UNIVERSAL PERFORMANCE TESTING METHOD FOR NUCLEAR STEAM POWER SYSTEMS

Abstract

UNIVERSAL PERFORMANCE TEST METHOD FOR NUCLEAR STEAM SUPPLY SYSTEM This disclosure specifically relates to a universal performance test method for a nuclear steam supply system, which includes: determining a limit of the nuclear steam supply system, and arranging performance test measurement points of a nuclear power generating unit and the nuclear steam supply system; determining a power generated by the nuclear power generating unit under the TMCR condition; performing a performance test on the nuclear steam supply system under a design condition based on the power generated by the nuclear power generating unit under the TMCR condition, and correcting a steam flow rate exported from the nuclear steam supply system subsequent to the design condition;and the correction of the power generated by the nuclear power generation unit under the TMCR condition, and the calculation of a test result for the nuclear steam feed system. This disclosure objectively and accurately reflects an operating state of the nuclear steam feed system and provides reliable support for design verification, performance evaluation, and subsequent optimization design of the steam feed system. Summary figure: Fig. 1;

Description

Title of the invention: UNIVERSAL PERFORMANCE TESTING METHOD FOR NUCLEAR STEAM SUPPLY SYSTEMS technical field

[0001] This disclosure relates to the technical field of adjusting nuclear steam supply systems, and in particular, a universal performance testing method for a nuclear steam supply system. STATE OF THE ART

[0002] Nuclear steam supply is a process of gradually heating a working fluid in a liquid state at ambient temperature into superheated steam using saturated steam from a secondary circuit generated by a reactor as the heat source and transporting the superheated steam remotely to a user. With the clean and low-carbon transformation of the national energy system and the scarcity and rising prices of traditional fossil fuels such as natural gas, the demand for nuclear steam supply from energy-intensive companies such as the petrochemical industry has become more pronounced. Nuclear steam supply is developing rapidly and has considerable room for further development.

[0003] A nuclear steam supply system prepares superheated steam using a saturated steam heat source and has a relatively complex thermal system and equipment structure. A traditional fossil fuel-fired steam supply system adopts a direct steam feed from a secondary circuit, and steam quality parameters and system efficiency variations can be obtained only by a turbine thermal performance test. However, in the nuclear steam supply system, phase changes of the working fluids on the cold and hot sides of the evaporator and superheater equipment occur simultaneously, and there are numerous backup circuits and operating conditions.Performance evaluation cannot be achieved solely through a thermal performance test of a steam turbine; the performance index of the nuclear steam supply system after system commissioning can only be assessed in detail by simultaneously performing a system performance test and the thermal performance test of the steam turbine, and the operating condition is objectively and truly reflected, thus providing reliable support for verification. design, performance evaluation and subsequent optimization design of the steam supply system. SUMMARY

[0004] One objective of this disclosure is to provide a universal performance test method for a nuclear steam supply system, which objectively and truly reflects an operating state of the nuclear steam supply system, and provides reliable support for design verification, performance evaluation and subsequent optimization design of the steam supply system.

[0005] To achieve the aforementioned objective, this disclosure provides the following technical solutions.

[0006] A universal performance test method for a nuclear steam supply system comprises the following steps: Step 101: Determine a limit of the nuclear steam supply system, and have measurement points for performance testing of a nuclear power unit and the nuclear steam supply system; step 102: perform a performance test on the nuclear power unit under a maximum turbine continuous rate (TMCR) condition to obtain power generated from the nuclear power unit under the TMCR condition; Step 103: Perform a performance test on the nuclear steam feed system under a design condition based on the power generated by the nuclear power unit under the TMCR condition to obtain an export steam flow rate from the nuclear steam feed system during the test under the design condition; and correct the export steam flow rate from the nuclear steam feed system during the test under the design condition to the design condition; and Step 104: Correct the power generated by the nuclear power unit in the TMCR condition according to the operating parameters of the nuclear power unit during the nuclear steam supply system test, and calculate a test result for the nuclear steam supply system.

[0007] According to one embodiment, in step 101, the nuclear power unit comprises a secondary circuit working fluid pump, a heater, a secondary circuit evaporator, a steam turbine, a condenser, and a generator, where the secondary circuit working fluid pump, heater, secondary circuit evaporator, steam turbine, and condenser are sequentially connected to form a closed-loop passage for the circulation of a 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; and the arrangement of the measurement points for the performance test of the nuclear power unit is as follows: a temperature measurement point, a pressure measurement point and a flow measurement point are arranged at a working fluid inlet of the evaporator of a secondary circuit, a temperature measurement point and a pressure measurement point are arranged at a working fluid outlet of the evaporator of a secondary circuit, a pressure measurement point is arranged at a steam turbine inlet, a pressure measurement point is arranged in the condenser, and an electrical energy measurement point is arranged on the generator.

[0008] According to one embodiment, in step 101, the nuclear steam supply system comprises: a working fluid pump, a preheater, an evaporator and a superheater, where the working fluid pump, a working fluid side of the preheater, a working fluid side of the evaporator and a working fluid side of the superheater are sequentially connected to form a working fluid side of the nuclear steam supply system, and a heat source side of the preheater, a heat source side of the evaporator and a heat source side of the superheater are sequentially connected to form a heat source side of the nuclear steam supply system;and the arrangement of the measurement points for performance testing of the nuclear steam supply system is as follows: a temperature measurement point, a pressure measurement point and a flow measurement point are arranged at each of an inlet and an outlet on the working fluid side of the nuclear steam supply system, a pressure measurement point and a flow measurement point are arranged at an inlet on the heat source side of the nuclear steam supply system, and a pressure measurement point, a flow measurement point and a temperature measurement point are arranged at an outlet on the heat source side of the nuclear steam supply system.

