CN211350119U - Large pressurized water reactor containment overall tightness test measuring system - Google Patents
Large pressurized water reactor containment overall tightness test measuring system Download PDFInfo
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- CN211350119U CN211350119U CN201921577427.2U CN201921577427U CN211350119U CN 211350119 U CN211350119 U CN 211350119U CN 201921577427 U CN201921577427 U CN 201921577427U CN 211350119 U CN211350119 U CN 211350119U
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Abstract
The utility model belongs to the technical field of nuclear safety monitoring, a large pressurized water reactor containment integral tightness test measurement system is related to, including the temperature measurement unit and the humidity measurement unit that are arranged in the containment of nuclear power plant, the flow measurement unit that is arranged outside the containment and is used for measuring the gas flow passing through the containment, the pressure measurement unit and the data acquisition unit and the data analysis unit that are arranged in the measuring chamber outside the containment, the pressure measurement unit can measure the atmospheric pressure and the pressure inside the containment; and the data obtained by the temperature, humidity, flow and pressure measuring units are transmitted to the data acquisition unit and then to the data analysis unit, and the data analysis unit calculates the data to obtain the overall leakage rate of the containment. The system can accurately calculate the overall leakage rate of the containment and verify the overall leakage rate; the integral leakage rate of containment vessels of different reactor types of pressurized water reactors can be measured; can also carry on the simulation and calculation of line; and the system adopts a redundancy design, so that the stability and the safety of the system are improved.
Description
Technical Field
The utility model belongs to the technical field of nuclear safety control, a whole leakproofness test measurement system of large-scale pressurized water reactor containment is related to.
Background
The containment vessel is the last safety barrier of a nuclear power plant and has the function of limiting and eliminating fission products in a reactor in a loss of coolant accident (LOCA) when the reactor generates the LOCA, so that the safety of nuclear power workers and the public is ensured, and therefore the guarantee of the integral tightness of the containment vessel after the accident occurs is very important for relieving the accident consequence.
The integral tightness of the containment vessel needs to be verified through a large-scale test, namely the integral tightness test of the containment vessel, also called as an A-type test, measures the integral leakage rate of the containment vessel through simulating the working condition after the LOCA accident occurs, and if the integral tightness of the containment vessel meets the design acceptance criteria, the integral tightness of the containment vessel is considered to be qualified. The simulation working condition is a normal-temperature high-pressure environment, the sealed containment needs to be inflated to achieve the test pressure, and the change of the dry air quality during the pressure maintaining period is monitored, so that the overall leakage rate of the containment is measured.
At present, the quality of dry air in a shell is generally measured at home and abroad by adopting an absolute pressure method, the pressure, the temperature and the humidity of the air in the shell need to be continuously measured, the quality of the dry air in a containment vessel at different moments is obtained according to an ideal gas equation, a dry air quality change curve is obtained according to the analysis of a quality point method, and then the integral leakage rate of the containment vessel is obtained through calculation.
The accuracy of the measurement of the whole leakage rate of the containment vessel is closely related to the measured temperature, humidity and pressure data in the containment vessel and also closely related to the data processing and analyzing processes.
The newly and autonomously researched large advanced pressurized water reactor in China adopts single-reactor arrangement and double-layer containment, and compared with the double-reactor arrangement and single-layer containment of the previous second-generation and second-generation improved nuclear power plants, the single-layer containment has larger space in the shell and more complicated equipment and pipeline arrangement; in order to meet higher nuclear safety requirements, the advanced pressurized water reactor adopts an active and passive design concept, a plurality of systems and equipment are added, the distribution condition of each compartment inside a plant is greatly changed, and the distribution of the free volume, the temperature field and the humidity field in the containment during operation is changed. The existing containment overall tightness test measurement system is developed on the basis of containment design parameters of second-generation and second-generation improved nuclear power plants, because the nuclear power plants are generally designed and built by adopting French standards, the calculation of the overall leakage rate also adopts French standards, verification tests are generally not included, and related standards are revised, so that higher requirements are placed on the calculation accuracy and evaluation standards of the overall leakage rate at home and abroad. Therefore, for the independently researched and developed large-scale advanced pressurized water reactor, if the existing measuring system is not suitable for being continuously adopted during the containment overall tightness test, the research and preparation of the measuring result are needed, the leakage rate calculation is more accurate, the verification test can be carried out, and the containment overall tightness test measuring system conforming to the characteristics of the large-scale advanced pressurized water reactor is used for testing the pressure-bearing tightness of the containment of the nuclear power plant under the design benchmark accident, so that the radioactive substance is prevented from leaking, and the safety of the natural environment and the public is ensured.
