematic diagram of the structure of the present invention.
In the figure, 1, a pressure vessel simulation body, 106, a vacuum gauge, 101, 901 observation ports, 103, 104, 903, 904 shutoff valves, 102, 902, 1402 exhaust valves, 107, 907, 1407 safety valves, 1403, 1404, 1405 ball valves, 2, 7, 12, 19 electric heaters, 3, a resin deaerator; 4. resin refueling channel 5, liquid flowmeter 6, make-up water pump 8, make-up water tank 9, steam generator analog 10, main pump 13, liquid level meter 14, voltage stabilizer analog 15, vacuum pump 16, gas flowmeter 11, 17 liquid flowmeter 18, upper charge pump 109, 309, 909, 1409 oxygen content measuring port.
Detailed Description
The invention is described in further detail below with reference to the drawings and the detailed description.
The whole test device consists of a water supplementing tank, a pressure container simulation body, a steam generator simulation body, a voltage stabilizer simulation body, a resin deaerator, a main pump, an upper charging pump, a vacuum pump, a liquid flowmeter, a gas flowmeter and temperature measuring system, a flow measuring system, a pressure measuring system and a data acquisition system.
The invention comprises a main loop, a water supplementing pipeline and an upper charging bypass. The main loop is sequentially connected with a main pump, a liquid flowmeter, a pressure vessel simulation body, an upper charge pump water inlet, a pressure stabilizer simulation body water outlet connecting pipe and a steam generator simulation body through pipelines. The water supplementing pipeline is sequentially connected with the water supplementing tank, the water supplementing pump, the liquid flowmeter, the resin deaerator and the main loop pipeline through pipelines. The upper charging bypass is sequentially connected with the main loop pipeline, the upper charging pump, the liquid flowmeter and the voltage stabilizer simulator through pipelines. The vacuum pump is connected with the exhaust valve at the top of the pressure vessel simulation body, the exhaust valve at the top of the steam generator simulation body and the exhaust valve at the top of the pressure stabilizer simulation body through pipelines. The water in the water supplementing tank is conveyed to the main loop to supplement water after being deoxidized by the resin deoxidizer by the water supplementing pump. The electric heater elements are respectively arranged in the voltage stabilizer simulator, the pressure container simulator and the water supplementing tank, and the water temperature of water supplementing and the water temperature of circulating water in the main loop can be controlled by the three groups of electric heaters. The upper charging pump sends the water in the circulation of the main loop to the voltage regulator analog body for mixing through the upper charging bypass, so that the water in the voltage regulator analog body can participate in the circulation of the main loop, the heating speed of the water in the main loop is improved, and the starting process of the whole device is accelerated. An isolation loop is arranged around the main pump. When the main loop is vacuumized, the main pump is separated from the main loop by controlling the isolating loop valve, so that cavitation of the main pump is prevented. The pressure vessel simulator, the steam generator simulator and the pressure stabilizer simulator are located on the same horizontal plane. The vacuum pump is higher than the exhaust valve at the top of the regulator analog body, the observation port at the top of the pressure vessel analog body and the observation port at the top of the steam generator analog body. The pressure vessel simulation body and the steam generator simulation body are respectively provided with a flange-connected visual observation port on the top exhaust pipeline, and are made of transparent glass, and whether the pressure vessel simulation body and the steam generator simulation body are filled with water or not can be determined in the water injection process through the observation ports.
The top of the pressure vessel simulation body, the steam generator simulation body and the pressure stabilizer simulation body are respectively provided with an exhaust valve. During air suction, the exhaust valve is opened to connect the vacuum pump with the pressure vessel simulation body, the steam generator simulation body and the voltage stabilizer simulation body so as to vacuumize the pressure vessel simulation body, the steam generator simulation body and the voltage stabilizer simulation body; when water is injected, after the chamber is determined to be full of water through the observation port, the exhaust valve is closed to stop injecting water into the chamber.