[0009] According to one implementation, performing the performance test on the nuclear unit under the TMCR condition to obtain the power generated by the nuclear unit under the TMCR condition in step 102 includes the following steps: setting a state of the nuclear unit according to a performance test requirement of a steam turbine, and determining that the operating parameters of the steam turbine meet a stability requirement; and measuring the power generated by the nuclear unit under the TMCR condition, where the nuclear unit operates according to the TMCR condition during the performance test of the nuclear steam supply system.

[0010] According to one implementation, in step 103, the design condition of the nuclear steam supply system includes: heat supply by a single nuclear power unit or joint heat supply by a plurality of nuclear power units, the nuclear steam supply system is provided with a single set of evaporators or a plurality of sets of evaporators, among which one set of evaporators serves as the main evaporator and the other evaporators serve as backup evaporators; The nuclear power unit operates under the TMCR condition during the performance test of the nuclear steam supply system under the design condition; each nuclear power unit provides heat under the condition of joint heat supply by the plurality of nuclear power units; the plurality of nuclear power units jointly provide heat under a stable heat load condition; the single set of evaporators operates at full load under the single set of evaporators condition; and each set of evaporators operates at least once at full load under the plurality of sets of evaporators condition.

[0011] According to one implementation, in step 103, the steam flow rate exported from the nuclear steam supply system during the test under the design condition is corrected according to the design condition using the following formula: [Math 1] jt __ f'wgf-Hwg'-Kgs) WgX ( TT Tj \ y (riwg "“gs / where .FWgx is the steam export flow rate from the nuclear steam supply system under the design condition, expressed in kg / h; KWg is the steam export flow rate from the nuclear steam supply system during the test under the design condition, expressed in kg / h; Jfwg is an enthalpy of the steam exported from the nuclear steam supply system at the pressure and temperature during the test under the design condition, expressed in kJ / kg; 'is an enthalpy of the steam exported from the nuclear steam supply system at the pressure and temperature under the design condition, expressed in kJ / kg; figs is an enthalpy of the feedwater of the nuclear steam supply system at the operating pressure and temperature during the test under the design condition, expressed in kJ / kg; and Hgs is an enthalpy of the feedwater of the nuclear steam supply system at the pressure and temperature under the design condition, expressed in kJ / kg.

[0012] According to one embodiment, during step 104, the operating parameters of the nuclear unit include a main steam pressure, a main steam moisture content, a turbine exhaust steam pressure, a power reactor thermal conductivity and a generator power factor; and the power generated by the nuclear unit under the TMCR condition is corrected according to the following formula: [Math 2] P "D __ a~

[0013] where Pq is the corrected generated power of the nuclear production unit in the TMCR condition, expressed in kW; Pnet is the generated power of the nuclear production unit in the heat supply condition, expressed in kW; and Opms is a correction factor for the main steam pressure, 0xnis is a correction factor for the moisture content of the main steam, is a correction factor for the turbine exhaust steam pressure, ^QNT is a correction factor for the reactor thermal power, and Qpp is a correction factor for the generator power factor.

[0014] According to one implementation, in step 104, the result of the test of the nuclear steam supply system includes a steam supply efficiency of the nuclear steam supply system, a heat supply efficiency of the nuclear production unit, and a power impact value of the nuclear steam supply system.

[0015] According to one embodiment, the steam supply efficiency of the nuclear steam supply system is calculated according to the following formula: [Math 3] _ Fwg(Wwg-HgS)x3600 where is the steam supply efficiency of the ^gq- Pe-Pe' nuclear steam supply system; PWg is an export steam flow rate of the nuclear steam supply system during the test under the design condition, expressed in kg / h; is an enthalpy of the export steam at pressure and temperature during the test under the design condition, expressed in kJ / kg; HgS is an enthalpy of the feed water of the nuclear steam supply system at pressure and temperature during the test under the design condition, expressed in kJ / kg; Pq is a corrected power generated of the nuclear power unit under the TMCR condition, expressed in kW; and p® is a corrected power generated of the nuclear power unit under the heat supply condition, expressed in kW.

[0016] According to one embodiment, the heat supply efficiency of the nuclear power unit is calculated according to the following formula: [Math 4] _ Fwg(HWcrHgS)x3600+Pe' where V is the efficiency of the heat input from the unit of _____ nuclear power generation; FWg is a steam flow rate exported from the nuclear steam supply system during the test under the design condition, expressed in kg / h; H-wg is an enthalpy of the steam exported at the pressure and temperature during the test under the design condition, expressed in kJ / kg; HgS is an enthalpy of the feedwater of the nuclear steam supply system at the pressure and temperature during the test under the design condition, expressed in kJ / kg; Q is a thermal power of a nuclear island of the nuclear power generation unit under the heat supply condition, expressed in kW; and is a corrected generated power of the nuclear power generation unit under the heat supply condition, expressed in kW.

[0017] According to one implementation, the power impact value of the nuclear steam supply system is calculated according to the following formula: [Math 5] Pa-Pa t-, ^P=-p~~~ XFWg 1 wgX J where AP is the power impact value of the nuclear steam supply system; Pg is a power generated from the nuclear power unit under a thermal supply condition in a unit of kW; Pg is a corrected power generated from the nuclear power unit under the TMCR condition in a unit of kW; FWgx is a steam flow rate exported from the nuclear steam supply system under the design condition in a unit of kg / h; and FWg is a steam flow rate exported from the nuclear steam supply system during the test under the design condition in a unit of kg / h.

