CN113674885A - Debugging method for accident discharge pipeline of steam generator blowdown system of pressurized water reactor nuclear power plant - Google Patents
Debugging method for accident discharge pipeline of steam generator blowdown system of pressurized water reactor nuclear power plant Download PDFInfo
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- 238000012360 testing method Methods 0.000 claims abstract description 83
- 238000002955 isolation Methods 0.000 claims abstract description 24
- 238000013461 design Methods 0.000 claims abstract description 22
- 239000007788 liquid Substances 0.000 claims description 26
- 238000007599 discharging Methods 0.000 claims description 16
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- 239000010865 sewage Substances 0.000 abstract description 6
- 238000013101 initial test Methods 0.000 abstract 1
- 238000005259 measurement Methods 0.000 description 4
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Abstract
The invention belongs to the technical field of nuclear power station safety, and particularly relates to a debugging method for an accident discharge pipeline of a blowdown system of a steam generator of a pressurized water reactor nuclear power plant. The accident discharge pipeline (2) of the steam generator sewage system is a plurality of, each accident discharge pipeline (2) corresponds to one steam generator (1), is led out from the steam generator (1) and is directly connected to a refueling water tank (4) arranged in a containment, and a drainage isolation valve (3) is arranged on the accident discharge pipeline, and the debugging method comprises the following steps: step S1, determining the purpose of the test; step S2, determining initial test conditions; step S3, determining acceptance criteria; and step S4, determining the test content. The invention fills the blank in the aspect of debugging and designing methods of the steam generator sewage system accident discharge pipeline in China, can verify the correctness of the performance of the steam generator sewage system accident discharge pipeline and the design conformity, and lays a foundation for the smooth on-site debugging in the follow-up process.
Description
Technical Field
The invention belongs to the technical field of nuclear power station safety, and particularly relates to a debugging method for an accident discharge pipeline of a blowdown system of a steam generator of a pressurized water reactor nuclear power plant.
Background
After the nuclear accident of the Japan Fudao, according to the adjustment of the nuclear energy policy of China and the development of the international trend, the new nuclear power plant in China adopts the advanced pressurized water reactor nuclear power technology with higher safety and stronger accident resistance. The design concept of the advanced pressurized water reactor nuclear power plant is mainly based on the design, manufacture, construction and operation experiences of the second generation improved pressurized water reactor nuclear power plant, and new concept design and items with new design characteristics are introduced.
In the design of typical two take place ofs improved generation PWR nuclear power plant steam generator blow-down systems, under the steam generator heat-transfer pipe rupture accident (SGTR) operating mode, in order to restrict the increase of damaged steam generator water level, the manual operation that resumes of blow-down systems carries out the maximum flow blowdown, discharges nuclear island waste liquid discharge system behind the blowdown water cooling, prevents that damaged steam generator from overflowing. However, it is noted that the piping and equipment downstream of the containment isolation valve outside of the steam generator blowdown system containment and the waste drain system are non-safety levels.
According to the existing blowdown system of the steam generator of the pressurized water reactor nuclear power plant, an accident discharge pipeline is additionally arranged on a containment vessel inner blowdown pipeline, leaked liquid in a damaged steam generator is discharged to a containment vessel inner replacement water tank, the water level and pressure of the damaged steam generator are adjusted in an SGTR accident, and therefore the requirement of assuming a safety function is met.
Due to the design change of the steam generator blowdown system, the accident discharge pipeline is required to be tested in the debugging stage of the nuclear power plant, and whether the accident discharge pipeline meets the accident analysis requirement or not is verified according to the function test of the accident discharge pipeline.
Because the medium state in the pipeline is vapor-liquid two-phase when the accident discharge pipeline is used, the flow of the vapor-liquid two-phase can not be accurately measured under the thermal state working condition, and the discharge capacity of the accident discharge pipeline can not be verified. Through the search of domestic documents and foreign documents, published documents related to debugging of the accident discharge pipeline are not found, and related design documents or documents show how the function is debugged and verified.
Disclosure of Invention
After the accident discharge pipeline of the blowdown system of the steam generator of the pressurized water reactor nuclear power plant is installed, the debugging stage is started, and the performance of the system is verified to meet the design requirement through system debugging. Because the accident discharge pipeline is a new design, no method for debugging the accident discharge pipeline exists at present, and the debugging difficulty and the workload are increased. The invention aims to ensure that the debugging work of the accident discharging pipeline of the steam generator sewage system is smoothly and orderly carried out, and provides a debugging method for the accident discharging pipeline of the steam generator sewage system, which is used for formulating the content of a debugging rule file and verifying the performance of the accident discharging pipeline.
