Universal nuclear energy steam supply system performance test method

Abstract

The invention particularly relates to a universal nuclear energy steam supply system performance test method, which comprises the following steps: determining the boundary of a nuclear energy steam supply system, and arranging performance test points of a nuclear power unit and the nuclear energy steam supply system; determining the power generation power of the nuclear power unit under the TMCR working condition; based on the power generation power of the nuclear power unit under the TMCR working condition, performing a performance test on the nuclear energy steam supply system under the design working condition, and correcting the external supply steam flow of the nuclear energy steam supply system under the design working condition test to the design working condition; and correcting the generated power of the nuclear power unit under the TMCR working condition, and calculating a nuclear energy steam supply system test result. According to the method, the operation state of the nuclear energy steam supply system is objectively and truly reflected, and reliable support is provided for design verification, performance assessment and subsequent optimization design of the steam supply system.

Description

Technical Field

[0001] The invention relates to the technical field of nuclear energy steam supply debugging, and in particular to a universal nuclear energy steam supply system performance test method. Background Art

[0002] Nuclear steam supply is a process that uses the secondary circuit saturated steam generated by the reactor as a heat source to gradually heat the working medium water from room temperature liquid to superheated steam and transport it to users over long distances. With the clean and low-carbon transformation of the national energy system and the shortage and price increase of traditional fossil energy such as natural gas, the demand for nuclear steam supply by high-energy-consuming enterprises such as petrochemicals will become more prominent. Nuclear steam supply is developing rapidly and has a very broad space for development.

[0003] The nuclear energy steam supply system uses saturated steam heat source to prepare superheated steam, and its thermal system and equipment structure are relatively complex. The traditional thermal power steam supply system uses a two-circuit steam direct supply, and the steam quality parameters and system efficiency changes can be obtained only through the thermal performance test of the steam turbine. However, for the nuclear energy steam supply system, the phase change of the working fluid on both the cold and hot sides of the evaporator and superheater equipment occurs simultaneously, and there are many spare circuits and operating conditions. It is impossible to evaluate the performance only by the thermal performance test of the steam turbine. The steam supply system performance test must be carried out at the same time to evaluate the performance indicators of the system after it is put into operation in detail, objectively and truly reflect the operating status, and provide reliable support for the design verification, performance assessment and subsequent optimization design of the steam supply system. Summary of the invention

[0004] The purpose of the present invention is to provide a universal nuclear energy steam supply system performance test method, which objectively and truly reflects the operating status of the nuclear energy steam supply system and provides reliable support for the design verification, performance assessment and subsequent optimization design of the steam supply system.

[0005] In order to achieve the above object, the present invention provides the following technical solutions:

[0006] A general nuclear energy steam supply system performance test method comprises the following steps:

[0007] Step 101, determine the boundary of the nuclear energy steam supply system, and arrange the performance test measurement points of the nuclear power unit and the nuclear energy steam supply system;

[0008] Step 102: Perform a performance test on the nuclear power unit under the TMCR operating condition to obtain the power generation of the nuclear power unit under the TMCR operating condition;

[0009] Step 103: Based on the power generation of the nuclear power unit under the TMCR condition, a performance test is performed on the nuclear energy steam supply system under the design condition to obtain the external steam supply flow rate under the design condition test of the nuclear energy steam supply system; and the external steam supply flow rate under the design condition test of the nuclear energy steam supply system is corrected to the design condition;

[0010] Step 104: According to the operating parameters of the nuclear power unit during the test of the nuclear energy steam supply system, the power generation of the nuclear power unit under the TMCR condition is corrected, and the test results of the nuclear energy steam supply system are calculated.

[0011] As one of the feasible ways, in step 101, the nuclear power unit includes a secondary circuit working fluid pump, a heater, a secondary circuit evaporator, a steam turbine, a condenser and a generator. The secondary circuit working fluid pump, the heater, the secondary circuit evaporator, the steam turbine and the condenser are connected in sequence to form a closed loop passage for the circulation of the secondary circuit working fluid. The steam turbine is connected to the generator, and the generator converts the mechanical energy of the steam turbine into electrical energy. The performance test measuring points of the nuclear power unit are arranged as follows: temperature measuring points, pressure measuring points and flow measuring points are arranged at the inlet of the working fluid side of the secondary circuit evaporator, temperature measuring points and pressure measuring points are arranged at the outlet of the working fluid side of the secondary circuit evaporator, pressure measuring points are arranged at the inlet of the steam turbine, pressure measuring points are arranged in the condenser, and electric power measuring points are arranged on the generator.

[0012] As one of the feasible ways, in step 101, the nuclear energy steam supply system includes a feedwater pump, a preheater, an evaporator and a superheater; the feedwater pump, the working fluid side of the preheater, the working fluid side of the evaporator and the working fluid side of the superheater are connected in sequence to form the working fluid side of the nuclear energy steam supply system; the heat source side of the preheater, the heat source side of the evaporator and the heat source side of the superheater are connected in sequence to form the heat source side of the nuclear energy steam supply system; the performance test measuring points of the nuclear energy steam supply system are arranged as follows: temperature measuring points, pressure measuring points and flow measuring points are arranged at the inlet and outlet of the working fluid side of the nuclear energy steam supply system, pressure measuring points and flow measuring points are arranged at the inlet of the heat source side of the nuclear energy steam supply system, and pressure measuring points, flow measuring points and temperature measuring points are arranged at the outlet of the heat source side of the nuclear energy steam supply system.