[0018] According to one embodiment, the universal performance test method for the nuclear steam supply system further includes: step 105. performing an uncertainty analysis on the result of the test of the nuclear steam supply system to ensure that the steam flow rate exported from the nuclear steam supply system during the test under the design condition meets a design indicator and that the result of the test of the nuclear steam supply system reaches a guaranteed value.

[0019] According to one implementation, performing an uncertainty analysis on the result of the nuclear steam supply system test based on the uncertainty of the test parameters and variables for the nuclear steam supply system includes the following steps:

[0020] determination of the uncertainty of each parameter, where the uncertainty of each parameter comes from the uncertainty of the instruments, the temporal uncertainty and the spatial uncertainty;

[0021] determination of the uncertainty of each variable, where the uncertainty of each variable comes from the uncertainty of each parameter involved in calculating the variable and from an influence of each parameter involved in calculating the variable on the variable;

[0022] determination of the uncertainty of each parameter and each variable on the result of the test, where the uncertainty of the variable on the result of the test = the uncertainty of the variable x a coefficient of influence of the variable on the result of the test; the uncertainty of the parameter on the result of the test = the uncertainty of the parameter x a coefficient of influence of the parameter on the result of the test; and

[0023] determination of the uncertainty of the result of the test according to the uncertainty of each parameter and each variable on the result of the test.

[0024] This disclosure has the following beneficial technical effects:

[0025] According to the universal performance test method for the nuclear steam supply system, relevant performance test measurement points are reasonably arranged in the nuclear power generation unit and the nuclear steam supply system, the steam supply efficiency of the nuclear steam supply system, the heat supply efficiency of the nuclear power generation unit and the power impact value of the nuclear steam supply system are measured and calculated, the economy of the nuclear steam supply system can be effectively evaluated, and the level of operational economy of the nuclear steam supply system is objectively reflected.

[0026] According to the universal performance test method for nuclear steam supply systems, based on the power generated by the nuclear power unit under the TMCR condition, the corrected power generated by the nuclear power unit under the heat supply condition, and the steam flow rate exported from the nuclear steam supply system under the design condition, the power impact value of the nuclear steam supply system is accurately corrected, resulting in high technical operability. It is not necessary to correct the entire nuclear steam supply system, which simplifies the mutual interference of the various pieces of equipment operating during the test of the nuclear steam supply system and improves the accuracy of the test results.

[0027] The universal performance test method for the nuclear steam supply system, as a supplement to the performance test standard of the nuclear steam supply system, allows the performance testing of the nuclear steam supply system to operate more fairly and accurately, measures and calculates in real time the steam supply efficiency of the nuclear steam supply system, the heat supply efficiency of the nuclear power generation unit and the power impact value of the nuclear steam supply system, effectively evaluates the design integrity of the nuclear steam supply system and objectively assesses the degree of energy utilization of the nuclear steam supply system. BRIEF DESCRIPTION OF THE DRAWINGS

[0028] [Fig. 1] is a structural diagram of an embodiment of a universal nuclear steam supply system according to the present disclosure; and

[0029] [Fig.2] is a flowchart of an embodiment of a universal method performance testing for a nuclear steam supply system as disclosed herein.

[0030] Numerical references: 1. water supply pump; 2. preheater; 3. evaporator; 4. superheater; 5. condenser; 6. working fluid pump of a secondary circuit; 7. heater; 8. evaporator of a secondary circuit; 9. steam turbine; and 10. generator. DETAILED DESCRIPTION OF THE IMPLEMENTATION METHODS.

[0031] Unless otherwise defined, all technical and scientific terms used in this specification have the same meanings as those generally understood by persons competent in the field of this disclosure. The terms used in the specification of this disclosure serve only to describe specific embodiments and are not intended to limit this disclosure. The terms "including" and "having," and all their variations, in the specification and claims of this disclosure and in the descriptions of the accompanying figures are intended to cover non-exclusive inclusion.

[0032] An "embody" referred to in this specification means that a particular feature, structure, or characteristic described with reference to that embodiment may be included in at least one embodiment of this disclosure. The phrase appearing in various places in this specification does not necessarily refer to a single embodiment and is not an independent or optional embodiment exclusive of another embodiment. It is explicitly and implicitly understood by a person competent in the field that the embodiments described in this specification may be combined with another embodiment.

[0033] The technical solutions of this disclosure are described below clearly and completely in connection with the accompanying figures and specific embodiments.

[0034] With reference to [Fig.2], this embodiment provides a universal performance testing method for a nuclear steam supply system, which comprises the following steps: Step 101: Determine a limit of the nuclear steam supply system, and have test measurement points for the performance of a nuclear unit and the nuclear steam supply system; step 102: perform a performance test on the nuclear unit under a TMCR condition to obtain power generated from the nuclear unit under the TMCR condition; Step 103: Perform a performance test on the nuclear steam feed system under a design condition based on the power generated by the nuclear unit under the TMCR condition to obtain an export steam flow rate from the nuclear steam feed system during the test under the design condition; and correct the export steam flow rate from the nuclear steam feed system during the test under the design condition to the design condition; and Step 104: Correct the power generated by the nuclear unit in the TMCR condition according to the operating parameters of the nuclear unit during the nuclear steam supply system test, and calculate a test result for the nuclear steam supply system.

[0035] To highlight the nuclear steam supply system and simplify the nuclear power unit, with reference to [Fig.1], in this embodiment, according to one implementation, in step 101, the nuclear power unit comprises a working fluid pump of a secondary circuit 6, a heater 7, an evaporator of a secondary circuit 8, a steam turbine 9, a condenser 5 and a generator 10, where the working fluid pump of a secondary circuit 6, the heater 7, the evaporator of a secondary circuit 8, the steam turbine 9 and the condenser 5 are put into sequential communication to form a closed loop passage for the circulation of a working fluid of a secondary circuit, 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.