In order to achieve the purposes, the technical scheme adopted by the invention is a debugging method for an accident discharge pipeline of a steam generator blowdown system of a pressurized water reactor nuclear power plant, the number of the accident discharge pipelines of the steam generator blowdown system is multiple, each accident discharge pipeline corresponds to one steam generator, the accident discharge pipeline is led out from the steam generator and is directly connected to a refueling water tank arranged in a containment, and a water discharge isolation valve is arranged on the accident discharge pipeline, and the debugging method comprises the following steps:
step S1, determining the purpose of the test
Aiming at the function and the design file of the accident discharge pipeline, analyzing the function requirement of the accident discharge pipeline and determining the purpose of the test;
step S2, determining the initial conditions of the test
According to the function of the accident discharge pipeline, determining that the test is carried out in a thermal state performance test stage, and setting parameters of the steam generator;
step S3, determining acceptance criteria
Based on the combing and analysis of the functions of the accident discharge pipeline, converting the acceptance method of the functions of the accident discharge pipeline into a test method operated by field debugging personnel, thereby establishing acceptance criteria under the thermal state performance test working condition;
step S4, determining the content of the test
Calculating the volume of discharged water by using a liquid level drop value of the secondary side of the steam generator within a period of time in a thermal state performance test stage, and then calculating the discharge mass flow; the period of time refers to the time when the discharge starts and ends;
and determining a test process, test error analysis and test result analysis according to the function of the accident discharge pipeline, the test purpose, the parameter setting of the steam generator in the design test process and the acceptance criteria.
Further, in the step S1, the purpose of the test is to verify whether the discharge flow rate of the emergency discharge line meets the requirement.
Further, before the step S2, the method further includes selecting a discharge start point and a discharge end point of the test, wherein the discharge start point selects a position of +0.6m of the water level of the steam generator, and the discharge end point selects a position of +0m of the water level of the steam generator.
Further, in the step S2, the accident discharging pipeline with the longest length and the largest resistance is selected for testing, the power supply of the drain isolation valve on the selected accident discharging pipeline is turned on, and before the test, the secondary pressure of the steam generator connected to the selected accident discharging pipeline reaches 4.0 mpa.a. People in the plant are evacuated; and adjusting the water level of the steam generator to be at the discharge starting point and the pressure to be 4.0MPa.
Further, in the test process of the step S4, the full open time of the drain isolation valve is recorded as the discharge start time, when the water level of the steam generator drops to the position of the discharge end point, the drain isolation valve is closed to end the discharge, the time when the drain isolation valve starts to close is the discharge end time, and the discharge time of the test is recorded.
Further, after the test process, carrying out discharge flow calculation, and calculating the average value of the liquid level of the steam generator measured by a measuring instrument at the discharge starting point; and calculating the liquid level average value measured by the discharge end point measuring instrument, calculating the volume of the discharged water, and calculating according to the discharge time to obtain the discharge flow.
Further, after the discharge flow is obtained, the error of the liquid level measuring channel, the error of the pressure measuring channel and the manufacturing error of the steam generator equipment are analyzed, and the comprehensive error of the test is calculated.
Further, in the step S3, determining that the acceptance criterion is that the discharge capacity of the accident discharge pipeline is equal to or greater than 4.74kg/S, while the secondary side of the steam generator is in a saturated state and the pressure is 4.0 mpa.a; discharge flow meets the acceptance criteria, indicating that the design requirements of the emergency discharge line of the steam generator blowdown system are met.
The invention has the beneficial effects that:
step S1 of the present invention determines the stage to be debugged by analyzing the function of the emergency discharge pipeline. The method aims to determine the stages needing debugging according to the main functions of the accident discharge pipeline, so as to provide reference and basis for the performance analysis of the accident discharge pipeline. The invention fills the gap of the prior debugging design method for the accident discharge pipeline of the steam generator sewage discharge system of the domestic pressurized water reactor nuclear power plant.
In the step S2, the debugging test is carried out in the thermal state performance test stage, so that the function is verified under the actual use condition of the steam generator blowdown system accident discharge pipeline, and the method for debugging the steam generator blowdown system accident discharge pipeline function is reasonably formulated.
In the step S3, the discharge capability of the steam generator blowdown system accident discharge pipeline is equivalently converted into the test parameters which are easy to use by field debugging personnel by designing acceptance criteria, so that the function of the steam generator blowdown system accident discharge pipeline can meet the design requirements, the field debugging personnel can operate more easily, and a foundation is laid for the smooth follow-up field debugging.