[0013] As one of the achievable methods, step 102, performing a performance test on a nuclear power unit under TMCR conditions to obtain the power generation of the nuclear power unit under TMCR conditions, includes the following steps:

[0014] Set the nuclear power unit status according to the turbine performance test requirements and ensure that the turbine operating parameters meet the stability requirements;

[0015] The power generation of nuclear power units under TMCR conditions is measured. During the performance test of the nuclear energy steam supply system, the nuclear power units are operated according to TMCR conditions.

[0016] As one of the achievable methods, in step 103, the design operating conditions of the nuclear energy steam supply system include: heating of a single nuclear power unit or joint heating of multiple nuclear power units, the nuclear energy steam supply system has a single set of evaporators or multiple sets of evaporators, among which one set of evaporators is a main evaporator and the other evaporators are standby evaporators;

[0017] During the performance test of the nuclear energy steam supply system under the design conditions, the nuclear power units are operated according to the TMCR conditions. Under the condition of joint heating of multiple nuclear power units, each nuclear power unit provides heat separately, and under the condition of stable heating load, multiple nuclear power units jointly provide heat. Under the condition of a single evaporator, a single evaporator operates at full load; under the condition of multiple evaporators, each evaporator operates at full load at least once.

[0018] As one achievable method, in step 103, the external steam supply flow rate under the design operating condition test of the nuclear energy steam supply system is corrected to the design operating condition according to the following formula:

[0019]

[0020] Among them, F wgX F is the external steam flow rate under the design conditions of the nuclear energy steam supply system, in kg / h; wg It is the external steam flow rate under the design condition test of nuclear energy steam supply system, in kg / h;

[0021] H wg It is the enthalpy of external steam at the design working condition test pressure and temperature of the nuclear energy steam supply system, in kJ / kg; H wg ′ is the enthalpy of external steam at the design operating pressure and temperature of the nuclear energy steam supply system, in kJ / kg;

[0022] H gs It is the feed water enthalpy value at the design operating pressure and operating temperature of the nuclear power steam supply system, in kJ / kg, H gs ′ is the feed water enthalpy at the design operating pressure and temperature of the nuclear energy steam supply system, in kJ / kg.

[0023] As one of the achievable methods, in step 104, the operating parameters of the nuclear power unit include main steam pressure, main steam humidity, turbine exhaust pressure, reactor thermal power and generator power factor; the power generation of the nuclear power unit under TMCR condition is corrected according to the following formula:

[0024]

[0025] Among them, P θ is the corrected power generation of the nuclear power unit under TMCR conditions, in kW; P net It is the power generation of the nuclear power unit under heating conditions, in kW;

[0026] θ pms is the main steam pressure correction factor, θ xms is the main steam humidity correction factor, θ pds is the steam turbine exhaust pressure correction factor, θ QNTis the reactor thermal power correction factor, θ PF is the generator power factor correction coefficient.

[0027] As one achievable method, in step 104, the test results of the nuclear energy steam supply system include the steam supply efficiency of the nuclear energy steam supply system, the heating efficiency of the nuclear power unit and the power impact value of the nuclear energy steam supply system.

[0028] As one of the feasible methods, the steam supply efficiency of the nuclear power steam supply system is calculated according to the following formula:

[0029]

[0030] Among them, η gq is the steam supply efficiency of nuclear energy steam supply system; F wg It is the external steam flow rate under the design condition test of nuclear energy steam supply system, in kg / h; H wg H is the enthalpy of external steam at the design operating test pressure and temperature, in kJ / kg; gs The feed water enthalpy value at the design test pressure and temperature of the nuclear steam supply system, in kJ / kg; P θ is the corrected power generation of the nuclear power unit under TMCR, in kW; P θ ' is the corrected power generation of the nuclear power unit under heating conditions, in kW.

[0031] As one of the feasible methods, the heating efficiency of nuclear power units is calculated according to the following formula:

[0032]

[0033] in, is the heating efficiency of nuclear power units; F wg It is the external steam flow rate under the design condition test of nuclear energy steam supply system, in kg / h; H wg H is the enthalpy of external steam at the design operating test pressure and temperature, in kJ / kg; gs Q is the feed water enthalpy value at the design test pressure and temperature of the nuclear power steam supply system, in kJ / kg; N P is the thermal power of the nuclear island under the heating condition of the nuclear power unit, in kW; θ ' is the corrected power generation of the nuclear power unit under heating conditions, in kW.

[0034] As one of the feasible methods, the power impact value of the nuclear energy steam supply system is calculated according to the following formula:

[0035]

[0036] Among them, ΔP is the power impact value of the nuclear energy steam supply system; Pθ ' is the power generation of the nuclear power unit under heating conditions, in kW; P θ is the corrected power generation of the nuclear power unit under TMCR conditions, in kW; F wgX F is the external steam flow rate under the design conditions of the nuclear energy steam supply system, in kg / h; wg It is the external steam supply flow rate under the design operating condition test of the nuclear energy steam supply system, in kg / h.

[0037] As one of the feasible ways, the general nuclear energy steam supply system performance test method also includes: step 105, performing uncertainty analysis on the test results of the nuclear energy steam supply system to ensure that the external steam supply flow rate under the design operating condition test of the nuclear energy steam supply system meets the design indicators and the test results of the nuclear energy steam supply system reach the guaranteed value.