[0036] During the operating process of the nuclear power unit, the working fluid of a secondary circuit sequentially passes through the condenser 5, the working fluid pump of a secondary circuit 6 and the heater 7, then enters the evaporator of a secondary circuit 8. The evaporator of a secondary circuit 8 generates Saturated steam enters steam turbine 9, steam turbine 9 converts saturated steam into mechanical energy, and generator 10 converts mechanical energy into electrical energy.

[0037] The arrangement of the measurement points for the performance tests of the nuclear power unit is as follows: a temperature measurement point, a pressure measurement point and a flow measurement point are arranged at a working fluid inlet of the evaporator of a secondary circuit, a temperature measurement point and a pressure measurement point are arranged at a working fluid outlet of the evaporator of a secondary circuit, a pressure measurement point is arranged at an inlet of the steam turbine, a pressure measurement point is arranged in the condenser and an electrical energy measurement point is arranged on the generator.

[0038] With reference to [Fig.1], in this embodiment, according to one implementation, in step 101, the nuclear steam supply system comprises: a water supply pump 1, a preheater 2, an evaporator 3 and a superheater 4, where the water supply pump 1, a working fluid side of the preheater 2, a working fluid side of the evaporator 3 and a working fluid side of the superheater 4 are sequentially connected to form a working fluid side of the nuclear steam supply system and a heat source side of the preheater 2, a heat source side of the evaporator 3 and a heat source side of the superheater 4 are sequentially connected to form a heat source side of the nuclear steam supply system.

[0039] In the operating process of the nuclear steam supply system, the saturated steam generated by the evaporator 8 of a secondary circuit is extracted to the heat source side of the nuclear steam supply system, and a working fluid from the working fluid side of the nuclear steam supply system is heated by inter-wall heat exchange to form condensed water, and the condensed water enters the condenser 5; the working fluid from the working fluid side of the nuclear steam supply system is progressively heated to form superheated steam through the preheater 2, evaporator 3 and superheater 4 in sequence, and is transported to the users as export steam.

[0040] The arrangement of the measurement points for the performance test of the nuclear steam supply system is as follows: a temperature measurement point, a pressure measurement point, and a flow measurement point are located at each of the inlets and outlets on the working fluid side of the nuclear steam supply system; a pressure measurement point and a flow measurement point are located at an inlet on the heat source side of the nuclear steam supply system; and a pressure measurement point, a flow measurement point, and a measurement point temperature sensors are located at an outlet on the heat source side of the nuclear steam supply system.

[0041] In this embodiment, according to one implementation, in the case where the nuclear steam supply system is provided with a feedwater heating line, a pressure measurement point, a flow measurement point and a temperature measurement point are arranged on the feedwater heating line.

[0042] In this embodiment, according to one implementation, performing the performance test on the nuclear unit under the TMCR condition to obtain the power generated by the nuclear unit under the TMCR condition in step 102 comprises the following steps: to adjust the state of the nuclear unit according to a performance test requirement for a steam turbine, and to determine that the operating parameters of the steam turbine meet a stability requirement; and measure the power generated by the nuclear unit under the TMCR condition, where the nuclear unit operates under the TMCR condition during the performance test of the nuclear steam supply system.

[0043] In this embodiment, according to one implementation, the operational parameters of the steam turbine include a main steam pressure, a main steam moisture content, a reheated steam temperature, an exhaust steam pressure, an extracted steam pressure, an extracted steam flow rate, an electrical power, a voltage, and a power factor.

[0044] The steam turbine performance test requirements 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 moisture content is ±0.5%, the allowable fluctuation of the main steam moisture content is ±0.1%, the allowable deviation of the reheated steam temperature is ±15 °C, the allowable fluctuation of the reheated steam temperature is ±4 °C, the allowable fluctuation of the exhaust steam pressure is 0.14 kPa, the allowable deviation of the extraction steam pressure is ±5 kPa, the allowable deviation of the extraction steam flow rate is ±5 kg / s, the allowable fluctuation of the electrical power is ±0.25 MW, the permissible voltage deviation is ±5,0 kV and the permissible power factor fluctuation is 1.0%.

[0045] In this embodiment, according to one implementation, in step 103, the design condition of the nuclear steam supply system includes: a thermal supply by a single nuclear unit or a supply joint thermal by a plurality of nuclear units, the nuclear steam supply system is provided with a single set of evaporators 3 or a plurality of sets of evaporators 3, among which one set of evaporators 3 serves as the main evaporator and the other evaporators 3 serve as backup evaporators.

[0046] During the performance test of the nuclear steam supply system under the design condition, the nuclear unit operates under the TMCR condition, part of the saturated steam generated by the evaporator 8 of a secondary circuit is used for electricity production, the remainder of the saturated steam is extracted and enters the heat source side of the nuclear steam supply system, and after the working fluid on the working fluid side of the nuclear steam supply system has been heated, condensed water forms and enters the condenser 5, thus enabling a heat supply to the nuclear steam supply system; the working fluid on the working fluid side of the nuclear steam supply system is heated by a heat source on the heat source side of the nuclear steam supply system to form export steam;each nuclear unit provides a thermal supply under the condition of a joint thermal supply by the plurality of nuclear units; the plurality of nuclear units jointly provide a thermal supply under the condition of a stable thermal load; the single set of evaporators 3 operates at full load under the condition of the single set of evaporators 3; and each set of evaporators 3 operates at least once at full load under the condition of the plurality of sets of evaporators 3.

