CN111680257B - Method for calculating leakage rate of steam generator during heat test of nuclear power plant - Google Patents
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Abstract
The invention discloses a method for calculating the leakage rate of a steam generator during a heat test of a nuclear power plant, which comprises the following steps: determining preconditions, sampling, analyzing the sample and calculating the leak rate of the steam generator; the invention initiates a calculation method for the leakage rate of the primary side and the secondary side of the steam generator during the thermal state function test of the nuclear power plant, and ensures the accuracy of the calculation result under the dynamic condition; according to the calculation method disclosed by the invention, different calculation formulas can be selected according to different continuous time of the primary side leakage rate test and the secondary side leakage rate test of the steam generator and different states of the unit during the thermal state function test of the nuclear power station, so that the application range of the calculation method is increased, and the accuracy of the calculation result of the leakage rate of the steam generator during the thermal state function test of the nuclear power station is further ensured; the calculation method provided by the invention is used for determining the sampling position and sampling method for executing the primary side-to-secondary side leakage rate test of the steam generator during the thermal state function test of the nuclear power station.
Description
Technical Field
The invention relates to the field of leakage test of a steam generator of a pressurized water nuclear reactor power plant, in particular to a calculation method of the leakage rate of the steam generator during the hot test of the nuclear power plant of the pressurized water nuclear reactor power plant, wherein the leakage rate test of the primary side and the secondary side of the steam generator is executed during the hot functional test.
Background
The Steam Generator (SG) is a junction of a first loop and a second loop of the nuclear power plant, and has the main function of transferring heat in a first loop coolant to a second loop feed water, and heating the feed water to generate steam for driving a steam turbine to generate electricity; thereby playing the roles of heat exchange and energy transfer; at the same time, SG also has the function of preventing the radioactivity of the primary loop from diffusing into the secondary loop, belonging to the secondary barrier of 3-channel deep defenses of nuclear radiation of nuclear power plant. The heat transfer tube and the tube plate of the steam generator are the interfaces of the medium of the first loop and the medium of the second loop, and if the sealing effect is poor, the radioactive coolant in the first loop can enter the second loop, so that the radioactivity is diffused, and the harm to personnel and the environment is caused. Therefore, it is clearly required in each plant design document that in order to verify the tightness of the heat transfer tubes and tube sheets of the steam generator during the commissioning phase, a primary lateral secondary leak rate test of the steam generator must be performed.
In the prior art, most domestic power stations execute steam generator leakage rate tests under the condition of primary loop cold state, and the secondary side of the steam generator is in a standing state. The secondary side of the SG is filled with desalted water, no water supply, no pollution discharge and no steam. The primary-side-to-secondary-side leakage rate of SG was calculated by measuring the amount of increase in boron concentration on the secondary side of SG over a certain period of time. The calculation formula is as follows:
note that:
v-the rate of leakage from the primary side to the secondary side of the steam generator, L/h;
x is the boron concentration of the reactor coolant, mg/L;
y-rise in boron concentration of the steam generator at two moments, mg/L;
v' — volume of steam generator water, L;
t-time interval of two samplings, h.
The method is a traditional steam generator leakage rate calculation method, and in the actual test process, a part of pressurized water reactor nuclear power stations (such as AP 1000) execute a steam generator primary side-to-secondary side leakage rate test during a thermal state function test. Steam generator leak rate test was performed during the thermal state functional test: the secondary side of the steam generator is the same as the operation working condition, continuous water supplementing is needed for maintaining the liquid level of the steam generator, small flow pollution discharge is maintained, and steam is generated at the same time; the secondary side medium of the steam generator is dynamically changed, the traditional steam generator leakage rate calculation method cannot meet the requirement, and how to accurately calculate the leakage rate of the steam generator in the state is a great difficulty.
Disclosure of Invention
The invention provides a calculation method of the leakage rate of the steam generator, which is suitable for executing the leakage rate test of the steam generator during the thermal state function test under the dynamic change state.
The technical scheme of the invention is as follows:
a method for calculating the leakage rate of a steam generator during a heat test of a nuclear power plant comprises the following steps:
step (1) determining preconditions;
and (2) sampling: sampling points are respectively arranged at the dirt discharging position of the steam generator, the water supply inlet position of the steam generator and the steam outlet position of the steam generator, sample collection is respectively carried out on all the sampling points at three moments, and the time interval between the two moments is more than or equal to 2 hours.