[0038] As one of the feasible ways, uncertainty analysis is performed on the test results of the nuclear energy steam supply system according to the uncertainty of the parameters and variables of the nuclear energy steam supply system test, including the following steps:

[0039] Determine the uncertainty of each parameter, the uncertainty of each parameter comes from instrument uncertainty, time uncertainty and spatial uncertainty;

[0040] Determine the uncertainty of each variable. The uncertainty of each variable comes from the uncertainty of each parameter involved in the calculation of the variable and the influence of each parameter involved in the calculation of the variable on the variable.

[0041] Determine the uncertainty of each parameter and each variable on the test results. The uncertainty of the variable on the test results = the uncertainty of the variable × the influence coefficient of the variable on the test results; the uncertainty of the parameter on the test results = the uncertainty of the parameter × the influence coefficient of the parameter on the test results;

[0042] Determine the uncertainty of the test results based on the uncertainty of each parameter and each variable to the test results.

[0043] Beneficial technical effects of the present invention:

[0044] The universal nuclear energy steam supply system performance test method of the present invention reasonably arranges relevant performance test measurement points in the nuclear power unit and the nuclear energy steam supply system, measures and calculates the steam supply efficiency of the nuclear energy steam supply system, the heating efficiency of the nuclear power unit and the power impact value of the nuclear energy steam supply system, can effectively evaluate the economy of the nuclear energy steam supply system, and objectively reflect the economy level of the operation of the nuclear energy steam supply system.

[0045] The universal nuclear energy steam supply system performance test method of the present invention accurately corrects the power influence value of the nuclear energy steam supply system based on the power generation power of the nuclear power unit under the TMCR working condition, the corrected power generation power of the nuclear power unit under the heating working condition and the external steam flow under the design working condition of the nuclear energy steam supply system. It has strong engineering operability and does not require the overall correction of the nuclear energy steam supply system. It simplifies the mutual interference of various equipment during operation during the nuclear energy steam supply system test and improves the accuracy of the test results of the nuclear energy steam supply system.

[0046] The universal nuclear energy steam supply system performance test method of the present invention, as a supplement to the nuclear energy steam supply system performance test standard, makes the nuclear energy steam supply system performance test run more fairly and accurately, measures and calculates the steam supply efficiency of the nuclear energy steam supply system, the heating efficiency of the nuclear power unit and the power impact value of the nuclear energy steam supply system in real time, effectively evaluates the design perfection of the nuclear energy steam supply system, and realizes an objective evaluation of its energy utilization degree. BRIEF DESCRIPTION OF THE DRAWINGS

[0047] Figure 1 It is a structural schematic diagram of an embodiment of a universal nuclear energy steam supply system of the present invention;

[0048] Figure 2 The present invention is a flowchart of an embodiment of a universal nuclear energy steam supply system performance test method.

[0049] In the figure, 1. feed water pump 1; 2. preheater; 3. evaporator; 4. superheater; 5. condenser; 6. secondary circuit working fluid pump; 7. heater; 8. secondary circuit evaporator; 9. turbine; 10. generator. DETAILED DESCRIPTION

[0050] Unless otherwise defined, all technical and scientific terms used herein have the same meaning as commonly understood by technicians in the technical field to which this application belongs; the terms used in the specification of the application are only for the purpose of describing specific embodiments and are not intended to limit this application; the terms "including" and "having" and any variations thereof in the specification and claims of this application and the above-mentioned figure descriptions are intended to cover non-exclusive inclusions.

[0051] Reference to "embodiments" herein means that a particular feature, structure, or characteristic described in conjunction with the embodiments may be included in at least one embodiment of the present application. The appearance of the phrase in various locations in the specification does not necessarily refer to the same embodiment, nor is it an independent or alternative embodiment that is mutually exclusive with other embodiments. It is explicitly and implicitly understood by those skilled in the art that the embodiments described herein may be combined with other embodiments.

[0052] The technical solution of the present invention is clearly and completely described below in conjunction with the accompanying drawings and specific embodiments.

[0053] See also Figure 2 This embodiment provides a general nuclear energy steam supply system performance test method, comprising the following steps:

[0054] Step 101, determine the boundary of the nuclear energy steam supply system, and arrange the performance test measurement points of the nuclear power unit and the nuclear energy steam supply system;

[0055] Step 102: Perform a performance test on the nuclear power unit under the TMCR operating condition to obtain the power generation of the nuclear power unit under the TMCR operating condition;

[0056] Step 103: Based on the power generation of the nuclear power unit under the TMCR condition, a performance test is performed on the nuclear energy steam supply system under the design condition to obtain the external steam supply flow rate under the design condition test of the nuclear energy steam supply system; and the external steam supply flow rate under the design condition test of the nuclear energy steam supply system is corrected to the design condition;

[0057] Step 104: According to the operating parameters of the nuclear power unit during the test of the nuclear energy steam supply system, the power generation of the nuclear power unit under the TMCR condition is corrected, and the test results of the nuclear energy steam supply system are calculated.

[0058] In order to highlight the nuclear energy steam supply system, the nuclear power unit is simplified. Figure 1 In this embodiment, as one of the achievable methods, in step 101, the nuclear power unit includes a secondary circuit working fluid pump 6, a heater 7, a secondary circuit evaporator 8, a steam turbine 9, a condenser 5 and a generator 10. The secondary circuit working fluid pump 6, the heater 7, the secondary circuit evaporator 8, the steam turbine 9 and the condenser 5 are sequentially connected to form a closed loop passage for the circulation of the secondary circuit working fluid. The steam turbine 9 is connected to the generator 10, and the generator 10 converts the mechanical energy of the steam turbine 9 into electrical energy.