[0047] Referring to [Fig. 1], during the performance test of the nuclear steam supply system, the nuclear power unit operates under the TMCR condition, and the working fluid of a secondary circuit enters the evaporator 8 of a secondary circuit after successively passing through the condenser 5, the working fluid pump of a secondary circuit 6 and the heater 7; the evaporator 8 of a secondary circuit produces saturated steam, part of the saturated steam enters the steam turbine 9, and the other part of the saturated steam enters the heat source side of the nuclear 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 steam supply system is gradually cooled into condensed water by the preheater 2, evaporator 3 and superheater 4, and the condensed water enters the condenser; the working fluid on the working fluid side of the nuclear steam supply system is gradually heated into superheated steam by the preheater 2, evaporator 3 and superheater 4, and the superheated steam is used as export steam and routed to a user.

[0048] In this embodiment, according to one implementation, in step 103, the export steam flow rate of the nuclear steam supply system during the test under the design condition is corrected according to the design condition using the following formula: [Math 1] p _ Fy^Hwg-HtJs) ^wgX - where KWgx is the steam flow rate exported from the nuclear steam supply system under the design condition, expressed in kg / h; Fwg is the steam flow rate exported from the nuclear steam supply system during the test under the design condition, expressed in kg / h; HWg is an enthalpy of the steam exported from the nuclear steam supply system at the pressure and temperature during the test under the design condition, expressed in kJ / kg; is an enthalpy of the steam exported from the nuclear steam supply system at the pressure and temperature under the design condition, expressed in kJ / kg; JfgS is an enthalpy of the feedwater of the nuclear steam supply system at the operating pressure and temperature during the test under the design condition, expressed in kJ / kg; and HgS is an enthalpy of the feedwater of the nuclear steam supply system at the pressure and temperature under the design condition, expressed in kJ / kg.

[0049] In this embodiment, according to one implementation, in step 104, the operating parameters of the nuclear unit include a main steam pressure, a main steam moisture content, a turbine exhaust steam pressure, a reactor thermal power and a generator power factor; and the power generated by the nuclear unit under the TMCR condition is corrected according to the following formula: [Math 2] where P^ is the corrected generated power of the nuclear power unit under the TMCR condition in kW units; Pnet is the generated power of the nuclear power unit under the heat supply condition in kW units; and Opms is a correction factor for the main steam pressure, 0xms is a correction factor for the main steam moisture content, 0pds is a correction factor for the turbine exhaust steam pressure, Oqnt is a correction factor for the thermal power of the reactor, and Qpp is a correction factor for the power factor of the generator.

[0050] The correction curve for the operating parameters of the nuclear production unit supplied by a nuclear production unit manufacturer includes operating parameters of the nuclear production unit and correction factors corresponding to the operating parameters of the nuclear production unit; according to the operating parameters of the nuclear production unit during the test of the nuclear steam supply system, the corresponding correction factors are sought in the correction curves for the operating parameters of the nuclear production unit supplied by a steam turbine manufacturer.

[0051] In this embodiment, according to one implementation, in step 104, the result of the test of the nuclear steam supply system includes a steam supply efficiency of the nuclear steam supply system, a heat supply efficiency of the nuclear production unit, and a power impact value of the nuclear steam supply system.

[0052] In this embodiment, according to one implementation, the steam supply efficiency of the nuclear steam supply system is calculated according to the following formula: [Math 3] _ Fwg(Hwg-Hg5)x3600 Pq-Pq where ^gq is the steam supply efficiency of the nuclear steam supply system; PWg is the export steam flow rate of the nuclear steam supply system during the test under the design condition, expressed in kg / h; HWg is the enthalpy of the export steam at the pressure and temperature during the test under the design condition, expressed in kJ / kg; HgS is the enthalpy of the feed water of the nuclear steam supply system at the pressure and temperature during the test under the design condition, expressed in kJ / kg; Pg is the corrected power generated by the nuclear unit under the TMCR condition, expressed in kW; and Pg' is the corrected power generated by the nuclear unit under the thermal supply condition, expressed in kW. In this embodiment, according to one implementation, the thermal supply efficiency of the nuclear unit is calculated using the following formula:

[0053] [Math 4] Fw^Hwg-H gs)x3600+Pe O7 ■ where V is the efficiency of the heat input of the nuclear power generation unit; FWg is an export steam flow rate of the nuclear steam feed system during the test under the design condition in a unit of kg / h; HWg is an enthalpy of the export steam at pressure and temperature during the test under the design condition in a unit of kJ / kg; Hg is an enthalpy of the feed water of the nuclear steam feed system at pressure and temperature during the test under the design condition in a unit of kJ / kg; QN is a thermal power of a nuclear island of the nuclear power generation unit under the heat supply condition in a unit of kW; and p^ is a corrected generated power of the nuclear power generation unit under the heat supply condition in a unit of kW.In this embodiment, according to one implementation, the power impact value of the nuclear steam supply system is calculated according to the following formula: [Math 5]. . _ Pp'-Pr AP = ~p “ XF wg 1 wgX where AP is the power impact value of the steam supply system nuclear; p^ ​​is a power generated corrected for the unit of nuclear power under a thermal supply condition in kW units; P^ is a power generated corrected nuclear power unit in the TMCR condition in kW units; PWgX is an export steam flow rate of the nuclear steam supply system in a design condition in kg / h units; and F Wg is an export steam flow rate of the nuclear steam supply system during the test in the design condition in kg / h units.

[0054] After the nuclear steam supply system test has been performed, an uncertainty analysis of the test result is required. The uncertainty of the test result depends on the combined effects of parameter errors and variable errors in both the nuclear steam supply system test and the nuclear power unit test.

