CN108346477B - Test system and test method for performance evaluation of nuclear-grade equipment under severe working conditions - Google Patents
Test system and test method for performance evaluation of nuclear-grade equipment under severe working conditions Download PDFInfo
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- CN108346477B CN108346477B CN201810148811.4A CN201810148811A CN108346477B CN 108346477 B CN108346477 B CN 108346477B CN 201810148811 A CN201810148811 A CN 201810148811A CN 108346477 B CN108346477 B CN 108346477B
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Abstract
The invention discloses a test system and a test method for performance evaluation of nuclear-grade equipment under severe working conditions, and the test system comprises a steam source container, a test container and an overheating container connected between the steam source container and the test container, wherein the input end of the overheating container is communicated with the steam source container, the output end of the overheating container is communicated with the test container, and the on-off of the overheating container and the steam source container and the overheating container and the test container are controlled by a quick-opening valve; heating elements are arranged in the steam source container and the overheating container; and a heating device is arranged on a connecting pipeline of the overheating container and the test container. The invention solves the problem that the test equipment in the prior art is difficult to meet the equipment performance evaluation test requirement of a third-generation nuclear power unit under the severe environment working condition, and achieves the purpose of completely covering the equipment performance evaluation test requirement under the severe environment working condition under the third-generation nuclear power standard.
Description
Technical Field
The invention relates to the field of nuclear safety, in particular to a test system and a test method for performance evaluation of nuclear-grade equipment under severe working conditions.
Background
Aiming at the performance evaluation test of nuclear-grade equipment under severe environmental conditions such as nuclear power plant design standard accidents and the like, the method is to simulate the thermal and chemical environments with severe accident conditions in a nuclear power plant containment vessel in the test according to the construction specifications of a pressurized water reactor nuclear power plant, perform an examination test on equipment and materials with nuclear safety level requirements in the reactor containment vessel, and verify whether the nuclear-grade equipment materials can normally work in the severe environment. The equipment performance evaluation test under the severe environment working condition has an important position in nuclear power equipment development required by nuclear power specifications, and especially after a fukushima nuclear accident, all parties fully realize the important significance of ensuring normal working capacity of safety-level equipment after the nuclear facility accident occurs.
The evaluation test of the equipment performance under the severe environment working condition is mainly based on a test curve specified by a standard. At present, commercial nuclear power plants in China are mainly second-generation and second-generation nuclear power generating units developed on the basis of M310 reactor type in France, so that tests mainly follow the regulations of RCC-E2005 design and construction rules of electrical equipment of nuclear island of pressurized water reactor nuclear power station in France. However, with the rapid development of the domestic third-generation nuclear power technology, the construction of the third-generation unit and the process of the localization of the equipment, the test requirements of the nuclear-grade equipment of the third-generation unit are greatly increased. The highest temperature rise value required by a test curve specified by RCC-E2005 is 156 ℃, 0.56MPa, the test medium is saturated steam, the thermal shock time is 30s, and the temperature rise rate is about 3.5 ℃/s. Taking a third-generation nuclear power AP1000 stack type as an example, the temperature peak value of a test curve of AP1000 requires that the temperature rises from 50 ℃ to about 90 ℃ in 1 second at the beginning of the test and reaches about 140 ℃; the temperature reaches 215 ℃ within 20 seconds, and the pressure is 0.55 MPa. Therefore, compared with a second-generation unit, the test curve of the third-generation unit provides higher technical requirements for the test device, particularly, in the early-stage temperature rise process of the test, the test medium is in an overheated state, the temperature rise rate reaches about 90 ℃/s, the test media are different, and the temperature rise rate and the temperature rise amplitude are far higher than those of the second-generation nuclear power. In general, the equipment performance evaluation test under the severe environment working condition of the third-generation nuclear power puts higher requirements on the medium, the heating capacity, the temperature uniformity and the like of the test device. However, the existing test equipment of each nuclear power station is difficult to meet the equipment performance evaluation test requirements of a third-generation nuclear power unit under severe environment working conditions.
Disclosure of Invention
The invention aims to provide a test system and a test method for performance evaluation of nuclear-grade equipment under severe working conditions, so as to solve the problem that test equipment in the prior art cannot meet the requirement of a third-generation nuclear power unit on the performance evaluation test of the equipment under the severe environment working conditions, and achieve the purpose of completely covering the requirement of the equipment performance evaluation test under the severe environment working conditions under the third-generation nuclear power standard.