SUMMERY OF THE UTILITY MODEL
The utility model aims at the requirement of nuclear safety control, provide a whole leakproofness test measurement system of large-scale pressurized water reactor containment to can measure the whole leakage rate of containment high-efficiently, accurately in the whole leakproofness of containment is experimental, and verify measuring result, make the whole leakproofness evaluation of containment more accurate.
In order to achieve the above purpose, the utility model adopts the technical scheme that:
a large pressurized water reactor containment overall tightness test measuring system comprises a temperature measuring unit and a humidity measuring unit which are arranged in a containment of a nuclear power plant, a flow measuring unit which is arranged outside the containment and is used for measuring the flow of gas passing through the containment, a pressure measuring unit, a data acquisition unit and a data analysis unit which are arranged in a measuring chamber outside the containment, wherein the pressure measuring unit can measure the atmospheric pressure and the internal pressure of the containment; the data obtained by the temperature measuring unit, the humidity measuring unit, the flow measuring unit and the pressure measuring unit are transmitted to the data acquisition unit, the data acquisition unit transmits the data to the data analysis unit, the data analysis unit calculates the data to obtain the overall leakage rate of the containment, and the overall leakage rate of the containment is verified.
Furthermore, the data acquisition unit comprises a plurality of data acquisition devices and a plurality of acquisition control machines, and the data acquisition devices are connected with the temperature measurement unit and the humidity measurement unit through cables and are correspondingly connected with the acquisition control machines one by one through network cables; the collection control machine is connected with the pressure measurement unit and the flow measurement unit in a one-to-one correspondence manner through connecting wires, so that the data collection and storage functions of temperature, humidity, pressure and atmospheric pressure in the containment vessel are realized; the data acquisition unit and the acquisition control machine are both in one-use one-standby and redundant design.
Furthermore, the data analysis unit comprises a plurality of data analysis machines which are correspondingly connected with the acquisition control machine one by one through network cables, so that the functions of storing and analyzing the data of the whole leakage rate of the containment vessel are realized; the data analysis machine is designed in a redundant mode.
Furthermore, the temperature measuring unit comprises a plurality of temperature sensors, the temperature sensors are arranged in the containment vessel, and each temperature sensor is connected with all the data collectors in the data acquisition unit through cables, so that the internal temperature measuring function of the containment vessel is realized.
Furthermore, a plurality of humidity transmitters are arranged in the humidity measuring unit, the humidity transmitters are arranged in the containment vessel, and each humidity transmitter is connected with all the data acquisition units in the data acquisition unit through cables, so that the internal humidity measuring function of the containment vessel is realized.
Furthermore, the number of the pressure measurement units is a plurality, and each pressure measurement unit is correspondingly connected with one acquisition control machine;
the pressure measuring unit comprises a plurality of pressure transmitters and an atmosphere pressure gauge, pressure leading pipelines are arranged on the pressure transmitters and the atmosphere pressure gauge, and the pressure transmitters and the atmosphere pressure gauge are arranged in the measuring chamber;
one end of the pressure-leading pipeline arranged on the pressure transmitter penetrates through the containment vessel and is used for leading out the internal pressure of the containment vessel for the pressure transmitter and measuring the internal pressure;
the pressure leading pipeline arranged on the atmospheric pressure gauge is positioned in the measuring chamber and used for measuring the atmospheric pressure outside the containment vessel by the atmospheric pressure gauge;
the pressure transmitter and the atmospheric pressure gauge are connected with the acquisition control machine through connecting wires respectively, and both the pressure transmitter and the atmospheric pressure gauge are in a redundant design.
Furthermore, including two flow control valves and two flowmeters in the flow measurement unit, parallelly connected the setting is in on the outer penetrating member of containment, flow measurement unit passes through connecting wire and all the collection control machine corresponds the connection, flow measurement unit with the connection of collection control machine is the redundant design, realizes leaking the rate verification function.
Furthermore, the acquisition control machine is an industrial personal computer with built-in data acquisition software, receives and stores acquired temperature, humidity and pressure data in real time, transmits the data to the data analyzer, and monitors whether the data is abnormal on line to realize an alarm function.