Step S4 of the present invention can verify the correctness of the steam generator blowdown system emergency drain line performance and the design compliance.
Drawings
FIG. 1 is a flow chart of a method for commissioning an emergency drain line of a steam generator blowdown system of a pressurized water reactor nuclear power plant in accordance with an embodiment of the present invention;
FIG. 2 is a schematic illustration of an emergency drain line of a pressurized water reactor nuclear power plant steam generator blowdown system in accordance with an embodiment of the present invention;
in the figure: 1-a steam generator, 2-an accident discharge pipeline, 3-a drainage isolation valve, 4-a refueling water tank arranged in a containment, 5-a containment, 6-an isolation valve arranged outside the containment, 7-a check valve (used for preventing a medium from flowing backwards), and 8-a manual isolation valve.
Detailed Description
The invention is further described below with reference to the figures and examples.
The invention provides a debugging method (as shown in figure 1) for accident discharge pipelines of a steam generator blowdown system of a pressurized water reactor nuclear power plant, wherein the number of the accident discharge pipelines 2 of the steam generator blowdown system (as shown in figure 2) is multiple, each accident discharge pipeline 2 corresponds to one steam generator 1, each accident discharge pipeline is led out of the corresponding steam generator 1 and is directly connected to a refueling water tank 4 arranged in a containment, and a drainage isolation valve 3 is arranged on each accident discharge pipeline, and the debugging method comprises the following steps:
step S1, determining the purpose of the test ("test" means debugging test, the same applies below)
Aiming at the main functions and related design files of the accident discharge pipeline 2, analyzing the requirements of the functions of the accident discharge pipeline 2 and determining the purpose of the test;
step S2, determining (debugging) test initial conditions
According to the function of the accident discharge pipeline 2, the fact that the test is carried out in the thermal state performance test stage is determined, and main parameters of the steam generator 1 need to be set, so that the smooth operation of the test is guaranteed; the thermal state is the condition of raising temperature and pressure under the condition of no nuclear fuel loading, and the actual operation condition of a nuclear power plant is simulated.
Step S3, determining acceptance criteria
Based on the combing and analysis of the functions of the accident discharge pipeline 2, equivalently converting the acceptance method of the functions of the accident discharge pipeline 2 into a test method which is easy to operate by field debugging personnel, thereby establishing acceptance criteria under the thermal state performance test working condition;
step S4, determining the content of the test
Because the saturated water or slightly undersaturated supercooled water is arranged in the steam generator 1 during the thermal state performance test, the refueling water tank 4 in the containment is an open water tank, and the liquid level pressure is normal pressure, two-phase flow can occur in the accident discharge pipeline 2 during the thermal state performance test, so that direct flow measurement cannot be carried out by using an online flow measurement device;
step S4 includes calculating the volume of water discharged by the liquid level drop value of the secondary side of the steam generator 1 in a period of time in the thermal state performance test stage, and then calculating the discharge mass flow; the period of time refers to the time when the discharge begins and ends;
the method further comprises the step of determining a debugging test process, a test error analysis, a test result analysis and the like according to the function and the test purpose of the accident discharge pipeline 2, the main parameter setting of the steam generator 1 in the design test process, the acceptance criterion and the like.
The accident discharge pipeline of the blowdown system of the steam generator of the pressurized water reactor nuclear power plant has the main functions that the electric drainage isolation valve 3 on the accident discharge pipeline 2 of the blowdown system of the steam generator is opened, leaked liquid in the damaged steam generator 1 is discharged to the replacement water tank 4 in the containment, the damaged steam generator 1 is depressurized, meanwhile, the water level of the damaged steam generator 1 is limited, and the damaged steam generator 1 is prevented from overflowing; in the latter stage of the SGTR accident, the operator may monitor the state of the damaged steam generator 1 according to the regulations, and adjust the pressure and water level of the damaged steam generator 1 by manually opening and closing one of the water discharge isolation valves 3 of the accident discharge pipeline in the main control room, to ensure that the damaged steam generator 1 does not overflow, and thus in step S1, the purpose of the test is to verify whether the discharge flow of the accident discharge pipeline 2 meets the requirements.