[0059] During the operation of the nuclear power unit, the secondary circuit working medium water passes through the condenser 5, the secondary circuit working medium pump 6 and the heater 7 in sequence and then enters the secondary circuit evaporator 8. The secondary circuit evaporator 8 generates saturated steam and enters the steam turbine 9. The steam turbine 9 converts the saturated steam into mechanical energy, and the generator 10 converts the mechanical energy into electrical energy.

[0060] The measurement points for the performance test of nuclear power units are arranged as follows: temperature measuring points, pressure measuring points and flow measuring points are arranged at the working fluid side inlet of the secondary circuit evaporator, temperature measuring points and pressure measuring points are arranged at the working fluid side outlet of the secondary circuit evaporator, pressure measuring points are arranged at the turbine inlet, pressure measuring points are arranged in the condenser, and electric power measuring points are arranged on the generator.

[0061] See also Figure 1In this embodiment, as one of the achievable ways, in step 101, the nuclear energy steam supply system includes a feedwater pump 1, a preheater 2, an evaporator 3 and a superheater 4, the feedwater pump 1, the working fluid side of the preheater 2, the working fluid side of the evaporator 3 and the working fluid side of the superheater 4 are sequentially connected to form the working fluid side of the nuclear energy steam supply system, and the heat source side of the preheater 2, the heat source side of the evaporator 3 and the heat source side of the superheater 4 are sequentially connected to form the heat source side of the nuclear energy steam supply system;

[0062] During the operation of the nuclear energy steam supply system, the saturated steam generated by the secondary circuit evaporator 8 is extracted into the heat source side of the nuclear energy steam supply system, and the working medium on the working medium side of the nuclear energy steam supply system is heated through the inter-wall heat exchange to form condensed water which enters the condenser 5; the working medium on the working medium side of the nuclear energy steam supply system is gradually heated to superheated steam through the preheater 2, the evaporator 3 and the superheater 4 in sequence, and is transported to the user as external supply steam;

[0063] The measurement points for the performance test of the nuclear energy steam supply system are arranged as follows: temperature measuring points, pressure measuring points and flow measuring points are arranged at the inlet and outlet of the working medium side of the nuclear energy steam supply system, pressure measuring points and flow measuring points are arranged at the inlet of the heat source side of the nuclear energy steam supply system, and pressure measuring points, flow measuring points and temperature measuring points are arranged at the outlet of the heat source side of the nuclear energy steam supply system.

[0064] In this embodiment, as one of the feasible ways, if the nuclear energy steam supply system has a heat recovery pipeline, a pressure measuring point, a flow measuring point and a temperature measuring point are set for the heat recovery pipeline.

[0065] In this embodiment, as one of the achievable methods, step 102, performing a performance test on the nuclear power unit under the TMCR condition to obtain the power generation of the nuclear power unit under the TMCR condition, includes the following steps:

[0066] Set the nuclear power unit status according to the turbine performance test requirements and ensure that the turbine operating parameters meet the stability requirements;

[0067] The power generation of nuclear power units under TMCR conditions is measured. During the performance test of the nuclear energy steam supply system, the nuclear power units are operated according to TMCR conditions.

[0068] In this embodiment, as one of the achievable methods, the steam turbine operating parameters include main steam pressure, main steam humidity, reheat steam temperature, exhaust pressure, extraction pressure, extraction flow, electric power, voltage and power factor;

[0069] The requirements for the steam turbine performance test are as follows: During the steam turbine performance test, the allowable deviation of the main steam pressure is ±3.0%, the allowable fluctuation of the main steam pressure is ±0.25%, the allowable deviation of the main steam humidity is ±0.5%, the allowable fluctuation of the main steam humidity is ±0.1%, the allowable deviation of the reheat steam temperature is ±15°C, the allowable fluctuation of the reheat steam temperature is ±4°C, the allowable fluctuation of the exhaust pressure is 0.14kPa, the allowable deviation of the extraction gas pressure is ±5kPa, the allowable deviation of the extraction flow rate is ±5kg / s, the allowable fluctuation of the electric power is ±0.25MW, the allowable deviation of the voltage is ±5.0kV, and the allowable fluctuation of the power factor is 1.0%.

[0070] In this embodiment, as one of the achievable methods, in step 103, the design operating conditions of the nuclear energy steam supply system include: heating of a single nuclear power unit or joint heating of multiple nuclear power units, the nuclear energy steam supply system has a single set of evaporators 3 or multiple sets of evaporators 3, among the multiple sets of evaporators 3, one set of evaporators 3 is a main evaporator, and the remaining evaporators 3 are standby evaporators;

[0071] During the performance test of the nuclear energy steam supply system under the design conditions, the nuclear power unit operates according to the TMCR conditions, and part of the saturated steam generated by the secondary circuit evaporator 8 is used for power generation, and the remaining part is extracted into the heat source side of the nuclear energy steam supply system, and after heating the working fluid on the working fluid side of the nuclear energy steam supply system, condensate is formed and enters the condenser 5 to realize the heating of the nuclear energy steam supply system; the working fluid on the working fluid side of the nuclear energy steam supply system is heated by the heat source on the heat source side of the nuclear energy steam supply system to form external steam supply; under the condition of joint heating of multiple nuclear power units, each nuclear power unit supplies heat separately, and under the condition of stable heating load, multiple nuclear power units jointly supply heat; under the condition of a single set of evaporator 3, the single set of evaporator 3 operates at full load; under the condition of multiple sets of evaporators 3, each set of evaporator 3 operates at full load at least once.