The inlet and outlet of the pressure vessel simulation body and the inlet and outlet of the steam generator simulation body are respectively provided with a throttle valve for adjusting the flow resistance of the pressure vessel simulation body and the steam generator simulation body. The bottom of the voltage stabilizer simulator is provided with a drain valve. When the water level in the analog body of the pressure stabilizer is too high, the excess water is discharged by opening the blow-down valve. Liquid flow meters are arranged on the water supplementing loop, the main loop and the upper charging bypass and are used for measuring the water flow rate; the gas flowmeter is arranged in the air extraction pipeline and is used for measuring the air extraction rate. The pressure stabilizer simulator, the pressure container simulator, the steam generator simulator and the downstream pipeline of the resin deaerator are respectively provided with an oxygen content measuring port, and the oxygen content of water in the areas in the test process can be measured through the measuring ports. Thermocouples are arranged in the water replenishing tank, the pressure vessel simulation body, the steam generator simulation body and the voltage stabilizer simulation body and are used for measuring the temperature of water in the water replenishing tank, the pressure vessel simulation body, the steam generator simulation body and the voltage stabilizer simulation body. Differential pressure sensors are arranged on the inlet and outlet pipelines of the pressure vessel simulation body and are used for measuring the differential pressure of the section. The temperature, flow and differential pressure data in the test are all input into a computer by an NI data acquisition system, and the test data are acquired, calculated and displayed by specially-programmed software.
The whole structure of the test device mainly comprises a pressure container simulation body 1, observation ports 101 and 901, a vacuum gauge 106, shutoff valves 103, 104, 903 and 904, exhaust valves 102, 902 and 1402, safety valves 107, 907 and 1407, a differential pressure transmitter 105, electric heaters 2, 7 and 12 and a resin deaerator 3 in the figure; the device comprises a resin refueling channel 4, a liquid flowmeter 5, a water supplementing pump 6, a water supplementing tank 8, a steam generator simulation body 9, a main pump 10, a liquid level meter 13, a voltage stabilizer simulation body 14, a vacuum pump 15, a gas flowmeter 16, liquid flowmeters 11 and 17, an upper charging pump 18 and oxygen content measuring ports 109, 309, 909 and 1409.
When being used for starting different vacuum degrees of a loop, the technical scheme 1 is as follows: firstly, the electric heater 7 is started to heat the water 8 in the water tank, the temperature rise condition of the water in the water tank is observed through the acquisition system, and the electric heater 7 is turned off after the water reaches the specified temperature. The exhaust valves 102, 902, 1402 are opened, the vacuum pump 15 is started, the rate of evacuation is monitored by the gas flow meter 16, and the main circuit pressure is gradually reduced at a certain evacuation rate. The change of the vacuum degree of the loop is observed through the pressure gauge 106, when the pressure of the loop is reduced to the designated vacuum degree, the vacuum pump 15 and the air suction valve are stopped, the loop is maintained for a period of time, whether the pressure in the main loop is changed is observed, and whether the loop leaks air is checked. After confirming that the vacuum state of the circuit can be maintained normally, the pipeline valve is opened, the water replenishing system is filled with water by using the water replenishing pump 6, and the water replenishing rate is monitored by the liquid flowmeter 5. The resin deaerator 3 is subjected to material changing through the resin material changing channel 4, and the resin deaerator 3 deoxidizes water in the water supplementing pipeline. Subsequently, the isolating pipeline of the main pump 10 is communicated to carry out water injection and exhaust, the main pump 10 is isolated again, a valve for connecting a water supplementing system and a main loop system is opened, the water injection rate is monitored through the liquid flowmeter 11, and water is injected into the main loop system at a certain speed. In the process, the water level is observed through the observation ports 101 and 901, the exhaust valve is closed after the inside of the analog bodies 1 and 9 is filled with water, then the display liquid level of the liquid level meter 13 on the voltage regulator analog body is observed, the water supplementing pump 6 is closed after the voltage regulator analog body 14 reaches the designated water level, the air exhaust valves 102, 902 and 1402 and the water supplementing pipeline valve are closed, and the main circuit is isolated. The electric heater 12 of the regulator analog body is started to heat the water in the regulator analog body 14, heat the water to the saturation temperature under the corresponding pressure and evaporate the water, so that the pressure in the regulator analog body 14 rises back until the pressure reaches the condition of starting the main pump 10. The main pump isolation loop is communicated with a main loop system, an electric heater 12 in the main pump 10, the upper charge pump 18 and the voltage stabilizer simulator is started, the temperature and the pressure of the main loop are increased, flow circulation is established, the flow in the upper charge bypass is monitored through a liquid flowmeter 17 in the upper charge bypass, the pressure difference between an inlet and an outlet of the pressure container simulator is monitored through a differential pressure meter 105, the flow resistance of the pressure container simulator and the flow resistance of the steam generator simulator are regulated through throttle valves 103, 104, 903 and 904, the data such as loop temperature and pressure are required to be focused in the process, and meanwhile, a small amount of water is led out through oxygen content measuring ports 109, 309, 909 and 1409 to measure the oxygen content. And opening the regulator simulator top exhaust valve 1402 to exhaust, determining that the non-condensable gas is exhausted, and closing the exhaust valve 1402. Finally, the electric heaters 2, 12 and 19 are started as required, so that the system pressure and temperature reach the required values, and the starting is finished. In the above process, if the pressure inside the circuit exceeds the normal operating pressure due to other reasons, the safety valve 107, 907 or 1407 is automatically opened, and the high-temperature steam in the main circuit is discharged to the atmosphere through the pipe connected with the safety valve, so that automatic pressure relief is completed.