Step (3) analyzing the sample: carrying out boron concentration analysis on samples collected by all sampling points;
and (4) calculating the leakage rate of the steam generator, and calculating based on data of sampling analysis and system parameter setting, wherein the calculation principle is as follows:
when the steady time of the unit state is less than or equal to 24 hours, the calculation method is as follows
When the steady time of the unit state is more than 24 hours, the calculation method is that
When the condensate water is refined and put into operation, the boron concentration in the steam is lower than the detection limit, and the unit state stabilization time is more than 24 hours, the calculation method is as follows:
wherein V is the volume of the steam generator (mW); ct is the boron concentration (mg/L) in the steam generator; fw is the feed water flow rate (m < n >/h) of a single steam generator, and Cw is the boron concentration (mg/L) of the feed water of the steam generator; fs is the flow rate (mw/h) of the steam generator; cs is the boron concentration (mg/L) of the steam generator steam; f (F) l A speed (mIng/h) of leakage from the primary side to the secondary side; cr is the boron concentration (mg/L) in the primary circuit; fb is the flow (mW/h) of the blowdown of the steam generator.
Preferably, the determining preconditions in the step (1) are specifically: the temperature of the first loop was determined to be 292℃and the pressure to be 15.4MPa.
Preferably, the determining preconditions in the step (1) are specifically: confirming that the liquid level keeping stable time of the steam generator is more than or equal to 4 hours, confirming that the sewage discharge flow of the steam generator is regulated to the maximum, the flow keeping stable time is more than or equal to 4 hours, confirming that the water supply flow keeping stable time of the steam generator is more than or equal to 4 hours, confirming that the steam flow keeping stable time of the steam generator is more than or equal to 4 hours, and confirming that the primary circuit boron concentration is 500-1000 mg/L.
Preferably, the detection limit of the boron concentration in a first loop when analyzing the sample is less than or equal to 50mg/L, and the analysis error is less than or equal to 5mg/L; the pollution discharge of the steam generator, the water supply of the steam generator and the detection limit of the steam sample analysis method of the steam generator are less than or equal to 1 mug/L, and the detection error is less than or equal to 1 mug/L.
The beneficial effects of the invention include:
(1) The invention discloses a calculation method of the leakage rate of a steam generator in a thermal test period of a nuclear power plant, which initiates a calculation method of the leakage rate of the primary side and the secondary side of the steam generator executed in the thermal function test period of the nuclear power plant, and ensures the accuracy of a calculation result of the steam generator under a dynamic condition;
(2) According to the calculation method, different calculation formulas can be selected according to different continuous time of the primary side leakage rate test and the secondary side leakage rate test of the steam generator during the thermal state function test of the nuclear power station, so that the application range of the calculation method is increased, and the accuracy of the calculation result of the leakage rate of the steam generator during the thermal state function test of the nuclear power station is further ensured;
(3) The calculation method provided by the invention is used for determining the test precondition, sampling position, sampling method and analysis detection lower limit value requirement of the primary side leakage rate test and the secondary side leakage rate test of the steam generator during the thermal state function test of the nuclear power station.
Drawings
FIG. 1 is a schematic diagram of steam generator leakage sources and consumption during a nuclear power plant hot test;
FIG. 2 is a graph showing the trend of the concentration of boron in the blowdown gas when the steam generator leak rate test is performed during the heat test of the nuclear power plant.
Detailed Description
The present invention will be described in detail with reference to specific examples.
A method for calculating the leakage rate of a steam generator during a heat test of a nuclear power plant comprises the following steps:
step (1) determining preconditions:
a: the temperature of a first loop is 292 ℃ and the pressure is 15.4MPa;
b: confirming that the liquid level of the steam generator is kept stable for more than or equal to 4 hours;
c: confirming that the sewage discharge flow of the steam generator is regulated to the maximum, and keeping the flow stable for more than or equal to 4 hours;
d: confirming that the steam generation water supply flow keeps stable for more than or equal to 4 hours;
e: confirm that the steam flow of the steam generator keeps stable for more than or equal to 4 hours
f: the boron concentration of the primary circuit is confirmed to be 500-1000 mg/L, and the boron concentration of the primary circuit is not changed in the test process.