Before step S2, the method further includes selecting a discharge start point and a discharge end point of the test, the discharge start point selecting a position of +0.6m of the water level of the steam generator 1, and the discharge end point selecting a position of +0m of the water level of the steam generator 1 (i.e., the discharge to the water level of +0m ends). If the discharge time of the accident discharge pipeline test is too short, the descending amplitude of the liquid level of the steam generator is not obvious, and the measurement error can be increased. If the discharge time of the accident discharge pipeline test is too long, the temperature of the refueling water tank in the containment vessel is excessively increased, and the discharged steam-water mixture cannot be completely absorbed by cold water in the water pool and directly enters the environment, so that the temperature in the containment vessel is increased. Therefore, a reasonable emission starting point and a reasonable emission end point need to be determined, so that the test result is credible, and the environmental condition in the containment is not influenced. And selecting an initial liquid level of +0.6m through conservative decision, and finishing the discharge until the initial liquid level reaches +0 m.
In step S2, the accident discharging line 2 having the longest length and the largest resistance is selected and tested, and the power supply of the drain isolation valve 3 (the drain isolation valve 3 is an electric drain isolation valve) on the selected accident discharging line 2 is turned on, and before the test, the secondary pressure of the steam generator 1 connected to the selected accident discharging line 2 reaches 4.0 mpa.a. People in the factory building are evacuated, and the entry of irrelevant people in the test is prevented; the water level of the steam generator 1 is adjusted to be at the discharge start point (+ about 0.6 m) and the pressure is about 4.0mpa.
In the test process of step S4 after step S2, the full open time of the drain isolation valve 3 is recorded as the discharge start time, when the water level of the steam generator 1 drops to the position of the discharge end (+ about 0 m), the drain isolation valve 3 is closed to end the discharge, the time when the drain isolation valve 3 starts to be closed is the discharge end time, and the discharge time of the test is recorded.
After the test process, performing discharge flow calculation, and calculating the average value of the liquid level of the steam generator 1 measured by the measuring instrument at the discharge starting point (i.e. the initial liquid level of the test); and calculating the average value of the liquid level measured by the measuring instrument at the discharge end point (namely the end liquid level of the test), calculating the volume of the discharged water, and calculating the discharge flow according to the discharge time.
And after the discharge flow is obtained, analyzing the tested liquid level measurement channel error, pressure measurement channel error, steam generator equipment manufacturing error and the like, and calculating the comprehensive error of the test.
In step S3, it is determined that the contingency discharge line test is performed during the thermal state performance test in order to make the test as close as possible to the actual contingency conditions. According to the analysis of the SGTR accident process, determining that the acceptance criterion is that the discharge capacity of the accident discharge pipeline 2 is equal to or more than 4.74kg/s, and the secondary side of the steam generator 1 corresponding to the mass flow is in a saturated state and the pressure is 4.0 MPa.a; the discharge flow meets the acceptance criteria, which means that the design requirements of the accident discharge pipeline 2 of the blowdown system of the steam generator are met; the acceptance criterion provides a judgment standard of a test result for field debugging personnel.
Finally, the test process part (including error analysis and result analysis) of the debugging method for the accident exhaust pipeline of the steam generator blowdown system of the pressurized water reactor nuclear power plant is illustrated.
An initial liquid level of +0.6m was selected and the discharge to +0m was ended, the discharge time of the test was recorded as 1199s and the liquid level change during the test as 582.5 mm. The pressure in the discharge test was 4.04MPa.a, and the volume of discharged water was calculated to be 8.3m in discharge volume3And then the discharge flow rate is calculated to be 5.52kg/s according to the discharge time 1199 s.
The total error of the liquid level measuring channel is 0.847%, the total error of the pressure measuring channel is 0.804%, the volume deviation caused by the steam generator manufacture related to the accident discharge pipeline test is 0.14%, and the comprehensive error of the test is calculated to be 1.176%.
Acceptance criterion value qaConsidering that the test error is 1.176%, the flow rate value obtained by converting the positive deviation is 4.74/s as follows:
qt≥(1+1.176％)*4.74kg/s＝4.796kg/s
test value the mass of the discharge fluid 5.52kg/s was converted to a discharge flow of 5.45kg/s at a pressure of 4.0MPa.
5.45kg/s >4.796kg/s, so the test results meet the acceptance criteria requirements.
5.45kg/s considers the comprehensive error of the test and takes the negative deviation to obtain a test value of 5.386kg/s, 5.386kg/s >4.74kg/s, so that the test result meets the requirement of acceptance criterion.
The device according to the present invention is not limited to the embodiments described in the specific embodiments, and those skilled in the art can derive other embodiments according to the technical solutions of the present invention, and also belong to the technical innovation scope of the present invention.
