CN111305914A - Nuclear turbine high-pressure cylinder efficiency testing method based on energy balance - Google Patents
Nuclear turbine high-pressure cylinder efficiency testing method based on energy balance Download PDFInfo
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Abstract
The invention discloses a method for testing efficiency of a high-pressure cylinder of a nuclear turbine based on energy balance, which comprises the following steps: a. installing performance test points according to a performance test point arrangement scheme; b. checking the state of the unit and isolating the system before the test according to the test requirement; c. performing a performance test according to the test requirements; d. processing the extracted test data; e. and calculating the efficiency of the high-pressure cylinder of the steam turbine of the nuclear power unit according to the test data. The invention provides a method for testing the efficiency of a high-pressure cylinder of a nuclear power unit based on energy balance, which can be used for measuring the efficiency of the high-pressure cylinder of a steam turbine of the nuclear power unit by a performance test method at low cost.
Description
Technical Field
The invention belongs to the technical field of power generation of turbines of nuclear power units, and particularly relates to a method for testing efficiency of a high-pressure cylinder of a nuclear turbine based on energy balance.
Background
The steam turbine is a key device in the thermal power conversion process in a nuclear power station, the cylinder efficiency is one of the most important indexes for evaluating the body performance of the steam turbine, and the cylinder efficiency reflects the thermal power conversion capability of a working medium in the expansion process of the steam turbine. Therefore, accurate steam turbine cylinder efficiency test data are obtained, and the method is of great importance for diagnosing, monitoring and evaluating the performance of the steam turbine.
The high pressure cylinder efficiency calculation requires the use of the induction and exhaust enthalpies of the high pressure cylinder. Generally speaking, the steam inlet and the steam outlet of the high-pressure cylinder of the nuclear power unit are wet steam, the enthalpy value of the steam cannot be determined by directly measuring the pressure and the temperature of the wet steam, and therefore the enthalpy value needs to be calculated by measuring the pressure and the humidity. The conventional method for measuring the steam humidity in the nuclear power unit usually adopts a tracer method, the method needs to perform discontinuous and repeated sampling on a measuring pipeline for many times, and performs laboratory test analysis on the sample, the operation procedure is complex, instruments used for the test analysis are expensive, and the method is not suitable for the conventional diagnostic test of the unit. The measurement of the exhaust steam humidity of the high-pressure cylinder has not been a mature and reliable measurement method.
Disclosure of Invention
The invention aims to provide an energy balance-based efficiency testing method for a high-pressure cylinder of a nuclear power turbine, which comprises the steps of designing and arranging pressure, temperature and flow measurement measuring points in a turbine system of a nuclear power unit, installing a measuring instrument according to regulation requirements, testing thermal parameters of the turbine according to a preset scheme, calculating the exhaust enthalpy of the high-pressure cylinder by combining the energy balance relations of systems or equipment such as a high-pressure heater, a deaerator, a steam-water separation reheater, the high-pressure cylinder and the like, and calculating the main steam enthalpy by using humidity data of a latest main steam humidity measurement test, so that the efficiency of the high-pressure cylinder is obtained.