And (2) sampling: sampling points are respectively arranged at the dirt discharging position of the steam generator, the water supply inlet of the steam generator and the steam outlet of the steam generator, and sample collection is carried out on each sampling point at three moments, wherein the interval time of two continuous sampling is more than or equal to 2 hours; the time interval between two sampling is 4 hours, and the specific method is that sampling is carried out at the sampling points at three moments of t1, t2 and t3, and the time interval between t1, t2 and t3 is 4 hours; 4 samples were taken for each sampling point, 2 of which were used for analysis and 2 of which were used for backup.
Step (3) analyzing the sample: carrying out boron concentration analysis on samples collected by all sampling points; the detection limit of the first loop sample analysis method is less than or equal to 50mg/L, and the analysis error is less than or equal to 5mg/L; the pollution discharge of the steam generator, the detection limit of the water supply of the steam generator and the analysis method of the steam sample of the steam generator should be less than or equal to 1 mug/L, and the detection error should be less than or equal to 1 mug/L.
And (4) calculating the leakage rate of the steam generator, and calculating based on data of sampling analysis and system parameter setting, wherein the calculation principle and the deduction process are as follows:
referring to fig. 1, a schematic diagram of the source and consumption of the steam generator leakage during the thermal state function test of the nuclear power plant, equation (1) can be obtained according to the source and consumption path of boron element in the steam generator:
（1）
wherein: v- -the volume of the steam generator, m_phase;
ct- -boron concentration in the steam generator, mg/L;
fw- -the water supply flow rate of a single steam generator, m/h;
cw- -boron concentration of steam generator feed water, mg/L;
fs— flow of steam generator steam, m/h;
cs- -boron concentration of steam generator steam, mg/L;
fl- -the rate of primary to secondary leakage, m < o >/h;
cr- -the concentration of boron in the primary circuit, mg/L;
fb- -flow of the blowdown of the steam generator, m/h.
(one) the first conversion method of equation (1):
converting the formula (1) to obtain a calculation formula (2) of the once side direction two-measurement leakage rate of the steam generator:
（2）
the expression (2) can be used to obtain:
（3）
（4）
wherein:
F l1 -measuring the leakage rate from the primary side to the secondary side of SG for the first calculation;
F l2 -measuring the leakage rate from the primary side to the secondary side of SG by a second calculation;
C t1 measuring the boron concentration of SG pollution discharge at the moment of-t 1, and mg/L;
C t2 measuring the boron concentration of SG pollution discharge at the moment of-t 2, and mg/L;
C t3 measuring the boron concentration of SG pollution discharge at the moment of-t 3, and mg/L;
C w1 measuring the boron concentration of SG water at the moment of-t 1 and mg/L;
C w2 measuring the boron concentration of SG water at the moment of-t 2, and mg/L;
C w3 measuring the boron concentration of SG water at the time of-t 3, mg/L;
C S1 measuring the boron concentration of SG steam at the time of-t 1, and mg/L;
C S2 measuring the boron concentration of SG steam at the time of-t 2, and mg/L;
C S3 -time t3Measuring the boron concentration of SG steam, mg/L;
cr- -the boron concentration of the previous loop, mg/L;
time difference h between time dt 1-t 2 and time t 1;
time difference h between time dt 2-t 3 and time t 2.
(II) a second conversion method of equation (1):
converting equation (1) into
（5）
Taking the integral can obtain:
（6）
it is apparent that, when t=0,is set to be 0, the number of the components is set to be 0,
converting formula (6):
（7）
depending on the course of the leak it is possible to obtain,，
further the formula can be obtained:
（8）
（9）
further derivations may be made:
（10）
when the water supply flow rate F w Boron concentration C of feed water w Steam flow F s Concentration of vapor boron C S Flow rate of sewage F b Primary-side-to-secondary-side leakage rate F l First circuit boron concentration C r And when the SG liquid level is unchanged, V, the boron concentration Ct and time of SG pollution discharge are exponential correlation functions. The trend of the change is shown in fig. 2.