[0072] refer to Figure 1 During the performance test of the nuclear energy steam supply system, the nuclear power unit operates according to the TMCR operating conditions, and the secondary circuit working medium water passes through the condenser 5, the secondary circuit working medium pump 6 and the heater 7 in sequence and then enters the secondary circuit evaporator 8; the secondary circuit evaporator 8 produces saturated steam, part of which enters the steam turbine 9, and the other part enters the heat source of the nuclear energy steam supply system; the steam turbine 9 converts the saturated steam into mechanical energy, and the generator 10 converts the mechanical energy into electrical energy; the saturated steam on the heat source side of the nuclear energy steam supply system is cooled step by step through the preheater 2, the evaporator 3 and the superheater 4 to condensed water and enters the condenser; the working medium on the working medium side of the nuclear energy steam supply system is heated step by step through the preheater 2, the evaporator 3 and the superheater 4 to superheated steam, and is transported to the user as external steam.

[0073] In this embodiment, as one of the achievable methods, in step 103, the external steam supply flow rate under the design operating condition test of the nuclear energy steam supply system is corrected to the design operating condition according to the following formula:

[0074]

[0075] Among them, F wgX F is the external steam flow rate under the design conditions of the nuclear energy steam supply system, in kg / h; wg It is the external steam flow rate under the design condition test of nuclear energy steam supply system, in kg / h;

[0076] H wg It is the enthalpy of external steam at the design working condition test pressure and temperature of the nuclear energy steam supply system, in kJ / kg; H wg ′ is the enthalpy of external steam at the design operating pressure and temperature of the nuclear energy steam supply system, in kJ / kg;

[0077] H gs It is the feed water enthalpy value at the design operating pressure and operating temperature of the nuclear power steam supply system, in kJ / kg, H gs ′ is the feed water enthalpy at the design operating pressure and temperature of the nuclear energy steam supply system, in kJ / kg.

[0078] In this embodiment, as one of the achievable methods, in step 104, the operating parameters of the nuclear power unit include main steam pressure, main steam humidity, turbine exhaust pressure, reactor thermal power and generator power factor; the power generation power of the nuclear power unit under TMCR condition is corrected according to the following formula:

[0079]

[0080] Among them, P θ is the corrected power generation of the nuclear power unit under TMCR conditions, in kW; P net It is the power generation of the nuclear power unit under heating conditions, in kW;

[0081] θ pms is the main steam pressure correction factor, θ xms is the main steam humidity correction factor, θ pds is the steam turbine exhaust pressure correction factor, θ QNT is the reactor thermal power correction factor, θ PF is the generator power factor correction coefficient;

[0082] The nuclear power unit operating parameter correction curve provided by the nuclear power unit manufacturer includes the nuclear power unit operating parameters and the correction coefficients corresponding to the nuclear power unit operating parameters; according to the nuclear power unit operating parameters during the nuclear energy steam supply system test, the corresponding correction coefficients are found in the nuclear power unit operating parameter correction curve provided by the turbine manufacturer.

[0083] In this embodiment, as one of the achievable methods, in step 104, the test results of the nuclear energy steam supply system include the steam supply efficiency of the nuclear energy steam supply system, the heating efficiency of the nuclear power unit and the power impact value of the nuclear energy steam supply system.

[0084] In this embodiment, as one of the achievable methods, the steam supply efficiency of the nuclear energy steam supply system is calculated according to the following formula:

[0085]

[0086] Among them, η gq is the steam supply efficiency of nuclear energy steam supply system; F wg It is the external steam flow rate under the design condition test of nuclear energy steam supply system, in kg / h; H wg H is the enthalpy of external steam at the design operating test pressure and temperature, in kJ / kg; gs The feed water enthalpy value at the design test pressure and temperature of the nuclear steam supply system, in kJ / kg; P θ is the corrected power generation of the nuclear power unit under TMCR conditions, in kW, P θ ′ is the corrected power generation of the nuclear power unit under heating conditions, in kW.

[0087] In this embodiment, as one of the achievable methods, the heating efficiency of the nuclear power unit is calculated according to the following formula:

[0088]

[0089] in, is the heating efficiency of nuclear power units; F wg It is the external steam flow rate under the design condition test of nuclear energy steam supply system, in kg / h; H wg H is the enthalpy of external steam at the design operating test pressure and temperature, in kJ / kg; gs Q is the feed water enthalpy value at the design test pressure and temperature of the nuclear power steam supply system, in kJ / kg; N P is the thermal power of the nuclear island under the heating condition of the nuclear power unit, in kW; θ ′ is the corrected power generation of the nuclear power unit under heating conditions, in kW.

[0090] In this embodiment, as one of the achievable methods, the power impact value of the nuclear energy steam supply system is calculated according to the following formula:

[0091]

[0092] Among them, ΔP is the power impact value of the nuclear energy steam supply system; P θ ′ is the corrected power generation of the nuclear power unit under heating conditions, in kW; Pθ is the corrected power generation of the nuclear power unit under TMCR conditions, in kW; F wgX F is the external steam flow rate under the design conditions of the nuclear energy steam supply system, in kg / h; wg It is the external steam supply flow rate under the design operating condition test of the nuclear energy steam supply system, in kg / h.

[0093] After the nuclear steam supply system test is completed, uncertainty analysis of the test results of the nuclear steam supply system is required. The uncertainty of the test results of the nuclear steam supply system depends on the combined influence of parameter errors and variable errors in the nuclear steam supply system test and nuclear power unit test.