The invention is realized by the following technical scheme:
the test system for performance evaluation of the nuclear-grade equipment under the severe working condition comprises a steam source container, a test container and an overheating container connected between the steam source container and the test container, wherein the input end of the overheating container is communicated with the steam source container, the output end of the overheating container is communicated with the test container, and the overheating container and the steam source container, and the overheating container and the test container are controlled to be on and off through quick-opening valves; heating elements are arranged in the steam source container and the overheating container; and a heating device is arranged on a connecting pipeline of the overheating container and the test container.
Aiming at the problem that test equipment in the prior art cannot meet the equipment performance evaluation test requirements of a third-generation nuclear power unit under the severe environment working condition, the invention firstly provides a test system for performance evaluation of nuclear-grade equipment under the severe working condition, and an overheating container is connected between a steam source container and a test container, so that after gas is generated in the steam source container, the gas flows through the overheating container firstly and then enters the test container. The heating element in the steam source container evaporates water into saturated steam, and the heating element in the overheating container further heats the saturated steam to form overheated steam, so that an overheating environment can be quickly achieved in the test container. As the performance evaluation test of the third-generation nuclear power severe environment working condition equipment requires that the environmental temperature is increased from 50 ℃ to about 140 ℃ within 1s, and steam must rapidly enter the test container within 1s, the system is controlled to be switched on and off between the overheating container and the steam source container and between the overheating container and the test container through a quick-opening valve. The time of the quick-opening valve reaching a full-open state from closing can reach within 0.5s, so that the steam flow can reach the maximum at the opening moment, and the temperature rise efficiency in the test container is improved. The connecting pipeline of the overheating container and the test container is also provided with a heating device for heating the pipeline wall between the overheating container and the test container before the test, so that the overheating steam is prevented from condensing on the pipeline wall, and the overheating steam parameters are reduced to interfere with the temperature rising efficiency in the test container. When the system works, water is firstly added into the steam source container, the steam source container is sealed, and the heating element in the steam source container is started, so that the gas in the steam source container reaches a saturated steam state. The temperature of the saturated steam is also nearly proportional to the pressure curve, so the temperature of the saturated steam gradually rises as the pressure inside the source vessel increases. After the temperature of the saturated steam rises to a preset temperature, opening a quick opening valve between a steam source container and a superheating container to enable the saturated steam to rapidly enter the superheating container, closing the superheating container, and starting a heating element in the superheating container; and simultaneously starting the heating devices on the connecting pipelines of the overheating container and the test container. Because the overheating container is closed at the moment, saturated steam entering from the steam source container is gradually heated into the overheating steam along with the rise of air temperature, when the pressure and the temperature range of the overheating steam meet the performance evaluation test requirements under the severe working conditions of third-generation nuclear-grade equipment, all quick-opening valves between the overheating container and the test container are opened, and the overheating steam is supplied into the test container for testing. The quick-opening valve is completely opened within 0.5s, superheated steam rapidly flows into the test container through the preheated pipeline at the moment, so that the temperature rise rate in the test container can reach more than 100 ℃/s within 1s after the test container is opened, and the test requirement of third-generation nuclear-grade equipment is met. When the pressure of the overheating container and the pressure of the test container are balanced, high-temperature overheated steam in the overheating container cannot continuously enter the test container actively, heat can be transferred only in a heat conduction mode, the efficiency is low, and the temperature in the test container is easy to reduce. However, the system can perfectly avoid the problem, specifically, after the pressure of the overheating container and the test container is balanced, the quick opening valve between the steam source container and the overheating container is opened, and because high-pressure saturated steam exists in the steam source container, the pressure head in the steam source container pushes the overheated steam in the overheating container to continuously enter the test container until the test is finished, so that the secondary heating of the test container is realized simply and efficiently, the internal temperature of the test container can be rapidly raised, and the equipment performance evaluation requirement under the severe environment working condition of the third-generation nuclear power nuclear grade equipment design basis accident is completely met.