About 0.2h -1 When t is more than or equal to 24h, the formula of the formula is->8.2E-3，/>At this time, the formula (10) is simplified to obtain:
（11）
the data obtained by sampling and measuring in three time points are averaged respectively to obtain:
（12）；
when the fine treatment of the condensate is put into operation entirely and it is assumed that the steam does not carry boron, the boron concentration cw=0 of the feed water can be considered at this time, the boron concentration cs=0 in the steam, and the formula (11) can be further simplified as:
（13）
substituting the sampling results of the SG pollution discharge at the time t1, t2 and t3 into a formula (13) to obtain:
（14）
based on the above-described derivation process, in the actual calculation process:
(1) When the steady time of the unit state is less than or equal to 24 hours, adopting a first calculation method, namely formulas (3) and (4), calculating the leakage rate of the primary side and the secondary side of the steam generator, and taking a larger value of the two calculation results.
(2) When the steady time of the unit state is more than 24 hours, and the deviation of the boron concentration of the pollution discharge of the steam generator is measured for three times and is less than 5%, the boron concentration in the pollution discharge of the SG is balanced, and the leakage rate of the primary side and the secondary side of the steam generator is calculated by adopting a second calculation method, namely a formula (12).
(3) When the condensed water is put into operation for fine treatment, the boron concentration in the steam is lower than the detection limit, and the steady state time of the unit is more than 24 hours, a third calculation formula (14) is adopted to calculate the leakage rate of the primary side and the secondary side of the steam generator.
The foregoing description of the preferred embodiments of the invention is not intended to limit the invention to the particular embodiments disclosed, but on the contrary, the intention is to cover all modifications, equivalents, and alternatives falling within the spirit and scope of the invention as defined by the appended claims.
Claims (2)
1. A method for calculating the leakage rate of a steam generator during a heat test of a nuclear power plant comprises the following steps:
step (1) determining preconditions;
and (2) sampling: sampling points are respectively arranged at the dirt discharging position of the steam generator, the water supply inlet of the steam generator and the steam outlet of the steam generator, and sample collection is carried out on each sampling point at three moments;
step (3) analyzing the sample: carrying out boron concentration analysis on samples collected by all sampling points;
and (4) calculating the leakage rate of the steam generator, wherein the calculation is performed based on data of sampling analysis and system parameter setting, and the calculation principle is as follows:
when the steady time of the unit state is less than or equal to 24 hours, the calculation method is as follows
When the steady time of the unit state is more than 24 hours, the calculation method is that
When the condensate water is refined and put into operation, the boron concentration in the steam is lower than the detection limit, and the unit state stabilization time is more than 24 hours, the calculation method is as follows:
wherein V is the volume of the steam generator; ct is the boron concentration of the pollution discharge of the steam generator; fw is the feed water flow of a single steam generator; cw is the boron concentration of the steam generator feed water; fs is the flow rate of the steam generator; cs is the boron concentration of the steam generator steam; fl is the rate of primary-side to secondary-side leakage; cr is the boron concentration in the primary circuit; fb is the flow of the sewage discharged by the steam generator;
the precondition for determination in the step (1) is specifically: determining a loop temperature of 292 ℃ and a pressure of 15.4MPa; confirming that the liquid level of the steam generator is kept stable for more than or equal to 4 hours, confirming that the sewage discharge flow of the steam generator is regulated to the maximum, the flow keeping stable for more than or equal to 4 hours, confirming that the steam flow of the steam generator is kept stable for more than or equal to 4 hours, confirming that the boron concentration of a primary circuit is 500-1000 mg/L, and the boron concentration of the primary circuit is not changed in the test process.
2. The method for calculating the leak rate of a steam generator during a hot test of a nuclear power plant according to claim 1, wherein: the detection limit of the boron concentration in a first loop is less than or equal to 50mg/L when a sample is analyzed, and the analysis error is less than or equal to 5mg/L; the pollution discharge of the steam generator, the water supply of the steam generator and the detection limit of the steam sample analysis method of the steam generator are less than or equal to 1 mug/L, and the detection error is less than or equal to 1 mug/L.
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| CN114093536A (en) * | 2021-10-20 | 2022-02-25 | 中核核电运行管理有限公司 | Measuring method for monitoring leakage of steam generator of nuclear power plant |
| CN114171218A (en) * | 2021-11-23 | 2022-03-11 | 中核核电运行管理有限公司 | Condenser leakage detection system of nuclear power plant |
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