When the system is used for quick starting under the condition of different makeup water oxygen contents of the loop, the technical scheme is as follows: by adopting the operation mode in the technical scheme 1, the system is quickly started under the condition of different oxygen contents of the makeup water by adjusting the deoxidizing efficiency of the resin deoxidizer. After the water is replenished in the circuit, the oxygen-removed water is led out through the oxygen content measuring ports 109, 309, 909 and 1409, and the oxygen content in the water is measured by using an oxygen meter.
When being used for quick start of the system under different water supplementing rates, the technical scheme is as follows: by adopting the operation mode in the technical scheme 1, the control of the water supplementing rate is realized by adjusting the opening of the valve on the bypass at the water supplementing pump 6, and the water supplementing rate is monitored by the flowmeter 5.
When being used for quick start of the system under different water replenishing temperatures, the technical scheme is as follows: by adopting the operation mode in the technical scheme 1, the system is quickly started under different water replenishing water temperature conditions by adjusting the heating power and the heating time of the electric heater 7, and the water replenishing water temperature can be monitored by a thermocouple.
When the system is used for quick starting under the conditions of different heating powers of the pressure vessel simulation body, the voltage stabilizer simulation body and the evaporator simulation body, the technical scheme is as follows: by adopting the operation mode in the technical scheme 1, the system is quickly started under the condition of different heating powers of the pressure vessel analog body, the voltage stabilizer analog body and the evaporator analog body by adjusting the heating powers of the electric heaters 2, 19 and 12.
Finally, it should be noted that the foregoing embodiments are merely for illustrating the technical solutions of the present invention, and not for limiting the scope of the present invention, and although the present invention has been described in detail with reference to the foregoing embodiments, it should be understood by those skilled in the art that the technical solutions described in the foregoing embodiments may be modified or some or all of the technical features may be equivalently replaced without departing from the essence of the corresponding technical solutions from the scope of the technical solutions of the embodiments of the present invention.
Claims (10)
1. A test device for studying nuclear reactor rapid start-up, its characterized in that: the device comprises a main loop, a water supplementing pipeline and an upper charging bypass, wherein the main loop is sequentially connected with a main pump, a liquid flowmeter, a pressure vessel simulation body, an upper charging pump water inlet, a pressure stabilizer simulation body water outlet connecting pipe and a steam generator simulation body through pipelines; the water supplementing pipeline is sequentially connected with a water supplementing tank, a water supplementing pump, a liquid flowmeter, a resin deaerator and a main loop pipeline through pipelines; the upper charging bypass is sequentially connected with a main loop pipeline, an upper charging pump, a liquid flowmeter and a voltage regulator simulator body through pipelines, and electric heater elements are respectively arranged in the voltage regulator simulator body, the pressure container simulator body and the water supplementing tank; the vacuum pump is connected with the exhaust valve at the top of the pressure vessel simulation body, the exhaust valve at the top of the steam generator simulation body and the exhaust valve at the top of the pressure stabilizer simulation body through pipelines; an isolation loop is arranged around the main pump, a flange-connected visual observation port is arranged on an exhaust pipeline at the top of the pressure vessel simulation body and the steam generator simulation body, oxygen content measurement ports are arranged on the pressure regulator simulation body, the pressure vessel simulation body, the steam generator simulation body and a pipeline at the downstream of the resin deaerator, thermocouples are arranged in the water supplementing tank, the pressure vessel simulation body, the steam generator simulation body and the pressure regulator simulation body, differential pressure sensors are arranged on inlet and outlet pipelines of the pressure vessel simulation body, and liquid flow meters are arranged on the water supplementing loop, the main loop and the upper charging bypass.
2. A test device for studying the rapid start of a nuclear reactor according to claim 1, wherein: the upper charging pump sends the water with the main loop in circulation to the voltage stabilizer simulator for mixing through an upper charging bypass; the water in the water supplementing tank is conveyed to the main loop to supplement water for the system after being deoxidized by the resin deoxidizer by the water supplementing pump; the pressure vessel simulator, the steam generator simulator and the pressure stabilizer simulator are located on the same horizontal plane.