Furthermore, the output end of the overheating container is connected with N main gas transmission pipelines, each main gas transmission pipeline is provided with a quick-opening valve, one end of each main gas transmission pipeline, which is positioned at the downstream of the quick-opening valve, is branched into M tail-end gas transmission pipelines, and all the tail-end gas transmission pipelines are communicated into the test container; wherein M is more than or equal to 2, and N is more than or equal to 2. N main gas transmission pipelines output superheated steam outwards, and a large amount of superheated steam is rapidly provided for the test container through N terminal gas transmission pipelines multiplied by M, the temperature rise rate of the test container can be improved through a plurality of terminal gas transmission pipelines, and meanwhile the uniformity of the temperature in the test container can be improved.
Furthermore, a pressure monitoring unit, a temperature monitoring unit and a liquid level monitoring unit are arranged in the steam source container and the test container; and a pressure monitoring unit and a temperature monitoring unit are arranged in the overheating container. The pressure, temperature and liquid level conditions in the steam source container and the test container are monitored by the pressure monitoring unit, the temperature monitoring unit and the liquid level monitoring unit, so that the working personnel can flexibly regulate and control various parameters. Similarly, the pressure and the temperature in the superheated container are monitored by the pressure monitoring unit and the temperature monitoring unit, so that a worker can conveniently enter the test container after the pressure and the temperature of the superheated steam meet test requirements, and the use stability and the reliability of the system are ensured.
Preferably, the temperature monitoring unit in the test vessel is a fast response thermocouple. The acquisition frequency of the quick response thermocouple per second can reach more than 10 times, and the response sensitivity to the temperature change in the test container is greatly improved.
Preferably, a temperature monitoring unit is arranged on a connecting pipeline of the overheating container and the test container. The device is convenient for monitoring the temperature of the tube wall in real time when the pipeline is connected between the preheating overheating container and the test container in advance, ensures that the temperature of the tube wall is not lower than that of the overheating steam, thoroughly avoids the phenomenon that the overheating steam is condensed on the tube wall, and further improves the use stability of the device.
Preferably, an electric control valve for adjusting the flow is further arranged on a connecting pipeline between the overheating container and the steam source container. The flow of saturated steam from the steam source container into the overheating container is regulated and controlled through an electric control valve. The pressure is stably applied to the superheated container during the secondary temperature rise to push the superheated steam to gradually enter the test container to supplement heat.
One end of the auxiliary pipeline is communicated to the upstream end of the quick opening valve between the overheating container and the steam source container, and the other end of the auxiliary pipeline is communicated into the test container; and an electric control valve for adjusting the flow is arranged on the auxiliary pipeline. For traditional second generation nuclear equipment, need not to use superheated container to convert saturated steam into superheated steam, therefore this scheme sets up auxiliary line, through auxiliary line, can make the saturated steam that comes out from the vapour source container directly pass through auxiliary line and get into the performance evaluation test under the abominable operating mode of realization second generation nuclear equipment in the experimental container, make this system in the equipment performance evaluation test under the adverse circumstances operating mode of the equipment design benchmark accident of third generation nuclear power nuclear level, still can compromise the test that covers second generation nuclear power equipment, commercial nuclear power industry to being in the transition period of transformation has high adaptability.
Preferably, the quick-opening valve is a ball valve. The ball valve has small resistance after being opened, and the partial resistance coefficient is close to 0 when the ball valve is fully opened, so that the pressure loss can be greatly reduced, and the working stability is ensured.
The performance evaluation test method of the nuclear-grade equipment under the severe working condition comprises the following steps:
(a) adding water into the steam source container, sealing the steam source container, and starting a heating element in the steam source container to enable the gas in the steam source container to reach a saturated steam state;
(b) opening a quick-opening valve between the steam source container and the overheating container to enable saturated steam to enter the overheating container, closing the overheating container, and starting a heating element in the overheating container; simultaneously starting a heating device on a connecting pipeline of the overheating container and the test container;
(c) when the saturated steam in the overheating container is heated to be overheated steam with the temperature of 350-400 ℃ and the pressure of 2-3 MPa, opening all quick-opening valves between the overheating container and a test container, and supplying the overheated steam into the test container for testing;
(d) after the pressures of the superheated container and the test container are balanced, a quick opening valve between the steam source container and the superheated container is opened, and superheated steam in the superheated container is pushed by the pressure in the steam source container to continuously enter the test container until the test is finished.