In order to achieve the purpose, the invention adopts the technical scheme that:
a method for testing efficiency of a high-pressure cylinder of a nuclear turbine based on energy balance comprises the following steps:
A. installing the performance test points according to the performance test point arrangement scheme
The main test points include: main steam pressure, high-pressure cylinder exhaust steam pressure, No. 7 high added water outlet temperature, No. 7 high added hydrophobic pressure, No. 7 high added hydrophobic temperature, No. 7 high added water inlet pressure, No. 7 high added water inlet temperature, primary reheater hydrophobic pressure, primary reheater hydrophobic temperature, secondary reheater hydrophobic temperature, steam-water separator hydrophobic pressure, primary reheater steam inlet temperature, primary reheater steam outlet pressure, primary reheater steam outlet temperature, No. 7 high added water outlet flow, No. 7 high added hydrophobic flow, primary reheater hydrophobic flow, secondary reheater hydrophobic flow and steam-water separator hydrophobic flow;
B. unit state inspection and system isolation are carried out before test according to test requirements
The method comprises the following steps of carrying out detailed inspection on the state of a nuclear power unit to ensure that the unit is in a normal commercial operation state before a test is started, the output power of a nuclear island is in a stable state and is more than 99% of rated power, each main device of the unit comprises a steam turbine, a steam-water separation reheater, a generator, a condenser and a regenerative heater is in a normal operation state, and each operation parameter of the unit is in a stable state; the leakage defects of pipelines and valves of a thermodynamic system of the unit are eliminated, and meanwhile, a test system is isolated from the outside, so that the unit operates in a unit mode;
C. performing performance tests according to test requirements
Before the test is started, the AGC and the primary frequency modulation control are quitted, and the stability of the load and the opening of the high-pressure regulating valve during the test is ensured; meanwhile, adjusting the unit operation parameters to enable the test working condition parameters to approach the design values; then keeping the unit operation parameters stable for more than 30 minutes, and performing a performance test; during the test, monitoring the fluctuation of the operation parameters in real time and adjusting in time to keep the parameter fluctuation within a set range; collecting and recording test data during a test period, and setting a sampling period to be less than or equal to 30 seconds; after continuously collecting data for at least 2 hours, finishing 1 test working condition, and extracting and storing the test data;
D. processing the extracted test data
Calculating the average value of the acquired data according to the effective time period of the test, then correcting the average value of the data according to the instrument check report, the zero position data of the pressure and differential pressure instrument and the water column potential difference in the pressure transmission pipe of the pressure instrument, and correcting the measured data of the relative pressure transmitter by considering the added atmospheric pressure to obtain the absolute pressure;
E. looking up a latest main steam humidity measurement test report, acquiring main steam humidity data and calculating main steam enthalpy;
F. and calculating the exhaust enthalpy of the high-pressure cylinder according to the test data and the flow balance and heat balance relationship among the high-pressure heating regenerator, the high-pressure cylinder and the steam-water separator, so as to obtain the efficiency of the high-pressure cylinder.
In the step C, the allowable deviation of the parameters of the test working condition and the design working condition and the allowable parameter fluctuation range during the test are shown in the table 1:
TABLE 1 parameter allowable Range
The invention is further improved in that in step F, the high-pressure cylinder efficiency calculation method is specifically as follows:
Fdw7＝Fis7+FdwL(1)
high heating balance No. 7:
Fis7×(his7-hdw7)＝Fow7×(how7-hiw7)-FdwL×(hdwL-hiw7) (2)
simultaneous equations (1) and (2) for calculating No. 7 high addition steam flow Fis7And the enthalpy of admission his7Enthalpy of admission his7Equal to the secondary reheater reheat steam enthalpy hrsK；