Furthermore, the acquisition control machine can receive and store analog signals and transmit the analog signals to the data analyzer to realize the function of a simulation test.
Further, the data analyzer is a PC computer with built-in data analysis software, receives the data transmitted by the data acquisition unit in real time, stores, processes and analyzes the data, and realizes the function of calculating the whole leakage rate of the containment vessel in real time.
The utility model has the advantages as follows:
the utility model provides a large-scale pressurized water reactor containment integral sealing test measurement system adopts measuring equipment such as temperature sensor, humidity transducer, pressure transmitter, flowmeter, and the distribution of free volume, temperature field, humidity field in the simulation large-scale pressurized water reactor containment is accurate, and temperature, humidity, pressure, verification flow isoparametric in the accurate measurement shell adopt the calculation of latest international standard to obtain the containment integral leakage rate, and carry out actual verification to it, have improved reliability and the credibility of test result; the integral leakage rate of containment vessels of different reactor types of pressurized water reactors can be measured; meanwhile, simulation and calculation can be performed in a line mode, and technical support can be provided for the research of the overall sealing performance test of the containment vessels of different reactor types.
Drawings
FIG. 1 is a schematic diagram of a large pressurized water reactor containment vessel tightness test measuring system according to an embodiment of the present invention;
in the figure: 1-a temperature sensor, 2-a humidity transmitter, 3-a flow regulating valve, 4-a flowmeter, 5-a data collector, 6-a pressure guide pipeline, 7-a pressure transmitter, 8-an atmospheric pressure gauge, 9-an acquisition controller, 10-a data analyzer, 11-a containment vessel and 12-a measuring chamber.
Detailed Description
The invention is further described with reference to the following figures and examples.
The utility model provides a large-scale pressurized water reactor containment whole leakproofness test measurement system can measure temperature, humidity, pressure, verification flow isoparametric in the containment whole leakproofness test process, calculates and obtains the whole leakage rate of containment to carry out actual verification to it, thereby carries out accurate evaluation to the whole leakproofness of containment; the integral leakage rate of containment vessels of different reactor types of pressurized water reactors can be measured; meanwhile, offline simulation and calculation can be performed, and technical support is provided for the research of the overall tightness test of the containment vessels of different reactor types.
As shown in FIG. 1, the main body of the large pressurized water reactor containment overall tightness test measuring system is arranged in and out of a containment 11 and in a measuring chamber 12 located outside the containment 11, and comprises a temperature measuring unit, a humidity measuring unit, a flow measuring unit, a pressure measuring unit, a data acquisition unit and a data analysis unit.
The temperature measuring unit is arranged in the containment 11 and consists of a plurality of temperature sensors 1, and the accuracy of the instrument reaches industrial grade A;
the humidity measuring unit is arranged in the containment 11 and consists of a plurality of humidity transmitters 2, and the accuracy of the instrument reaches 1% RH;
the flow measurement unit is arranged outside the containment vessel 11 and consists of two flow regulating valves 3 and two flow meters 4 (the two flow regulating valves 3 are sequentially connected in parallel, the flow regulating valves 3 are close to the containment vessel 11), and the accuracy of the flow meters reaches 1% F.S.;
the pressure measuring units are arranged in the measuring chamber 12, each pressure measuring unit consists of a plurality of pressure transmitters 7 and 1 atmosphere pressure gauge 8, pressure leading pipelines 6 are arranged on the pressure transmitters 7 and the atmosphere pressure gauges 8, and the accuracy of the instruments reaches 0.01 percent F.S.;
the data acquisition unit is arranged in the measuring chamber 12 and consists of a plurality of data acquisition devices 5 and a plurality of acquisition controllers 9, and the data acquisition devices 5 are connected with the acquisition controllers 9 in a one-to-one correspondence manner;
the data analysis unit is arranged in the measuring chamber 12 and consists of a plurality of data analyzers 10, and the data analyzers 10 are correspondingly connected with the acquisition control machine 9 one by one.
The temperature sensors 1 are arranged in a factory building of the containment 11 according to a large pressurized water reactor temperature distribution scheme, a cable termination box built in a shell of the containment 11 penetrates through an electric penetrating piece to be connected to a terminal row in a measuring room 12, the terminal row is connected with all data collectors 5 in a data acquisition unit through cables, data acquired by each temperature sensor 1 are transmitted to all the data collectors 5 in the data acquisition unit in real time, and the data collectors 5 transmit the data to corresponding acquisition control machines 9 through network cables, so that the internal temperature measuring function of the containment 11 is realized.