The method can ensure that the internal temperature of the test container has extremely high uniformity and reliability, the temperature rise rate of the environmental temperature in 1 second inside the test container reaches more than 100 ℃/s, the temperature in 20 seconds reaches more than 220 ℃, and the equipment performance evaluation requirement of the nuclear-grade equipment of the third generation under the severe environment working condition of the design basis accident is fully met.
Preferably, the temperature of the saturated steam in the steam source container is controlled to be between 180 and 220 ℃ in the step (a).
Compared with the prior art, the invention has the following advantages and beneficial effects:
1. the test system and the test method for the performance evaluation of the nuclear-grade equipment under the severe working condition solve the problem that the test equipment in the prior art cannot meet the requirement of the equipment performance evaluation test of a third-generation nuclear power unit under the severe environment working condition, and achieve the purpose of completely covering the requirement of the equipment performance evaluation test under the severe environment working condition under the third-generation nuclear power standard.
2. The test system and the test method for performance evaluation of nuclear-grade equipment under severe working conditions are suitable for equipment performance evaluation tests under severe environment working conditions of third-generation nuclear-grade equipment design basis accidents, can also be used for covering tests of second-generation nuclear power equipment, and have extremely high adaptability to commercial nuclear power industries in transition periods.
Drawings
The accompanying drawings, which are included to provide a further understanding of the embodiments of the invention and are incorporated in and constitute a part of this application, illustrate embodiment(s) of the invention and together with the description serve to explain the principles of the invention. In the drawings:
FIG. 1 is a schematic diagram of a connection relationship in embodiment 1 of the present invention;
fig. 2 is a schematic connection diagram according to embodiment 2 of the present invention.
Reference numbers and corresponding part names in the drawings:
1-a steam source container, 2-a test container, 3-an overheating container, 4-a quick-opening valve, 5-a heating element, 6-a main gas pipeline, 7-a tail gas pipeline, 8-a pressure monitoring unit, 9-a temperature monitoring unit, 10-a liquid level monitoring unit, 11-an electric control valve and 12-an auxiliary pipeline.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is further described in detail below with reference to examples and accompanying drawings, and the exemplary embodiments and descriptions thereof are only used for explaining the present invention and are not meant to limit the present invention.
Example 1:
the test system for performance evaluation of nuclear-grade equipment under severe working conditions, as shown in fig. 1, comprises a steam source container 1, a test container 2 and a superheat container 3 connected between the steam source container 1 and the test container 2, wherein the input end of the superheat container 3 is communicated with the steam source container 1, the output end of the superheat container 3 is communicated with the test container 2, and the connection and disconnection between the superheat container 3 and the steam source container 1 and between the superheat container 3 and the test container 2 are controlled by a quick-opening valve 4; heating elements 5 are arranged in the steam source container 1 and the overheating container 3; and a heating device is arranged on a connecting pipeline of the overheating container 3 and the test container 2. When the system works, firstly, water is added into the steam source container 1, the steam source container 1 is sealed, and the heating element 5 in the steam source container 1 is started, so that the gas in the steam source container 1 reaches a saturated steam state. After the temperature of the saturated steam rises to 180-220 ℃, opening a quick opening valve 4 between the steam source container 1 and the overheating container 3 to enable the saturated steam to rapidly enter the overheating container 3, closing the overheating container 3, and starting a heating element 5 in the overheating container 3; the heating means on the connecting lines of the superheating vessel 3 and the test vessel 2 were activated simultaneously. The saturated steam is gradually heated to be superheated steam, when the pressure and the temperature range of the superheated steam are 350-400 ℃ and the pressure is 2-3 MPa, all the quick-opening valves 4 between the superheated container 3 and the test container 2 are opened, and the superheated steam is supplied into the test container 2 for testing. The quick-opening valve 4 is completely opened within 0.5s, and superheated steam rapidly flows into the test container 2 through the preheated pipeline at the moment, so that the temperature rise rate in the test container 2 can reach over 100 ℃/s within 1s after the test container is opened. After the pressure of the overheating container 3 and the pressure of the test container 2 are balanced, the quick opening valve 4 between the steam source container 1 and the overheating container 3 is opened, high-pressure saturated steam is used in the steam source container 1, so that the overheated steam in the overheating container 3 is pushed by a pressure head in the steam source container 1 to continue to enter the test container 2 until the test is finished, secondary heating of the test container 2 is realized simply and efficiently, the internal temperature of the test container 2 can be rapidly raised, the temperature can reach more than 220 ℃ in 20 seconds, and the equipment performance evaluation requirement under the severe environment working condition of the third-generation nuclear-grade equipment design basis accident is completely met.