Main steam enthalpy equal to primary reheaterEnthalpy of hot steam hrsL：
hms＝(1-x)hms'+xmshms" (3)
Primary reheater thermal balancing:
FisLP×(hosL-hisL)＝FdwL×(hrsL-hdwL) (4)
simultaneous equations (3) and (4) for calculating low-pressure cylinder steam inlet flow FisLP；
Secondary reheater thermal balancing:
FisLP×(hosK-hisK)＝FdwK×(hrsK-hdwK) (5)
calculating the secondary reheater steam admission enthalpy h according to equation (5)isK；
Flow balance of the steam-water separator:
FisLP＝FdwJ+FexsHP(6)
steam-water separator heat balance:
FisLP×hisK＝FdwJ×hdwJ+FexsHP×hexsHP(7)
simultaneous equations (6) and (7) for calculating high-pressure cylinder exhaust flow FexsHPAnd the exhaust enthalpy h of the high-pressure cylinderis5；
High-pressure cylinder efficiency calculation formula:
in the formula:
Fis7-No. 7 high addition steam flow;
Fdw7-No. 7 high pressure hydrophobic flux;
Fow7-high No. 7 added water flow;
FdwL-primary reheater drain flow;
his7-No. 7 high admission enthalpy;
hdw7-high plus hydrophobic enthalpy No. 7;
how7-high feed water enthalpy No. 7;
hiw7-high feed water enthalpy No. 7;
hms-main steam enthalpy;
xms-main steam humidity;
hms' -saturated steam enthalpy;
hms"-saturated water enthalpy;
FisLP-low pressure cylinder inlet flow;
FexHP-high pressure cylinder exhaust flow;
FdwK-secondary reheater drainage flow;
FdwJ-steam trap drain flow;
hexsHP-high pressure cylinder exhaust enthalpy;
hrsL-primary reheater reheat steam enthalpy;
hisL-primary reheater steam admission enthalpy;
hosL-primary reheater exhaust enthalpy;
hrsK-secondary reheater reheat steam enthalpy;
hisK-secondary reheater steam admission enthalpy;
hosK-secondary reheater exhaust enthalpy;
h’exsHP-isentropic enthalpy of high pressure cylinder exhaust;
hisLP-low pressure cylinder inlet enthalpy;
hdwL-primary reheater drainage enthalpy;
hdwK-secondary reheater drainage enthalpy;
hdwJ-trap hydrophobic enthalpy.
The invention has the following advantages:
1. according to the invention, only temperature, pressure and flow measuring instruments are required to be installed to measure the efficiency of the high-pressure cylinder of the steam turbine of the nuclear power unit, and the steam humidity is not measured by using a tracer method which is complex in operation and high in cost.
Drawings
FIG. 1 is a schematic flow chart of the present invention.
FIG. 2 is a typical EPR nuclear power unit turbine high pressure cylinder efficiency test point installation layout.
Detailed Description
The invention further provides a method for testing the efficiency of a high-pressure cylinder of a nuclear turbine based on energy balance, which is disclosed by the invention, by combining the attached drawings and an example.
As shown in FIG. 1 and FIG. 2, the method for testing the efficiency of the high-pressure cylinder of the nuclear turbine based on energy balance provided by the invention comprises the following steps.
A. And installing the performance test points according to the performance test point arrangement scheme. The main test points include: main steam pressure, high-pressure cylinder exhaust steam pressure, No. 7 high pressure added water outlet pressure, No. 7 high temperature added water outlet, No. 7 high pressure added hydrophobic pressure, No. 7 high hydrophobic temperature, No. 7 high pressure added water inlet, No. 7 high temperature added water inlet, primary reheater hydrophobic pressure, primary reheater hydrophobic temperature, secondary reheater hydrophobic pressure, primary reheater steam inlet temperature, primary reheater steam outlet pressure, primary reheater steam outlet temperature, No. 7 high added water outlet flow, No. 7 high hydrophobic flow, primary reheater hydrophobic flow, secondary reheater hydrophobic flow, steam-water separator hydrophobic flow and the like.
B. And performing unit state check and system isolation before the test according to the test requirements. The state of the nuclear power unit is checked in detail, the unit is in a normal commercial operation state before the test is started, the output power of a nuclear island is in a stable state and is more than 99% of rated power, main equipment of the unit, including a steam turbine, a steam-water separation reheater, a generator, a condenser, a regenerative heater and the like, is in a normal operation state, and main operation parameters of the unit are in a stable state. The leakage defects of pipelines and valves of a thermodynamic system of the unit are eliminated, and meanwhile, a test system is isolated from the outside, so that the unit operates in a unit mode.