The humidity transmitters 2 are arranged in a factory building of the containment 11 according to a large pressurized water reactor humidity distribution scheme, a cable termination box built in a shell of the containment 11 penetrates through an electric penetrating piece to be connected to a terminal row in a measuring room, the terminal row is connected with all data collectors 5 in a data acquisition unit through cables, data acquired by each humidity transmitter 2 are transmitted to all the data collectors 5 in the data acquisition unit in real time, and the data collectors 5 transmit the data to corresponding acquisition controllers 9 through network cables, so that the internal humidity measuring function of the containment 11 is realized.
Each pressure measuring unit is correspondingly connected with an acquisition controller 9; in the pressure measuring unit, a pressure transmitter 7 is connected with a pipeline communicated with the interior of the containment 11 through a pressure leading pipeline 6 and is used for measuring the internal pressure of the containment 11; the atmospheric pressure gauge 8 is directly placed in the measurement chamber 12 empty to measure atmospheric pressure. The pressure transmitter 7 and the atmospheric pressure gauge 8 are connected with the corresponding acquisition controller 9 through connecting wires (RS232 interfaces), and transmit the measured internal pressure and atmospheric pressure to the corresponding acquisition controller 9 when the pressure and atmospheric pressure are compacted, so as to realize the internal pressure measurement and atmospheric pressure measurement functions of the containment 11.
The flow measurement unit is correspondingly connected with all the acquisition controllers 9 in the data acquisition unit through connecting wires.
And when the measurement of the overall leakage rate of the containment is finished, starting to perform a verification test. The flow regulating valve 3 and the flowmeter 4 are sequentially arranged on a proper penetrating piece outside the containment 11; and opening the flow regulating valve 3, regulating the discharged air flow according to the test requirement, and measuring and verifying the test flow by using the flowmeter 4. The flowmeter 4 transmits the measured verification test flow to the acquisition controller 9 in real time through a connecting wire (RS485 interface), so that the leakage rate verification function is realized.
The acquisition control machine 9 is in real-time communication with the data analyzer 10 through a network cable, transmits data such as temperature, humidity, pressure, verification flow and the like measured in a test to the data analyzer 10, calculates through data analysis software built in the data analyzer 10 to obtain the overall leakage rate of the containment, compares the overall leakage rate with an acceptance criterion, and judges whether the overall tightness of the containment is qualified.
Data acquisition software developed according to design parameters of the large pressurized water reactor containment is arranged in the acquisition control machine 9, and the data acquisition control machine can receive, display and monitor parameters such as temperature, humidity, pressure, verification flow and the like in the test process in real time and give an alarm when data is abnormal or communication is interrupted.
The data analysis machine 10 is internally provided with containment overall tightness test data analysis software developed according to American ANSI/ANS56.8-2002 standard and French RCC-G88 standard, can receive data transmitted by the acquisition control machine 9 in real time, selects the American ANSI/ANS56.8-2002 standard or French RCC-G88 standard for analysis and calculation to obtain the containment overall leakage rate, and judges whether the containment overall leakage rate meets the acceptance criterion.
The pressure measuring unit consisting of a pressure transmitter 7, an atmospheric pressure gauge 8 and a pressure leading pipeline 6, the flow measuring unit consisting of a flow regulating valve 3 and a flowmeter 4, the data acquisition unit consisting of a data acquisition unit 5 and an acquisition control machine 9, and the data analysis unit consisting of a data analysis machine 10 are all used for one purpose. The temperature and humidity data measured in the containment vessel are simultaneously transmitted to all the data collectors 5. The whole system adopts a redundancy design, and the continuity and the reliability of test data are guaranteed.
The data acquisition unit can receive the containment overall tightness test simulation signal and transmit the containment overall tightness test simulation signal to the data analysis unit, or directly import the historical test data into the data analysis machine 10, and the simulation data or the historical test data can be analyzed and calculated according to the corresponding containment design parameter setting, so that technical support is provided for the containment overall tightness test research.
The flow measuring unit is directly connected with the acquisition control machine 9 through a connecting wire correspondingly, and can be independently connected with a computer on site for direct measurement, and after the measurement is finished, the data is led into the safety shell integral tightness test data analysis software built in the data analysis machine 10 for leakage rate result verification.