Claims (8)
1. The debugging method of the accident discharge pipeline of the steam generator blow-down system of the pressurized water reactor nuclear power plant comprises the following steps that the accident discharge pipeline (2) of the steam generator blow-down system is a plurality of, each accident discharge pipeline (2) corresponds to one steam generator (1), the accident discharge pipeline is led out from the steam generator (1) and is directly connected to a refueling water tank (4) arranged in a containment, and a drainage isolation valve (3) is arranged on the accident discharge pipeline:
step S1, determining the purpose of the test
Aiming at the function and design file of the accident discharge pipeline (2), analyzing the requirement of the function of the accident discharge pipeline (2) and determining the purpose of the test;
step S2, determining the initial conditions of the test
According to the function of the accident discharge pipeline (2), determining that the test is carried out in a thermal state performance test stage, and setting parameters of the steam generator (1);
step S3, determining acceptance criteria
Based on the combing and analysis of the functions of the accident discharge pipeline (2), converting the acceptance method of the functions of the accident discharge pipeline (2) into a test method operated by field debugging personnel, thereby establishing acceptance criteria under the thermal state performance test working condition;
step S4, determining the content of the test
Calculating the volume of discharged water by using a secondary side liquid level drop value of the steam generator (1) in a period of time in a thermal state performance test stage, and then calculating the discharge mass flow; the period of time refers to the time when the discharge starts and ends;
the method also comprises the steps of determining a test process, analyzing test errors and analyzing test results according to the functions of the accident discharge pipeline (2), the test purpose, the parameter setting of the steam generator (1) in the design test process and the acceptance criteria.
2. The debugging method for the accident discharging pipeline of the steam generator blowdown system of the pressurized water reactor nuclear power plant as set forth in claim 1, wherein: in the step S1, the purpose of the test is to verify whether the discharge flow of the accident discharge line (2) meets the requirements.
3. The debugging method for the accident discharging pipeline of the steam generator blowdown system of the pressurized water reactor nuclear power plant as set forth in claim 1, wherein: before the step S2, the method further includes selecting a discharge start point and a discharge end point of the test, the discharge start point selecting a +0.6m position of the water level of the steam generator (1), and the discharge end point selecting a +0m position of the water level of the steam generator (1).
4. The debugging method for the accident exhaust pipeline of the steam generator blowdown system of the pressurized water reactor nuclear power plant as set forth in claim 3, wherein: in the step S2, the accident discharging pipeline (2) having the longest length and the largest resistance is selected for testing, the power supply of the drain isolation valve (3) on the selected accident discharging pipeline (2) is turned on, and before the test, the secondary pressure of the steam generator (1) connected with the selected accident discharging pipeline (2) reaches 4.0 mpa.a. People in the plant are evacuated; and adjusting the water level of the steam generator (1) to be at the discharge starting point and the pressure to be 4.0MPa.
5. The debugging method for the accident exhaust pipeline of the steam generator blowdown system of the pressurized water reactor nuclear power plant as set forth in claim 4, wherein: in the test process of the step S4, recording the full open time of the drain isolation valve (3) as the discharge start time, closing the drain isolation valve (3) to end the discharge when the water level of the steam generator (1) drops to the position of the discharge end point, and recording the discharge time of the test, wherein the time when the drain isolation valve (3) starts to close is the discharge end time.
6. The debugging method for the accident exhaust pipeline of the steam generator blowdown system of the pressurized water reactor nuclear power plant as set forth in claim 5, wherein: after the test process, carrying out discharge flow calculation, and calculating the average value of the liquid level of the steam generator (1) measured by a measuring instrument at the discharge starting point; and calculating the liquid level average value measured by the discharge end point measuring instrument, calculating the volume of the discharged water, and calculating according to the discharge time to obtain the discharge flow.
7. The debugging method for the accident discharging pipeline of the steam generator blowdown system of the pressurized water reactor nuclear power plant as set forth in claim 6, wherein: and after the discharge flow is obtained, analyzing the error of the liquid level measuring channel, the error of the pressure measuring channel and the manufacturing error of the steam generator equipment in the test, and calculating the comprehensive error of the test.
8. The debugging method for the accident discharging pipeline of the steam generator blowdown system of the pressurized water reactor nuclear power plant as set forth in claim 1, wherein: in the step S3, determining the acceptance criterion as that the discharge capacity of the accident discharge pipeline (2) is equal to or more than 4.74kg/S, and the secondary side of the steam generator (1) is in a saturated state and the pressure is 4.0 MPa.a; discharge flow meets the acceptance criteria, i.e. indicates that the design requirements of the accident discharge line (2) of the steam generator blowdown system are met.
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