3. A test device for studying the rapid start of a nuclear reactor according to claim 1 or 2, characterized in that: the vacuum pump is higher than the exhaust valve at the top of the regulator analog body, the observation port at the top of the pressure vessel analog body and the observation port at the top of the steam generator analog body.
4. A test device for studying the rapid start of a nuclear reactor according to claim 1 or 2, characterized in that: the top of the pressure vessel simulation body, the top of the steam generator simulation body and the top of the pressure stabilizer simulation body are respectively provided with an exhaust valve, and the vacuum pump is communicated with the pressure vessel simulation body, the steam generator simulation body and the pressure stabilizer simulation body by opening the exhaust valves during air suction so as to vacuumize the pressure vessel simulation body, the steam generator simulation body and the pressure stabilizer simulation body; when water is injected, after the chamber is determined to be full of water through the observation port, the exhaust valve is closed to stop injecting water into the chamber.
5. A test device for studying the rapid start of a nuclear reactor according to claim 3, wherein: the top of the pressure vessel simulation body, the top of the steam generator simulation body and the top of the pressure stabilizer simulation body are respectively provided with an exhaust valve, and the vacuum pump is communicated with the pressure vessel simulation body, the steam generator simulation body and the pressure stabilizer simulation body by opening the exhaust valves during air suction so as to vacuumize the pressure vessel simulation body, the steam generator simulation body and the pressure stabilizer simulation body; when water is injected, after the chamber is determined to be full of water through the observation port, the exhaust valve is closed to stop injecting water into the chamber.
6. A test device for studying the rapid start of a nuclear reactor according to claim 1 or 2, characterized in that: the inlet and outlet of the pressure vessel analog body and the inlet and outlet of the steam generator analog body are respectively provided with a throttle valve.
7. A test device for studying the rapid start of a nuclear reactor according to claim 5, wherein: the inlet and outlet of the pressure vessel analog body and the inlet and outlet of the steam generator analog body are respectively provided with a throttle valve.
8. A test device for studying the rapid start of a nuclear reactor according to claim 1 or 2, characterized in that: the bottom of the voltage stabilizer simulator is provided with a drain valve.
9. A test device for studying the rapid start of a nuclear reactor according to claim 5, wherein: the bottom of the voltage stabilizer simulator is provided with a drain valve.
10. A test device for studying the rapid start of a nuclear reactor according to claim 7, wherein: the bottom of the voltage stabilizer simulator is provided with a drain valve.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202111053607.2A CN113782236B (en) | 2021-09-09 | 2021-09-09 | Test device for researching quick start of nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202111053607.2A CN113782236B (en) | 2021-09-09 | 2021-09-09 | Test device for researching quick start of nuclear reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN113782236A CN113782236A (en) | 2021-12-10 |
| CN113782236B true CN113782236B (en) | 2024-01-16 |
Family
ID=78841888
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202111053607.2A Active CN113782236B (en) | 2021-09-09 | 2021-09-09 | Test device for researching quick start of nuclear reactor |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN113782236B (en) |
Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103985422A (en) * | 2014-03-20 | 2014-08-13 | 中国核动力研究设计院 | Active and passive nuclear steam supplying system based on 177 reactor core and nuclear power station thereof |
| CN106340329A (en) * | 2016-10-31 | 2017-01-18 | 中国核动力研究设计院 | Reactor thermal-hydraulic simulation testing apparatus and fluid dynamics characteristic simulation method |
| CN107437436A (en) * | 2017-07-28 | 2017-12-05 | 中国核动力研究设计院 | The secondary circuit energy expenditure simulation test device and method of power adjusting can be carried out |
| CN109741842A (en) * | 2019-01-07 | 2019-05-10 | 苏州热工研究院有限公司 | Nuclear power plant holds control case deoxygenation test macro and method |
| CN110033872A (en) * | 2019-04-26 | 2019-07-19 | 华北电力大学 | A kind of universal sodium cold rapid stack component monomer hydraulic experiment rack and its experimental method |
| CN110444302A (en) * | 2019-08-13 | 2019-11-12 | 中国核动力研究设计院 | Reactor core Experiment of Thermophysics device and experimental method under coolant loading amount reduction event |