[0055] Depending on the performance of the nuclear power unit and the nuclear steam supply system, certain variables have a greater impact on the test result, such as the main steam pressure, the main steam moisture content, the reheat steam temperature, the exhaust steam pressure, the extraction steam pressure, the extraction steam flow rate, the electrical power, the voltage and the power factor of the steam turbine, and the uncertainty of the result of the nuclear steam supply system test is controlled at ±(1.0%-1.17%).

[0056] In this embodiment, according to one implementation, the universal performance test method for the nuclear steam supply system further comprises: step 105: performing an uncertainty analysis on the result of the test of the nuclear steam supply system to ensure that the export steam flow rate of the nuclear steam supply system in the design condition test complies with a design indicator and that the result of the test of the nuclear steam supply system reaches a guaranteed value.

[0057] In this embodiment, according to one implementation, performing an uncertainty analysis on the result of the test of the nuclear steam supply system according to the uncertainty of the parameters and variables of the test for the nuclear steam supply system includes the following steps: determination of the uncertainty of each parameter, where the uncertainty of each parameter comes from the uncertainty of the instruments, the temporal uncertainty and the spatial uncertainty.

[0058] determination of the uncertainty of each variable, where the uncertainty of each variable arises from the uncertainty of each parameter involved in calculating the variable and from an influence of each parameter involved in calculating the variable on the variable; determining the uncertainty of each parameter and each variable on the test result, where the uncertainty of the variable on the test result = the uncertainty of the variable x a coefficient of influence of the variable on the test result; the uncertainty of the parameter on the test result = the uncertainty of the parameter x a coefficient of influence of the parameter on the test result; and calculation of the uncertainty of the test result according to the uncertainty of each parameter and each variable on the test result.

[0059] In this embodiment, according to one implementation, the parameters include a temperature, a pressure, a voltage and a current.

[0060] The uncertainty of the instrument is represented by the uncertainty of a measured average: [Math 6] _ U] where U| is the uncertainty of the measured mean; is the uncertainty of U i — ।— 1 1 VM the instrument, which can be obtained from an instrument calibration report; M is the number of instruments used to measure the same parameter.

[0061] In this embodiment, according to one implementation, the temporal uncertainty is represented by an estimate of the standard deviation of the measured parameter: [Math 7] 8=^(^-^)^-1) where s is an estimated standard deviation of the measured parameter; Xj is a single reading of the measured parameter; X is the average of the measured parameter; N is the number of readings of the measured parameter; The uncertainty of the average reading of a single instrument is: [Math 8] Ut = tvx(s / ^N) where Ut is the uncertainty of the mean reading of the single instrument; v is the degree of freedom, which is equal to N - 1; tv is the value of the t-distribution when the confidence level is 95% and the degree of freedom is v; in a case where a plurality of instruments of the same precision measure the same parameter, the uncertainty of the mean reading of the plurality of instruments is: [Math 9] Ut = tv X (S / ^MxN)[Math 10] s=^s|7m where Ut is the uncertainty of the mean reading of the plurality of instruments, M is the number of instruments; v is the degree of freedom, which is equal to MX (N - 1)' ct S is the mean of S calculated for each instrument reading.

[0062] In this embodiment, according to one implementation, the spatial uncertainty represents the average uncertainty caused by spatial variability: [Math 11] Us = tLx R where Us is the average uncertainty due to spatial variability; R is a numerical range, which is the difference between the maximum and minimum values ​​of the mean of the instrument readings; and is the distribution value of the substitution t, which can be obtained by consulting the table.

[0063] It should be noted that, during field measurements, the variability on certain surfaces due to the difference in position of the measurement points may in fact be due to the uncertainty of the instrument, so that the uncertainty of the instrument and the spatial uncertainty must be compared, and the greater one must be taken to determine the total uncertainty.

[0064] In this embodiment, according to one implementation, the uncertainty of the parameter is: [Math 12] TT CT 7 7~l 7 ~ t where UP is the uncertainty of the parameter; UDb is Up = ^UPt + (UPI or UPS) F pt the temporal uncertainty of the parameter, Upj is the instrumental uncertainty of the parameter, and Upg is the spatial uncertainty of the parameter.

[0065] In this embodiment, according to one implementation, the variables that affect the result of the test are calculated from the measured values ​​of the parameter, and the variables include a flow rate and an electrical power;

[0066] The uncertainty of the variables is: [Math 13] TT = f^TT P" ur dp, upi / where Up is the uncertainty of the variable; dTL is an influence coefficient of the variable R ôPj varying with Pj.

[0067] In this embodiment, according to one implementation, the uncertainty of the flow rate is: [Math 14] Uw = Uw is the uncertainty of the flow rate, Ud is the uncertainty of an opening diameter of a flow device, Uk is the uncertainty of a flow coefficient, U^p is the uncertainty of a differential flow pressure, and Up is the uncertainty of the relative density.

[0068] In this embodiment, according to one implementation, the uncertainty of the power is:

[0069] [Math 15] U = 2 + U 2 °where is the uncertainty of the power, Uj is the uncertainty of the current measurement, and Uy is the uncertainty of the voltage measurement. In this implementation, according to one method, the square root of the sum of The squares of the uncertainty of each parameter and each variable on the result of the test is taken as the uncertainty of the result of the test.

[0070] According to the universal performance test method for the nuclear steam supply system in this embodiment, relevant performance test measurement points are reasonably arranged in the nuclear power unit and the nuclear steam supply system. The steam supply efficiency of the nuclear steam supply system, the heat supply efficiency of the nuclear power unit, and the power impact value of the nuclear steam supply system are measured and calculated. The economics of the nuclear steam supply system can be effectively evaluated, and the The level of operational economy of the nuclear steam supply system is objectively reflected.