The utility model can be applied to the containment overall tightness test of different reactor type pressurized water reactors, and the points are distributed in the containment according to the arrangement scheme of the corresponding temperature sensor 1 and the humidity transmitter 2, and the corresponding setting is carried out on the data acquisition software built in the acquisition controller 9; meanwhile, the containment overall leakage rate of different reactor type pressurized water reactors can be measured by correspondingly setting the containment overall tightness test data analysis software built in the data analyzer 10 according to the free volume coefficient schemes of the corresponding temperature sensor 1 and the humidity transmitter 2.
The utility model discloses a redundant design still can expand measuring equipment quantity through increasing switching terminal row between each measuring cell and data acquisition unit, realizes many sets of equipment and moves side by side, can provide technical support for the application of new installation, new technology.
The utility model discloses can exchange or DC supply during the operation, provide incessant removal DC power supply, can realize the incessant operation function of factory building outage.
The device of the present invention is not limited to the specific embodiments described in the embodiments, and those skilled in the art can obtain other embodiments according to the technical solution of the present invention, which also belongs to the technical innovation scope of the present invention.
Claims (10)
1. A large pressurized water reactor containment integral tightness test measurement system is characterized in that: the device comprises a temperature measuring unit and a humidity measuring unit which are arranged in a containment (11) of a nuclear power plant, a flow measuring unit which is arranged outside the containment (11) and is used for measuring the flow of gas passing through the containment (11), a pressure measuring unit, a data acquisition unit and a data analysis unit which are arranged in a measuring chamber (12) outside the containment (11), wherein the pressure measuring unit can measure the atmospheric pressure and the internal pressure of the containment (11); and the data acquisition unit transmits the data to the data analysis unit, and the data analysis unit calculates the data to obtain the overall containment leakage rate.
2. The large pressurized water reactor containment overall tightness test measuring system of claim 1, which is characterized in that: the data acquisition unit comprises a plurality of data acquisition devices (5) and a plurality of acquisition control machines (9), wherein the data acquisition devices (5) are connected with the temperature measurement unit and the humidity measurement unit through cables and are connected with the acquisition control machines (9) in a one-to-one correspondence manner through network cables; the acquisition control machine (9) is connected with the pressure measurement unit and the flow measurement unit in a one-to-one correspondence manner through connecting wires, so that the data acquisition and storage functions of temperature, humidity, pressure and atmospheric pressure in the containment vessel (11) are realized; the data acquisition unit (5) and the acquisition control machine (9) are both in a one-use one-standby redundant design.
3. The large pressurized water reactor containment overall tightness test measuring system of claim 2, which is characterized in that: the data analysis unit comprises a plurality of data analyzers (10), the data analyzers (10) are correspondingly connected with the acquisition control machine (9) through network cables, and the functions of storing and analyzing the data of the whole containment leakage rate are realized; the data analysis machine (10) is designed in a redundant mode.
4. The large pressurized water reactor containment overall tightness test measuring system of claim 3, wherein: the temperature measuring unit comprises a plurality of temperature sensors (1), the temperature sensors (1) are arranged in the containment (11), each temperature sensor (1) is connected with all the data collectors (5) in the data collecting unit through cables, and the internal temperature measuring function of the containment (11) is achieved.
5. The large pressurized water reactor containment overall tightness test measuring system of claim 3, wherein: including a plurality of humidity transducer (2) in the humidity measurement unit, humidity transducer (2) set up in containment (11), every humidity transducer (2) all through the cable with in the data acquisition unit all data collection station (5) are connected, realize the inside humidity measurement function of containment (11).
6. The large pressurized water reactor containment overall tightness test measuring system of claim 3, wherein:
the number of the pressure measuring units is a plurality, and each pressure measuring unit is correspondingly connected with one acquisition control machine (9);
the pressure measuring unit comprises a plurality of pressure transmitters (7) and an atmospheric pressure gauge (8), pressure leading pipelines (6) are arranged on the pressure transmitters (7) and the atmospheric pressure gauge (8), and the pressure transmitters (7) and the atmospheric pressure gauge (8) are arranged in the measuring chamber (12);
one end of the pressure guide pipeline (6) arranged on the pressure transmitter (7) penetrates through the containment (11) and is used for guiding the internal pressure of the containment (11) out of the pressure transmitter (7) and measuring the internal pressure;
the pressure leading line (6) arranged on the atmospheric pressure gauge (8) is positioned in the measuring chamber (12) and is used for measuring the atmospheric pressure outside the containment (11) by the atmospheric pressure gauge (8);
the pressure transmitter (7) and the atmospheric pressure gauge (8) are respectively connected with the acquisition controller (9) through connecting wires, and the pressure transmitter (7) and the atmospheric pressure gauge (8) are both in redundant design.