[0094] According to the performance of nuclear power units and nuclear energy steam supply systems, certain variables have a greater impact on the test results, such as the main steam pressure, main steam humidity, reheat steam temperature, exhaust pressure, extraction pressure, extraction flow, electric power, voltage and power factor of the steam turbine. The uncertainty of the test results of the nuclear energy steam supply system is controlled within ±(1.0%~1.17%).

[0095] In this embodiment, as one of the feasible ways, the general nuclear energy steam supply system performance test method also includes: step 105, performing uncertainty analysis on the test results of the nuclear energy steam supply system to ensure that the external steam supply flow rate under the design operating condition test of the nuclear energy steam supply system meets the design indicators and the test results of the nuclear energy steam supply system reach the guaranteed value.

[0096] In this embodiment, as one of the achievable methods, uncertainty analysis is performed on the test results of the nuclear energy steam supply system according to the uncertainty of the parameters and variables of the nuclear energy steam supply system test, including the following steps:

[0097] Determine the uncertainty of each parameter, the uncertainty of each parameter comes from instrument uncertainty, time uncertainty and spatial uncertainty;

[0098] Determine the uncertainty of each variable. The uncertainty of each variable comes from the uncertainty of each parameter involved in the calculation of the variable and the influence of each parameter involved in the calculation of the variable on the variable.

[0099] Determine the uncertainty of each parameter and each variable on the test results. The uncertainty of the variable on the test results = the uncertainty of the variable × the influence coefficient of the variable on the test results; the uncertainty of the parameter on the test results = the uncertainty of the parameter × the influence coefficient of the parameter on the test results;

[0100] Calculate the uncertainty of the test results based on the uncertainty of each parameter and each variable to the test results.

[0101] In this embodiment, as one of the achievable methods, the parameters include temperature, pressure, voltage and current;

[0102] The instrument uncertainty is expressed as the uncertainty of the measurement mean:

[0103]

[0104] Among them, U1 is the uncertainty of the measured average value; U′1 is the uncertainty of the instrument itself, which can be obtained from the instrument calibration report; M is the number of instruments used to measure the same parameter.

[0105] In this embodiment, as one of the achievable ways, the time uncertainty is represented by the estimated value of the standard deviation of the measurement parameter:

[0106]

[0107] Where S is the estimated standard deviation of the measured parameter; X I is a single reading of a measured parameter; is the average value of the measured parameter; N is the number of readings of the measured parameter;

[0108] The uncertainty of the average of the individual instrument readings is:

[0109]

[0110] Among them, U t is the uncertainty of the average value of a single instrument reading; v is the degree of freedom, which is equal to N-1; t v is the t distribution value when the confidence level is 95% and the degrees of freedom are v;

[0111] When multiple instruments of the same accuracy measure the same parameter, the uncertainty of the average value of the multiple instrument readings is:

[0112]

[0113] Among them, U t is the uncertainty of the average value of multiple instrument readings, M is the number of instruments; v is the degree of freedom, which is equal to M×(N-1); The average value of S calculated for each meter reading.

[0114] In this embodiment, as one of the possible implementations, the spatial uncertainty is represented by the uncertainty of the mean value caused by the spatial variability:

[0115] U S =t′ L ×R

[0116] Among them, U S is the uncertainty of the mean value caused by spatial variability; R is the value range, which is the difference between the maximum and minimum values ​​of the average value of the instrument reading; t′L is the distribution value of the substitute t, which can be obtained by looking up the table.

[0117] It should be noted that in actual on-site measurements, some variability that appears to be caused by different measurement point locations may actually be caused by instrument uncertainty. Therefore, the instrument uncertainty and spatial uncertainty should be compared, and the larger one should be taken to determine the total uncertainty.

[0118] In this embodiment, as one of the achievable methods, the uncertainty of the parameter is:

[0119]

[0120] Among them, U P is the uncertainty of the parameter; U Pt is the time uncertainty of the parameter, U PI is the instrument uncertainty of the parameter, U PI is the spatial uncertainty of the parameter.

[0121] In this embodiment, as one of the achievable methods, the variables affecting the test results are calculated through the measured values ​​of the parameters, and the variables include flow rate and electric power;

[0122] The uncertainty of the variables is:

[0123]

[0124] Among them, U R is the uncertainty of the variable; is the variable with P I The influence coefficient of the change.

[0125] In this embodiment, as one of the achievable methods, the uncertainty of the flow rate is:

[0126]

[0127] Among them, U W is the uncertainty of flow rate, U d is the uncertainty of the flow device opening diameter, U k is the uncertainty of the outflow coefficient, U ΔP is the uncertainty of flow differential pressure, U ρ is the uncertainty of specific gravity.

[0128] In this embodiment, as one of the achievable methods, the uncertainty of power is:

[0129]

[0130] Among them, U Gis the uncertainty of power, U I is the uncertainty of current measurement, U V is the uncertainty of voltage measurement.

[0131] In this embodiment, as one of the achievable methods, the square root of the sum of the squares of the uncertainty of each parameter and each variable to the test result is taken as the uncertainty of the test result.

[0132] The universal nuclear energy steam supply system performance test method of this embodiment reasonably arranges relevant performance test measurement points in the nuclear power unit and the nuclear energy steam supply system, measures and calculates the steam supply efficiency of the nuclear energy steam supply system, the heating efficiency of the nuclear power unit and the power impact value of the nuclear energy steam supply system, can effectively evaluate the economy of the nuclear energy steam supply system, and objectively reflect the economy level of the operation of the nuclear energy steam supply system.