C. Performance tests were performed according to the test requirements. Before the test is started, the AGC and the primary frequency modulation control are quitted, and the stability of the load and the opening of the high-pressure regulating valve during the test is ensured. And meanwhile, adjusting the unit operation parameters to enable the test working condition parameters to be close to the design values. And then keeping the operation parameters of the unit stable for more than 30 minutes, and carrying out a performance test. During the test, the fluctuation of the operation parameters is monitored in real time and adjusted in time to keep the parameter fluctuation within a certain range. And acquiring and recording test data during the test period, and setting the sampling period to be less than or equal to 30 seconds. And (3) finishing 1 test working condition after continuously collecting data for at least 2 hours, and extracting and storing the test data.
The allowable deviation of the parameters of the test condition and the design condition and the allowable parameter fluctuation range during the test are shown in table 1.
TABLE 1 parameter allowable Range
D. And processing the extracted test data. And calculating the average value of the collected data according to the effective time period of the test. And then correcting the average value of the data according to the instrument check report, the zero position data of the pressure and differential pressure instrument and the water column potential difference in a pressure transmission pipe of the pressure instrument, and taking the atmospheric pressure correction into consideration relative to the measurement data of the pressure transmitter so as to obtain the absolute pressure.
E. And looking up a latest main steam humidity measurement test report, acquiring main steam humidity data and calculating main steam enthalpy.
F. And calculating the exhaust enthalpy of the high-pressure cylinder according to the test data and the flow balance and heat balance relationship among the high-pressure heating regenerator, the high-pressure cylinder and the steam-water separator, so as to obtain the efficiency of the high-pressure cylinder.
In step F, the method for calculating the high-pressure cylinder efficiency is specifically as follows:
Fdw7＝Fis7+FdwL(1)
high heating balance No. 7:
Fis7×(his7-hdw7)＝Fow7×(how7-hiw7)-FdwL×(hdwL-hiw7) (2)
simultaneous equations (1) and (2) for calculating No. 7 high addition steam flow Fis7And the enthalpy of admission his7(equal to secondary reheater reheat steam enthalpy hrsK)。
Main steam enthalpy (equal to primary reheater reheat steam enthalpy hrsL)：
hms＝(1-x)hms'+xmshms" (3)
Primary reheater thermal balancing:
FisLP×(hosL-hisL)＝FdwL×(hrsL-hdwL) (4)
simultaneous equations (3) and (4) for calculating low-pressure cylinder steam inlet flow FisLP。
Secondary reheater thermal balancing:
FisLP×(hosK-hisK)＝FdwK×(hrsK-hdwK) (5)
calculating the secondary reheater steam admission enthalpy h according to equation (5)isK。
Flow balance of the steam-water separator:
FisLP＝FdwJ+FexsHP(6)
steam-water separator heat balance:
FisLP×hisK＝FdwJ×hdwJ+FexsHP×hexsHP(7)
simultaneous equations (6) and (7) for calculating high-pressure cylinder exhaust flow FexsHPAnd the exhaust enthalpy h of the high-pressure cylinderis5。
High-pressure cylinder efficiency calculation formula:
in the formula:
Fis7-No. 7 high addition steam flow;
Fdw7-No. 7 high pressure hydrophobic flux;
Fow7-high No. 7 added water flow;
FdwL-primary reheater drain flow;
his7-No. 7 high admission enthalpy;
hdw7-high plus hydrophobic enthalpy No. 7;
how7-high feed water enthalpy No. 7;
hiw7-high feed water enthalpy No. 7;
hms-main steam enthalpy;
xms-main steam humidity;
hms' -saturated steam enthalpy;
hms"-saturated water enthalpy;
FisLP-low pressure cylinder inlet flow;
FexHP-high pressure cylinder exhaust flow;
FdwK-secondary reheater drainage flow;
FdwJ-steam trap drain flow;
hexsHP-high pressure cylinder exhaust enthalpy;
hrsL-primary reheater reheat steam enthalpy;
hisL-primary reheater steam admission enthalpy;
hosL-primary reheater exhaust enthalpy;
hrsK-secondary reheater reheat steam enthalpy;
hisK-secondary reheater steam admission enthalpy;
hosK-secondary reheater exhaust enthalpy;
h’exsHP-isentropic enthalpy of high pressure cylinder exhaust;
hisLP-low pressure cylinder inlet enthalpy;
hdwL-first reheater drainage enthalpy；
hdwK-secondary reheater drainage enthalpy;
hdwJ-trap hydrophobic enthalpy.