Example 2:
as shown in fig. 2, in the test system for performance evaluation of nuclear-grade equipment under severe conditions, on the basis of embodiment 1, the output end of the overheating container 3 is connected to N main gas transmission pipelines 6, each main gas transmission pipeline 6 is provided with a quick-opening valve 4, one end of each main gas transmission pipeline 6 located downstream of the quick-opening valve 4 is branched into M tail-end gas transmission pipelines 7, and all the tail-end gas transmission pipelines 7 are communicated into the test container 2; wherein M is more than or equal to 2, and N is more than or equal to 2. A pressure monitoring unit 8, a temperature monitoring unit 9 and a liquid level monitoring unit 10 are arranged in the steam source container 1 and the test container 2; a pressure monitoring unit 8 and a temperature monitoring unit 9 are arranged in the overheating container 3. The temperature monitoring unit 9 in the test vessel 2 is a fast response thermocouple. A temperature monitoring unit 9 is arranged on a connecting pipeline of the overheating container 3 and the test container 2. And an electric control valve 11 for adjusting the flow is also arranged on a connecting pipeline between the overheating container 3 and the steam source container 1. The system also comprises an auxiliary pipeline 12, wherein one end of the auxiliary pipeline 12 is communicated to the upstream end of the quick opening valve 4 between the overheating container 3 and the steam source container 1, and the other end of the auxiliary pipeline 12 is communicated into the test container 2; an electric control valve 11 for adjusting the flow rate is arranged on the auxiliary pipeline 12. The quick-opening valve 4 is a ball valve.
Example 3:
a performance evaluation test method for nuclear-grade equipment under severe working conditions comprises the following steps: (a) adding water into the steam source container, sealing the steam source container, and starting a heating element in the steam source container to enable the gas in the steam source container to reach a saturated steam state; (b) opening a quick-opening valve between the steam source container and the overheating container to enable saturated steam to enter the overheating container, closing the overheating container, and starting a heating element in the overheating container; simultaneously starting a heating device on a connecting pipeline of the overheating container and the test container; (c) when the saturated steam in the overheating container is heated to be overheated steam with the temperature of 350-400 ℃ and the pressure of 2-3 MPa, opening all quick-opening valves between the overheating container and a test container, and supplying the overheated steam into the test container for testing; (d) after the pressures of the superheated container and the test container are balanced, a quick opening valve between the steam source container and the superheated container is opened, and superheated steam in the superheated container is pushed by the pressure in the steam source container to continuously enter the test container until the test is finished. The method can ensure that the internal temperature of the test container has extremely high uniformity and reliability, the temperature rise rate of the environmental temperature in 1 second inside the test container reaches more than 100 ℃/s, the temperature in 20 seconds reaches more than 220 ℃, and the equipment performance evaluation requirement of the nuclear-grade equipment of the third generation under the severe environment working condition of the design basis accident is fully met.
Preferably, the temperature of the saturated steam in the steam source container is controlled to be between 180 and 220 ℃ in the step (a).
The above-mentioned embodiments are intended to illustrate the objects, technical solutions and advantages of the present invention in further detail, and it should be understood that the above-mentioned embodiments are merely exemplary embodiments of the present invention, and are not intended to limit the scope of the present invention, and any modifications, equivalent substitutions, improvements and the like made within the spirit and principle of the present invention should be included in the scope of the present invention.