[0133] The universal nuclear energy steam supply system performance test method of this embodiment makes accurate corrections to the power influence value of the nuclear energy steam supply system based on the power generation power of the nuclear power unit under the TMCR condition, the corrected power generation power of the nuclear power unit under the heating condition and the external steam flow rate under the design condition of the nuclear energy steam supply system. It has strong engineering operability and does not require the overall correction of the nuclear energy steam supply system. It simplifies the mutual interference of various equipment during operation during the nuclear energy steam supply system test and improves the accuracy of the test results of the nuclear energy steam supply system.

[0134] The universal nuclear energy steam supply system performance test method of this embodiment, as a supplement to the nuclear energy steam supply system performance test standard, makes the nuclear energy steam supply system performance test more fair and accurate, measures and calculates the steam supply efficiency of the nuclear energy steam supply system, the heating efficiency of the nuclear power unit and the power impact value of the nuclear energy steam supply system in real time, effectively evaluates the design perfection of the nuclear energy steam supply system, and realizes an objective evaluation of its energy utilization degree.

[0135] The above-mentioned embodiments only express several implementation methods of the present invention, and the description thereof is relatively specific and detailed, but it cannot be understood as limiting the scope of the patent of the present invention. It should be pointed out that, for ordinary technicians in this field, several variations and improvements can be made without departing from the concept of the present invention, which all belong to the protection scope of the present invention. Therefore, the protection scope of the patent of the present invention shall be subject to the attached claims.

Claims

1. A general nuclear energy steam supply system performance test method, characterized in that: The steps include: Step 101, determine the boundary of the nuclear energy steam supply system, and arrange the performance test points of the nuclear power unit and the nuclear energy steam supply system; Step 102: Perform a performance test on the nuclear power unit under the TMCR operating condition to obtain the power generation of the nuclear power unit under the TMCR operating condition; Step 103: Based on the power generation of the nuclear power unit under the TMCR condition, a performance test is performed on the nuclear energy steam supply system under the design condition to obtain the external steam supply flow rate under the design condition test of the nuclear energy steam supply system; and the external steam supply flow rate under the design condition test of the nuclear energy steam supply system is corrected to the design condition; Step 104: According to the operating parameters of the nuclear power unit during the test of the nuclear energy steam supply system, the power generation of the nuclear power unit under the TMCR condition is corrected, and the test results of the nuclear energy steam supply system are calculated.

2. The nuclear energy steam supply system performance test method according to claim 1, characterized in that: In step 101, the nuclear power unit comprises a secondary circuit working fluid pump (6), a heater (7), a secondary circuit evaporator (8), a steam turbine (9), a condenser (5) and a generator (10); the secondary circuit working fluid pump (6), the heater (7), the secondary circuit evaporator (8), the steam turbine (9) and the condenser (5) are connected in sequence to form a closed loop passage for the circulation of the secondary circuit working fluid; the steam turbine (9) is connected to the generator (10); the generator (10) converts the mechanical energy of the steam turbine (9) into electrical energy; and the nuclear power unit performance test measurement points are arranged as follows: a temperature measurement point, a pressure measurement point and a flow measurement point are arranged at the working fluid side inlet of the secondary circuit evaporator, a temperature measurement point and a pressure measurement point are arranged at the working fluid side outlet of the secondary circuit evaporator, a pressure measurement point is arranged at the turbine inlet, a pressure measurement point is arranged in the condenser, and an electrical power measurement point is arranged on the generator.

3. The nuclear energy steam supply system performance test method according to claim 1, characterized in that: In step 101, the nuclear energy steam supply system comprises a feedwater pump (1), a preheater (2), an evaporator (3) and a superheater (4); the feedwater pump (1), the working fluid side of the preheater (2), the working fluid side of the evaporator (3) and the working fluid side of the superheater (4) are connected in sequence to form the working fluid side of the nuclear energy steam supply system; the heat source side of the preheater (2), the heat source side of the evaporator (3) and the heat source side of the superheater (4) are connected in sequence to form the heat source side of the nuclear energy steam supply system; the nuclear energy steam supply system performance test measurement points are arranged as follows: temperature measurement points, pressure measurement points and flow measurement points are arranged at the inlet and outlet of the working fluid side of the nuclear energy steam supply system, pressure measurement points and flow measurement points are arranged at the inlet of the heat source side of the nuclear energy steam supply system, and pressure measurement points, flow measurement points and temperature measurement points are arranged at the outlet of the heat source side of the nuclear energy steam supply system.

4. The nuclear energy steam supply system performance test method according to claim 1, characterized in that: Step 102, performing a performance test on the nuclear power unit under the TMCR operating condition to obtain the power generation of the nuclear power unit under the TMCR operating condition, includes the following steps: Set the nuclear power unit status according to the turbine performance test requirements and ensure that the turbine operating parameters meet the stability requirements; The power generation of nuclear power units under TMCR conditions is measured. During the performance test of the nuclear energy steam supply system, the nuclear power units are operated according to TMCR conditions.

5. The nuclear energy steam supply system performance test method according to claim 1, characterized in that: In step 103, the design working conditions of the nuclear energy steam supply system include: heating of a single nuclear power unit or joint heating of multiple nuclear power units, the nuclear energy steam supply system has a single set of evaporators (3) or multiple sets of evaporators (3), among the multiple sets of evaporators (3), one set of evaporators (3) is a main evaporator, and the remaining evaporators (3) are standby evaporators; During the performance test of the nuclear energy steam supply system under the design conditions, the nuclear power units are operated according to the TMCR conditions. Under the condition of joint heating of multiple nuclear power units, each nuclear power unit provides heat separately. Under the condition of stable heating load, multiple nuclear power units jointly provide heat. Under the condition of a single evaporator (3), the single evaporator (3) is operated at full load. Under the condition of multiple evaporators (3), each evaporator (3) is operated at full load at least once.