| CN110783006A (en) * | 2019-11-20 | 2020-02-11 | 中国核动力研究设计院 | Degassing test device and method |
-
2021
- 2021-09-09 CN CN202111053607.2A patent/CN113782236B/en active Active
Patent Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103985422A (en) * | 2014-03-20 | 2014-08-13 | 中国核动力研究设计院 | Active and passive nuclear steam supplying system based on 177 reactor core and nuclear power station thereof |
| CN106340329A (en) * | 2016-10-31 | 2017-01-18 | 中国核动力研究设计院 | Reactor thermal-hydraulic simulation testing apparatus and fluid dynamics characteristic simulation method |
| CN107437436A (en) * | 2017-07-28 | 2017-12-05 | 中国核动力研究设计院 | The secondary circuit energy expenditure simulation test device and method of power adjusting can be carried out |
| CN109741842A (en) * | 2019-01-07 | 2019-05-10 | 苏州热工研究院有限公司 | Nuclear power plant holds control case deoxygenation test macro and method |
| CN110033872A (en) * | 2019-04-26 | 2019-07-19 | 华北电力大学 | A kind of universal sodium cold rapid stack component monomer hydraulic experiment rack and its experimental method |
| CN110444302A (en) * | 2019-08-13 | 2019-11-12 | 中国核动力研究设计院 | Reactor core Experiment of Thermophysics device and experimental method under coolant loading amount reduction event |
| CN110783006A (en) * | 2019-11-20 | 2020-02-11 | 中国核动力研究设计院 | Degassing test device and method |
Non-Patent Citations (4)
| Title |
|---|
| Simulations of coupled heat transport, oxygen diffusion, and thermal expansion;Bogdan Mihaila et al.;Journal of Nuclear Materials(第394期);182–189 * |
| 全厂断电事故下模块化小堆非能动余热排出系统实验研究;张妍;鲁晓东;彭传新;白雪松;昝元锋;卓文彬;闫晓;;核动力工程(第S2期);129-134 * |
| 压水堆核电站LOCA事故最大上充流量的数值研究;周雅宁;胡佳琪;;科技信息(第19期);71-73 * |
| 开式自然循环系统启动特性实验研究;郭雪晴;核技术;第37卷(第4期);(040602-1)--(040602-6) * |
Also Published As
| Publication number | Publication date |
|---|---|
| CN113782236A (en) | 2021-12-10 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN104934082B (en) | A kind of controlled ocean thermal environment analog systemss of temperature and pressure | |
| CN203643083U (en) | Low temperature pressure sensor automatic calibration device | |
| CN102288492B (en) | High-temperature and high-pressure circulating water constant-load extension experimental device with acoustic emission testing function | |
| CN104880502B (en) | Simple stimulation apparatus for corrosion and electrochemistry tests in low speed pipeline | |
| CN109741842B (en) | Nuclear power plant capacity control box deoxygenation testing system and method | |
| KR101445751B1 (en) | Using a cryogenic fluid heat exchanger valve leakage measuring device | |
| CN104047870A (en) | Closed-loop-type liquid heavy metal mechanical pump performance testing device | |
| CN113782236B (en) | Test device for researching quick start of nuclear reactor | |
| CN103489492B (en) | A kind of non-active water level test device and test method | |
| CN205488356U (en) | Through cold and hot device that follows ring testing fuel cell stack structural stability | |
| CN108389635B (en) | A kind of reactor cavity flood pattern three-dimensional simulation experimental provision and experimental method | |
| CN113030151A (en) | Device and method for testing liquefaction rate of low-temperature gas liquefaction device | |
| CN106289834A (en) | A kind of experimental system building the initial operating mode of steam generator secondary side | |
| CN205656103U (en) | A test device that is used for pressure -bearing container seals circle performance to verify | |
| Kopytov et al. | Experimental investigation of non-condensable gases effect on Novovoronezh NPP-2 steam generator condensation power under the condition of passive safety systems operation | |
| CN106323624B (en) | A kind of performance of safety valve experimental rig that can be boosted and test method | |
| CN213955679U (en) | Test device for measuring performance of supercritical carbon dioxide heat exchanger and material | |
| CN114843556A (en) | Hydrogen circulating pump and ejector performance test system | |
| CN104409116B (en) | The O-shaped sealing ring detection method of CAP1400 metals and experiment porch | |
| CN114136863A (en) | Sandstone uranium ore permeability testing device | |
| CN108538413B (en) | It is a kind of for studying the experimental provision and experimental method of condensation water tank hot-working hydraulic characteristic | |
| CN208000150U (en) | A kind of liquid level component thermal response detecting system | |
| CN206804288U (en) | Low-temperature test system | |
| CN204177558U (en) | A kind of big-flow high-pressure fluid test system | |
| CN204667891U (en) | The ocean thermal environment simulation system that a kind of temperature and pressure are controlled |
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 |