7. The large pressurized water reactor containment overall tightness test measuring system of claim 3, wherein: including two flow control valves (3) and two flowmeters (4) in the flow measurement unit, set up on the outer penetration piece of containment (11), flow measurement unit passes through connecting wire and all gather controller (9) and correspond the connection, flow measurement unit with the connection of gathering controller (9) is redundancy design, realizes leakage rate verification function.
8. The large pressurized water reactor containment overall tightness test measuring system of claim 3, wherein: the acquisition control machine (9) is an industrial personal computer with built-in data acquisition software, receives and stores acquired temperature, humidity and pressure data in real time, transmits the data to the data analyzer (10), and monitors whether the data is abnormal on line to realize an alarm function.
9. The large pressurized water reactor containment overall tightness test measuring system of claim 3, wherein: the acquisition control machine (9) can receive and store analog signals and transmit the analog signals to the data analysis machine (10) to realize the function of a simulation test.
10. The large pressurized water reactor containment overall tightness test measuring system of claim 3, wherein: the data analysis machine (10) is a PC computer with built-in data analysis software, receives the data transmitted by the data acquisition unit in real time, stores, processes and analyzes the data, and realizes the function of calculating the whole leakage rate of the containment vessel in real time.
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Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN112037949A (en) * | 2020-09-09 | 2020-12-04 | 三门核电有限公司 | Method for executing cap buckling after loading in AP1000 containment overall leakage rate test |
| CN112435766A (en) * | 2020-11-13 | 2021-03-02 | 中广核工程有限公司 | Nuclear power station containment leakage rate measurement network precision measurement system |
| CN112432741A (en) * | 2020-11-04 | 2021-03-02 | 中广核工程有限公司 | Nuclear power station containment pressure monitoring device and monitoring method |
| CN113140340A (en) * | 2021-03-24 | 2021-07-20 | 中国核电工程有限公司 | Design method for integrity test of advanced pressurized water reactor nuclear power plant containment |
| CN113421674A (en) * | 2021-05-26 | 2021-09-21 | 华能山东石岛湾核电有限公司 | Method and device for calculating leakage rate of primary loop during high-temperature reactor cold test |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN112037949A (en) * | 2020-09-09 | 2020-12-04 | 三门核电有限公司 | Method for executing cap buckling after loading in AP1000 containment overall leakage rate test |
| CN112037949B (en) * | 2020-09-09 | 2022-05-13 | 三门核电有限公司 | Method for executing cap buckling after loading in AP1000 containment overall leakage rate test |
| CN112432741A (en) * | 2020-11-04 | 2021-03-02 | 中广核工程有限公司 | Nuclear power station containment pressure monitoring device and monitoring method |
| CN112435766A (en) * | 2020-11-13 | 2021-03-02 | 中广核工程有限公司 | Nuclear power station containment leakage rate measurement network precision measurement system |
| CN112435766B (en) * | 2020-11-13 | 2024-04-30 | 中广核工程有限公司 | Nuclear power station containment leak rate measurement network precision measurement system |
| CN113140340A (en) * | 2021-03-24 | 2021-07-20 | 中国核电工程有限公司 | Design method for integrity test of advanced pressurized water reactor nuclear power plant containment |
| CN113140340B (en) * | 2021-03-24 | 2022-07-26 | 中国核电工程有限公司 | Design method for integrity test of advanced pressurized water reactor nuclear power plant containment |
| WO2022199178A1 (en) * | 2021-03-24 | 2022-09-29 | 中国核电工程有限公司 | Design method and apparatus for containment integrity test of advanced pressurized water reactor nuclear power plant |
| GB2619465A (en) * | 2021-03-24 | 2023-12-06 | China Nuclear Power Eng Co Ltd | Design method and apparatus for containment integrity test of advanced pressurized water reactor nuclear power plant |
| WO2022218423A1 (en) * | 2021-04-16 | 2022-10-20 | 中广核工程有限公司 | System for testing containment building of nuclear power plant |
| CN113421674A (en) * | 2021-05-26 | 2021-09-21 | 华能山东石岛湾核电有限公司 | Method and device for calculating leakage rate of primary loop during high-temperature reactor cold test |
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