6. The nuclear energy steam supply system performance test method according to claim 1, characterized in that: In step 103, the external steam supply flow rate under the design operating condition test of the nuclear energy steam supply system is corrected to the design operating condition according to the following formula: Among them, F wgX F is the external steam flow rate under the design conditions of the nuclear energy steam supply system, in kg / h; wg It is the external steam flow rate under the design condition test of nuclear energy steam supply system, in kg / h; H wg It is the enthalpy of external steam at the design working condition test pressure and temperature of the nuclear energy steam supply system, in kJ / kg; H wg ′ is the enthalpy of external steam at the design operating pressure and temperature of the nuclear energy steam supply system, in kJ / kg; H gs It is the feed water enthalpy value at the design operating pressure and operating temperature of the nuclear power steam supply system, in kJ / kg, H gs ′ is the feed water enthalpy at the design operating pressure and temperature of the nuclear energy steam supply system, in kJ / kg.

7. The nuclear energy steam supply system performance test method according to claim 1, characterized in that: In step 104, the operating parameters of the nuclear power unit include main steam pressure, main steam humidity, turbine exhaust pressure, reactor thermal power and generator power factor; the power generation of the nuclear power unit under the TMCR condition is corrected according to the following formula: Among them, P θ is the corrected power generation of the nuclear power unit under TMCR conditions, in kW; P net It is the power generation of the nuclear power unit under heating conditions, in kW; θ pms is the main steam pressure correction factor, θ xms is the main steam humidity correction factor, θ pds is the steam turbine exhaust pressure correction factor, θ QNT is the reactor thermal power correction factor, θ PF is the generator power factor correction coefficient.

8. The nuclear energy steam supply system performance test method according to claim 1, characterized in that: In step 104, the test results of the nuclear energy steam supply system include the steam supply efficiency of the nuclear energy steam supply system, the heating efficiency of the nuclear power unit and the power impact value of the nuclear energy steam supply system.

9. The nuclear energy steam supply system performance test method according to claim 8, characterized in that: The steam supply efficiency of the nuclear energy steam supply system is calculated according to the following formula: Among them, η gq is the steam supply efficiency of nuclear energy steam supply system; F wg It is the external steam flow rate under the design condition test of nuclear energy steam supply system, in kg / h; H wg H is the enthalpy of external steam at the design operating test pressure and temperature, in kJ / kg; gs The feed water enthalpy value at the design test pressure and temperature of the nuclear steam supply system, in kJ / kg; P θ is the corrected power generation of the nuclear power unit under TMCR, in kW; P θ , is the corrected power generation capacity of the nuclear power unit under heating conditions, in kW.

10. The nuclear energy steam supply system performance test method according to claim 8, characterized in that: The heating efficiency of the nuclear power unit is calculated according to the following formula: in, is the heating efficiency of nuclear power units; F wg It is the external steam flow rate under the design condition test of nuclear energy steam supply system, in kg / h; H wg H is the enthalpy of external steam at the design operating test pressure and temperature, in kJ / kg; gs Q is the feed water enthalpy value at the design test pressure and temperature of the nuclear power steam supply system, in kJ / kg; N P is the thermal power of the nuclear island under the heating condition of the nuclear power unit, in kW; θ , is the corrected power generation capacity of the nuclear power unit under heating conditions, in kW.

11. The nuclear energy steam supply system performance test method according to claim 8, characterized in that: The power impact value of the nuclear energy steam supply system is calculated according to the following formula: Among them, ΔP is the power impact value of the nuclear energy steam supply system; P θ , is the power generation of the nuclear power unit under heating conditions, in kW; P θ is the corrected power generation of the nuclear power unit under TMCR conditions, in kW; F wgX F is the external steam flow rate under the design conditions of the nuclear energy steam supply system, in kg / h; wg It is the external steam supply flow rate under the design operating condition test of the nuclear energy steam supply system, in kg / h.

12. The nuclear energy steam supply system performance test method according to claim 1, characterized in that: It also includes: step 105, performing uncertainty analysis on the test results of the nuclear energy steam supply system to ensure that the external steam supply flow rate under the design operating condition test of the nuclear energy steam supply system meets the design indicators and the test results of the nuclear energy steam supply system reach the guaranteed value.

13. The nuclear energy steam supply system performance test method according to claim 12, characterized in that: According to the uncertainty of the parameters and variables of the nuclear energy steam supply system test, the uncertainty analysis of the test results of the nuclear energy steam supply system is carried out, including the following steps: Determine the uncertainty of each parameter, the uncertainty of each parameter comes from instrument uncertainty, time uncertainty and spatial uncertainty; Determine the uncertainty of each variable. The uncertainty of each variable comes from the uncertainty of each parameter involved in the calculation of the variable and the influence of each parameter involved in the calculation of the variable on the variable. Determine the uncertainty of each parameter and each variable on the test results. The uncertainty of the variable on the test results = the uncertainty of the variable × the influence coefficient of the variable on the test results; the uncertainty of the parameter on the test results = the uncertainty of the parameter × the influence coefficient of the parameter on the test results; Calculate the uncertainty of the test results based on the uncertainty of each parameter and each variable to the test results.

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