Claims (7)
1. The test system for performance evaluation of nuclear-grade equipment under severe working conditions comprises a steam source container (1) and a test container (2), and is characterized by further comprising a superheat container (3) connected between the steam source container (1) and the test container (2), wherein the input end of the superheat container (3) is communicated with the steam source container (1), the output end of the superheat container (3) is communicated with the test container (2), and the on-off of the superheat container (3) and the steam source container (1) and the superheat container (3) and the test container (2) are controlled by a quick-opening valve (4); heating elements (5) are arranged in the steam source container (1) and the overheating container (3); a heating device is arranged on a connecting pipeline of the overheating container (3) and the test container (2); the output end of the overheating container (3) is connected with N main gas transmission pipelines (6), each main gas transmission pipeline (6) is provided with a quick-opening valve (4), one end of each main gas transmission pipeline (6) positioned at the downstream of the quick-opening valve (4) is branched into M tail-end gas transmission pipelines (7), and all the tail-end gas transmission pipelines (7) are communicated into the test container (2); wherein M is more than or equal to 2, and N is more than or equal to 2; a temperature monitoring unit (9) is arranged on a connecting pipeline of the overheating container (3) and the test container (2); the device also comprises an auxiliary pipeline (12), wherein one end of the auxiliary pipeline (12) is communicated to the upstream end of the quick-opening valve (4) between the overheating container (3) and the steam source container (1), and the other end of the auxiliary pipeline (12) is communicated into the test container (2); an electric control valve (11) used for adjusting the flow is arranged on the auxiliary pipeline (12).
2. The test system for the performance evaluation of the nuclear-grade equipment under the severe working conditions according to claim 1, wherein a pressure monitoring unit (8), a temperature monitoring unit (9) and a liquid level monitoring unit (10) are arranged in the steam source container (1) and the test container (2); a pressure monitoring unit (8) and a temperature monitoring unit (9) are arranged in the overheating container (3).
3. The test system for the performance evaluation of the nuclear-grade equipment under the severe working conditions according to claim 2, wherein the temperature monitoring unit (9) in the test container (2) is a quick-response thermocouple.
4. The test system for the performance evaluation of the nuclear-grade equipment under the severe working conditions is characterized in that an electric control valve (11) for adjusting the flow is further arranged on a connecting pipeline between the overheating container (3) and the steam source container (1).
5. The test system for the performance evaluation of the nuclear-grade equipment under the severe working conditions, according to claim 1, wherein the quick-opening valve (4) is a ball valve.
6. The method for evaluating and testing the performance of the nuclear-grade equipment under the severe working conditions based on the test system of any one of claims 1 to 5 is characterized by comprising the following steps of:
(a) adding water into the steam source container (1), sealing the steam source container (1), and starting a heating element (5) in the steam source container (1) to enable the gas in the steam source container (1) to reach a saturated steam state;
(b) opening a quick-opening valve (4) between the steam source container (1) and the overheating container (3), enabling saturated steam to enter the overheating container (3), closing the overheating container (3), and starting a heating element (5) in the overheating container (3); simultaneously starting a heating device on a connecting pipeline of the overheating container (3) and the test container (2);
(c) when the saturated steam in the overheating container (3) is heated to be overheated steam with the temperature of 350-400 ℃ and the pressure of 2-3 MPa, opening all quick-opening valves (4) between the overheating container (3) and the test container (2), and supplying the overheated steam into the test container (2) for testing;
(d) after the pressure of the superheated container (3) and the pressure of the test container (2) are balanced, a quick-opening valve (4) between the steam source container (1) and the superheated container (3) is opened, and superheated steam in the superheated container (3) is pushed to continuously enter the test container (2) through the pressure in the steam source container (1) until the test is finished.
7. The method for the performance evaluation test of the nuclear-grade equipment under the severe working conditions according to claim 6, wherein the temperature of the saturated steam in the steam source container (1) is controlled to be 180-220 ℃ in the step (a).
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| WO2014125442A3 (en) * | 2013-02-15 | 2015-04-23 | Commissariat A L'energie Atomique Et Aux Energies Alternatives | Electricity generation facility comprising a device for producing steam of reduced height, application to pwr and bwr reactors |
| CN104392753A (en) * | 2014-10-13 | 2015-03-04 | 中国工程物理研究院材料研究所 | Experimental system used for simulating severe accident conditions of containment of nuclear power plant, and implementation method thereof |
| CN104966536A (en) * | 2015-07-14 | 2015-10-07 | 西安交通大学 | High-temperature working medium heat exchange test system using heat conducting oil as hot fluid and test method |
| CN107564593A (en) * | 2017-08-09 | 2018-01-09 | 华北电力大学 | Cooling test system and method outside a kind of pressure vessel |
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| CN108346477A (en) | 2018-07-31 |
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