[0071] According to the universal performance test method for the nuclear steam supply system in this embodiment, based on the power generated by the nuclear power unit under the TMCR condition, the corrected power generated by the nuclear power unit under the heat supply condition, and the steam flow rate exported from the nuclear steam supply system under the design condition, the power impact value of the nuclear steam supply system is accurately corrected, with high technical operability. It is not necessary to correct the entire nuclear steam supply system, which simplifies the mutual interference of the various equipment operating during the test of the nuclear steam supply system and improves the accuracy of the test results for the nuclear steam supply system.

[0072] The universal performance test method for the nuclear steam supply system in this embodiment, as a complement to the performance test standard for the nuclear steam supply system, enables the performance test of the nuclear steam supply system to be more equitable and accurate, measures and calculates in real time the steam supply efficiency of the nuclear steam supply system, the heat supply efficiency of the nuclear power unit and the power impact value of the nuclear steam supply system, effectively evaluates the design integrity of the nuclear steam supply system, and objectively assesses the degree of energy utilization of the nuclear steam supply system.

[0073] The preceding embodiments merely illustrate certain implementations of this disclosure, and their description is relatively specific and detailed, but should not be interpreted as a limitation of the scope of patent protection of this disclosure. It should be noted that ordinary people in the technical field may make certain variations and improvements without departing from the idea of ​​this disclosure, and such improvements and refinements fall within the scope of protection of this disclosure. Therefore, the scope of protection of this disclosure should be limited to the following claims.

Claims

1.

2. Demands A universal performance test method for a nuclear steam supply system, comprising the following steps: step 101: determine a boundary of the nuclear steam supply system, and arrange the performance test measurement points of a nuclear power unit and the nuclear steam supply system; Step 102: Perform a performance test on the nuclear power unit under a TMCR condition to obtain a power generated by the nuclear power unit under the TMCR condition; Step 103: Perform a performance test on the nuclear steam supply system under a design condition based on the power generated by the nuclear power unit under the TMCR condition to obtain a steam export flow rate from the nuclear steam supply system during the test under the design condition; and correct the steam export flow rate from the nuclear steam supply system during the test under the design condition to the design condition;and step 104: correct the power generated by the nuclear power unit in the TMCR condition according to the operating parameters of the nuclear power unit during a test of the nuclear steam supply system, and calculate a test result of the nuclear steam supply system. The performance test method for the nuclear steam supply system according to claim 1, wherein, 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) being connected sequentially to form a closed-loop passage for the circulation of a secondary circuit working fluid, the steam turbine (9) being connected to the generator (10), and the generator (10) converting the mechanical energy of the steam turbine (9) into electrical energy; and the performance test measurement points of the nuclear power unit are arranged as

3.

4. The following is provided: a temperature measurement point, a pressure measurement point and a flow measurement point are arranged at a working fluid inlet of the evaporator of a secondary circuit, a temperature measurement point and a pressure measurement point are arranged at a working fluid outlet of the evaporator of a secondary circuit, a pressure measurement point is arranged at an inlet of the steam turbine, a pressure measurement point is arranged in the condenser, and an electrical energy measurement point is arranged on the generator. The performance test method of the nuclear steam supply system according to claim 1, wherein, in step 101, the nuclear steam supply system comprises: a water supply pump (1), a heater (2), an evaporator (3) and a superheater (4), the water supply pump (1), a working fluid side of the preheater (2), a working fluid side of the evaporator (3) and a working fluid side of the superheater (4) being sequentially connected to form a working fluid side of the nuclear steam supply system, and a heat source side of the preheater (2), a heat source side of the evaporator (3) and a heat source side of the superheater (4) being sequentially connected to form a heat source side of the nuclear steam supply system;and the performance measurement points of the nuclear steam supply system are arranged as follows: a temperature measurement point, a pressure measurement point and a flow measurement point are arranged at each of an inlet and an outlet on the working fluid side of the nuclear steam supply system, a pressure measurement point and a flow measurement point are arranged at an inlet on the heat source side of the nuclear steam supply system, and a pressure measurement point, a flow measurement point and a temperature measurement point are arranged at an outlet on the heat source side of the nuclear steam supply system. The performance test method for the nuclear steam supply system according to claim 1, wherein the performance test is performed on the nuclear power unit under the TMCR condition to obtain the power generated by the unit nuclear power in the TMCR condition in step 102 includes the following steps: setting a state of the nuclear power unit according to a steam turbine performance test requirement, and determining that the steam turbine operating parameters meet a stability requirement; and measuring the power generated by the nuclear power unit in the TMCR condition, in which the nuclear power unit operates according to the TMCR condition during the performance test of the nuclear steam supply system.