Claims (3)
1. A method for testing efficiency of a high-pressure cylinder of a nuclear turbine based on energy balance is characterized by comprising the following steps:
A. installing the performance test points according to the performance test point arrangement scheme
The main test points include: main steam pressure, high-pressure cylinder exhaust steam pressure, No. 7 high added water outlet temperature, No. 7 high added hydrophobic pressure, No. 7 high added hydrophobic temperature, No. 7 high added water inlet pressure, No. 7 high added water inlet temperature, primary reheater hydrophobic pressure, primary reheater hydrophobic temperature, secondary reheater hydrophobic temperature, steam-water separator hydrophobic pressure, primary reheater steam inlet temperature, primary reheater steam outlet pressure, primary reheater steam outlet temperature, No. 7 high added water outlet flow, No. 7 high added hydrophobic flow, primary reheater hydrophobic flow, secondary reheater hydrophobic flow and steam-water separator hydrophobic flow;
B. unit state inspection and system isolation are carried out before test according to test requirements
The method comprises the following steps of carrying out detailed inspection on the state of a nuclear power unit to ensure that the unit is in a normal commercial operation state before a test is started, the output power of a nuclear island is in a stable state and is more than 99% of rated power, each main device of the unit comprises a steam turbine, a steam-water separation reheater, a generator, a condenser and a regenerative heater is in a normal operation state, and each operation parameter of the unit is in a stable state; the leakage defects of pipelines and valves of a thermodynamic system of the unit are eliminated, and meanwhile, a test system is isolated from the outside, so that the unit operates in a unit mode;
performing performance tests according to test requirements
Before the test is started, the AGC and the primary frequency modulation control are quitted, and the stability of the load and the opening of the high-pressure regulating valve during the test is ensured; meanwhile, adjusting the unit operation parameters to enable the test working condition parameters to approach the design values; then keeping the unit operation parameters stable for more than 30 minutes, and performing a performance test; during the test, monitoring the fluctuation of the operation parameters in real time and adjusting in time to keep the parameter fluctuation within a set range; collecting and recording test data during a test period, and setting a sampling period to be less than or equal to 30 seconds; after continuously collecting data for at least 2 hours, finishing 1 test working condition, and extracting and storing the test data;
D. processing the extracted test data
Calculating the average value of the acquired data according to the effective time period of the test, then correcting the average value of the data according to the instrument check report, the zero position data of the pressure and differential pressure instrument and the water column potential difference in the pressure transmission pipe of the pressure instrument, and correcting the measured data of the relative pressure transmitter by considering the added atmospheric pressure to obtain the absolute pressure;
E. looking up a latest main steam humidity measurement test report, acquiring main steam humidity data and calculating main steam enthalpy;
F. and calculating the exhaust enthalpy of the high-pressure cylinder according to the test data and the flow balance and heat balance relationship among the high-pressure heating regenerator, the high-pressure cylinder and the steam-water separator, so as to obtain the efficiency of the high-pressure cylinder.