5. The performance test method for the nuclear steam supply system according to claim 1, wherein, in step 103, the design condition of the nuclear steam supply system includes: heat supply by a single nuclear power unit or joint heat supply by a plurality of nuclear power units, the nuclear steam supply system is equipped with a single set of evaporators (3) or a plurality of sets of evaporators (3), and among the plurality of sets of evaporators (3), one set of evaporators serves as the main evaporator (3) and the other evaporators serve as backup evaporators (3);and the nuclear power unit operates according to the TMCR condition during the performance test of the nuclear steam supply system under the design condition, each nuclear power unit provides heat in a condition of joint heat supply by the plurality of nuclear power units, the plurality of nuclear power units jointly provide heat in a stable thermal load condition; the single set of evaporators (3) operates at full load in a condition of the single set of evaporators (3); and each set of evaporators (3) operates at least once at full load in a condition of the plurality of sets of evaporators (3).;

6. The performance test method for the nuclear steam supply system according to claim 1, wherein, in step 103, the export steam flow rate of the nuclear steam supply system during the test under the design condition is corrected under the design condition according to the following formula:

7. [Math 1] p _ F (¾¾) where FWgx is the export steam flow rate of the nuclear steam supply system under the design condition in a unit of kg / h; FWg is the export steam flow rate of the steam supply system during the test under the design condition in a unit of kg / h; HWg is an export vapor enthalpy of the nuclear steam supply system at the pressure and temperature during the test under the design condition in a unit of kJ / kg; is an export vapor enthalpy of the nuclear steam supply system at the pressure and temperature under the design condition in a unit of kJ / kg; Hgs is an enthalpy of the feedwater of the nuclear steam supply system at the operating pressure and temperature during the test under the design condition in a unit of kJ / kg; and HgS is an enthalpy of the feedwater of the nuclear steam supply system at the pressure and temperature under the design condition in a unit of kJ / kg. The performance test method for the nuclear steam supply system according to claim 1, wherein, in step 104, the operating parameters of the nuclear power generating unit include a main steam pressure, a main steam moisture content, a turbine exhaust steam pressure, a reactor thermal power and a generator power factor; and the power generated by the nuclear power generating unit under the TMCR condition is corrected according to the following formula: [Math 2] where Pg is the corrected generated power of the nuclear power generation unit under the TMCR condition in kW units; Puei is the generated power of the power generation unit nuclear under a thermal feed condition in units of kW; and Opms is a main steam pressure correction factor, 0xms is a main steam moisture content correction factor, Opds is a turbine exhaust steam pressure correction factor, 9qnt is a reactor thermal power correction factor, and 3pp is a generator power factor correction factor.

8. The performance test method for the nuclear steam supply system according to claim 1, wherein, in step 104, the result of the test of the nuclear steam supply system includes a steam supply efficiency of the nuclear steam supply system, a heat supply efficiency of the nuclear power unit and a power impact value of the nuclear steam supply system.

9. The performance test method for the nuclear steam supply system according to claim 8, wherein the steam supply efficiency of the nuclear steam supply system is calculated according to the following formula: [Math 3] _ FwdHwg-Hgs)x3600 where Hgq is the steam supply efficiency of the nuclear steam supply system; FWg is the flow rate of steam exported from the nuclear steam supply system during the test under the design condition in a unit of kg / h; HWg is the enthalpy of the exported steam at pressure and temperature during the test under the design condition in a unit of kJ / kg; HgS is the enthalpy of the feed water of the nuclear steam supply system at pressure and temperature during the test under the design condition in a unit of kJ / kg;Pq is a corrected generated power of the nuclear unit under the TMCR condition in a unit of kW; and p& is a corrected generated power of the nuclear unit under a thermal supply condition in a unit of kW.

10. The performance test method for the nuclear steam supply system according to claim 8, wherein the heat supply efficiency of the nuclear unit is calculated according to the following formula: [Math 4] Pwq(Hv:g~Hgs)x3 6 0O+jPq ' where is the heat supply efficiency of the nuclear unit; Pwg is an export steam flow rate of the nuclear steam supply system during the test under the design condition in units of kg / h; JfWg is an export steam enthalpy at pressure and temperature during the test under the design condition in units of kJ / kg; JigS is an enthalpy of feed water of the nuclear steam supply system at pressure and temperature during the test under the design condition in units of kJ / kg; Q^ is a thermal power of a nuclear island of the nuclear unit under the heat supply condition in units of kW;and is a corrected generated power of the nuclear unit under the heat supply condition in kW units.

11. The performance test method for the nuclear steam supply system according to claim 8, wherein the power impact value of the nuclear steam supply system is calculated according to the following formula: [Math 5] = ~ p 1 wgX J where AP is the power impact value of the nuclear steam supply system; Pq is a power generated from the nuclear power unit under a thermal supply condition in one unit of kW; Pg is a corrected power generated from the nuclear power unit under the TMCR condition in one unit of kW; FWgx is an export steam flow rate of the nuclear steam supply system under the design condition in one unit of kg / h; and Pwg is an export steam flow rate of the nuclear steam supply system during the test under the design condition in one unit of kg / h.

12. The nuclear steam supply system performance test method according to claim 1, further comprising: step 105: performing an uncertainty analysis on the result of the nuclear steam supply system test to ensure that the steam flow rate exported from the nuclear steam supply system during the test under the design condition meets a design indicator and that the result of the nuclear steam supply system test reaches a guaranteed value.

13. The method for testing the performance of the nuclear steam supply system according to claim 12, wherein the performance of an uncertainty analysis on the result of the test of the nuclear steam supply system according to the uncertainty of the parameters and variables of the test for the nuclear steam supply system comprises the following steps: determining the uncertainty of each parameter, the uncertainty of each parameter arising from the uncertainty of the instrument, the temporal uncertainty and the spatial uncertainty; determining the uncertainty of each variable, the uncertainty of each variable arising from the uncertainty of each parameter participating in the calculation of the variable and the influence of each parameter participating in the calculation of the variable on the variable;Determine the uncertainty of each parameter and each variable on the test result; the uncertainty of the variable on the test result = the uncertainty of the variable x a coefficient of influence of the variable on the test result; the uncertainty of the parameter on the test result = the uncertainty of the parameter x a coefficient of influence of the parameter on the test result; and calculate the uncertainty of the test result according to the uncertainty of each parameter and each variable on the test result.

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