2. The method for testing the efficiency of the high-pressure cylinder of the nuclear turbine based on the energy balance as claimed in claim 1, wherein in the step C, the allowable deviation of the parameters of the test working condition and the design working condition and the allowable parameter fluctuation range during the test are shown in Table 1:
TABLE 1 parameter allowable Range
3. The method for testing the efficiency of the high-pressure cylinder of the nuclear turbine based on the energy balance as claimed in claim 1, wherein in the step F, the method for calculating the efficiency of the high-pressure cylinder is as follows:
number 7 high pressure flow balance:
Fdw7＝Fis7+FdwL(1)
high heating balance No. 7:
Fis7×(his7-hdw7)＝Fow7×(how7-hiw7)-FdwL×(hdwL-hiw7) (2)
simultaneous equations (1) and (2) for calculating No. 7 high addition steam flow Fis7And the enthalpy of admission his7Enthalpy of admission his7Equal to the secondary reheater reheat steam enthalpy hrsK；
The main steam enthalpy is equal to the primary reheater reheat steam enthalpy hrsL：
hms＝(1-x)hms'+xmshms" (3)
Primary reheater thermal balancing:
FisLP×(hosL-hisL)＝FdwL×(hrsL-hdwL) (4)
simultaneous equations (3) and (4) for calculating low-pressure cylinder steam inlet flow FisLP；
Secondary reheater thermal balancing:
FisLP×(hosK-hisK)＝FdwK×(hrsK-hdwK) (5)
calculating the secondary reheater steam admission enthalpy h according to equation (5)isK；
Flow balance of the steam-water separator:
FisLP＝FdwJ+FexsHP(6)
steam-water separator heat balance:
FisLP×hisK＝FdwJ×hdwJ+FexsHP×hexsHP(7)
simultaneous equations (6) and (7) for calculating high-pressure cylinder exhaust flow FexsHPAnd the exhaust enthalpy h of the high-pressure cylinderis5；
High-pressure cylinder efficiency calculation formula:
in the formula:
Fis7-No. 7 high addition steam flow;
Fdw7-No. 7 high pressure hydrophobic flux;
Fow7-high No. 7 added water flow;
FdwL-primary reheater drain flow;
his7-No. 7 high admission enthalpy;
hdw7-high plus hydrophobic enthalpy No. 7;
how7-high feed water enthalpy No. 7;
hiw7-high feed water enthalpy No. 7;
hms-main steam enthalpy;
xms-main steam humidity;
hms' -saturated steam enthalpy;
hms"-saturated water enthalpy;
FisLP-low pressure cylinder inlet flow;
FexHP-high pressure cylinder exhaust flow;
FdwK-secondary reheater drainage flow;
FdwJ-steam trap drain flow;
hexsHP-high pressure cylinder exhaust enthalpy;
hrsL-primary reheater reheat steam enthalpy;
hisL-primary reheater steam admission enthalpy;
hosL-primary reheater exhaust enthalpy;
hrsK-secondary reheater reheat steam enthalpy;
hisK-secondary reheater steam admission enthalpy;
hosK——secondary reheater exhaust enthalpy;
h’exsHP-isentropic enthalpy of high pressure cylinder exhaust;
hisLP-low pressure cylinder inlet enthalpy;
hdwL-primary reheater drainage enthalpy;
hdwK-secondary reheater drainage enthalpy;
hdwJ-trap hydrophobic enthalpy.
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| CN112127958A (en) * | 2020-08-28 | 2020-12-25 | 中核核电运行管理有限公司 | Device and method for determining steam extraction parameters of nuclear turbine |
| CN114087033A (en) * | 2021-11-16 | 2022-02-25 | 西安热工研究院有限公司 | System and method for measuring exhaust enthalpy of low-pressure cylinder of power station steam turbine |
| CN114942144A (en) * | 2022-05-19 | 2022-08-26 | 苏州西热节能环保技术有限公司 | Method for measuring and calculating efficiency of single steam turbine cylinder of garbage power station based on main pipe system |
| CN115312224A (en) * | 2022-06-20 | 2022-11-08 | 福建福清核电有限公司 | Method for judging rated heat output test of nuclear power unit |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN115312224A (en) * | 2022-06-20 | 2022-11-08 | 福建福清核电有限公司 | Method for judging rated heat output test of nuclear power unit |
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