CN111737856A - Method for calculating rotating speed of variable-frequency water feeding pump of nuclear power plant - Google Patents
Method for calculating rotating speed of variable-frequency water feeding pump of nuclear power plant Download PDFInfo
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- CN111737856A CN111737856A CN202010447639.XA CN202010447639A CN111737856A CN 111737856 A CN111737856 A CN 111737856A CN 202010447639 A CN202010447639 A CN 202010447639A CN 111737856 A CN111737856 A CN 111737856A
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Abstract
The invention relates to a method for calculating the rotating speed of a variable-frequency water feeding pump of a nuclear power plant, which comprises the following steps: according to the pump head characteristic curve fitting function, obtaining a relation between a pump steady-state pressure head and a normalized rotating speed of the water feeding pump at a certain flow rate; and finally, solving to obtain the normalized rotating speed which the feed pump should reach under the flow through a steady pressure head balance equation. The method is simple and easy to use, and can quickly calculate the rotating speed of the variable-speed feed pump to ensure the displacement under different load working conditions and different configuration quantities.
Description
Technical Field
The invention relates to calculation of the rotating speed of a main water feeding pump in a main water feeding system of a nuclear power station, in particular to a method for calculating the rotating speed of a variable-frequency water feeding pump of a nuclear power plant.
Background
A main water supply system of a nuclear power station provides qualified main water for a steam generator of a nuclear island, and is an important system of a conventional island of the nuclear power station, and a main water supply pump is the core of the system and plays an important role in safe, stable and economic operation of the nuclear power station.
Generally, for verifying the design of a water supply system, the variation conditions of parameters such as the flow rate and the rotating speed of a main water supply system of a unit under different transient working conditions need to be accurately obtained, the rotating speeds of water supply pumps under different flow rates to ensure the discharge capacity are calculated, the data can provide a basis for selecting the number of the configuration variable-speed water supply pumps of the water supply system of the nuclear power plant, can provide a necessary input basis for the design and safety analysis of a water supply control system and a loop control system of a nuclear island, and ensure the safe and stable operation after the nuclear power plant is put into operation. The method generally adopted is as follows: and establishing a nuclear power device simulation system, carrying out comprehensive steady-state or transient calculation on the water supply system through system simulation research, and finally verifying through a debugging test of the actual nuclear power device.
However, the nuclear power plant simulation system has long development period, great difficulty and high cost, and influences the iterative design of a water supply system and related systems, thereby influencing the overall design progress of the nuclear power plant.
Therefore, it is necessary to provide a simple and easy-to-use method for calculating the rotating speed of the variable-speed feed pump under different load conditions and different configuration quantities to ensure the displacement.
Disclosure of Invention
The invention aims to overcome the defects of the prior art and provides a method for calculating the rotating speed of a variable-frequency water-feeding pump of a nuclear power plant, which is simple and easy to use and can quickly calculate the rotating speed of the variable-frequency water-feeding pump which is required to ensure the discharge capacity under different load working conditions and different configuration quantities.
The technical scheme adopted for realizing the aim of the invention is a method for calculating the rotating speed of a variable-frequency water feeding pump of a nuclear power plant, which comprises the following steps:
according to the pump head characteristic curve fitting function, obtaining a relation between a pump steady-state pressure head and a normalized rotating speed of the water feeding pump at a certain flow rate;
and finally, solving to obtain the normalized rotating speed which the feed pump should reach under the flow through a steady pressure head balance equation.
The method can calculate the rotating speed of the water feeding pump under different flow rates, so that the following data requirements can be provided: on one hand, the method provides a basis for selecting the number of the configuration variable-speed feed pumps of the water supply system of the nuclear power plant, on the other hand, the method can accurately obtain the change condition of the rotation speed of the water supply pump of the main water supply system under different flow rates when the unit is under some transient working conditions (such as pump tripping event of the water supply pump and load shedding to service power), provide design guidance for optimizing and selecting the operation mode and the operation parameters, and also provide a necessary input basis for the design and safety analysis of a water supply control system and a loop control system of a nuclear island.
Drawings
FIG. 1 is a flow chart of a method for calculating the rotating speed of a variable-frequency water-feeding pump of a nuclear power plant.
Detailed Description
The invention is described in further detail below with reference to the figures and the specific embodiments.
As shown in figure 1, the technical scheme adopted for realizing the purpose of the invention is a method for calculating the rotating speed of a variable-frequency water feeding pump of a nuclear power plant, which comprises the following steps:
and S1, obtaining a relation between the steady-state pressure head and the normalized rotating speed of the water supply pump at a certain flow rate according to the pump head characteristic curve fitting function.
The relation between the steady-state pressure head and the normalized rotating speed of the water-feeding pump under a certain flow rate is as follows:
ΔP＝k0·α2+k1·G·α+k2G2(1)
in formula (1):
delta P-steady state head of feed pump, MPa;
g is mass flow rate, t/h;
k0、k1、k2-fitting coefficients;
α is the normalized feed pump speed,
n is the actual rotating speed of the pump, r/min; n is0The rated rotation speed of the pump is r/min.
According to the pump flow and lift characteristic curve, performing second-order curve fitting on the steady-state head-flow of the pump by adopting a least square method, and obtaining the pressure head-flow through the equation of delta P-k0+k1·G+k2G2Fitting is carried out to obtain a fitting coefficient k0、k1、k2。
S2, obtaining the steady state pressure head which the feed pump should reach at the flow rate.
The steady state head that the feed pump should achieve at this flow rate is calculated by:
ΔP'＝ΔPξ+PSG-PDE+(ΔPV+ΔPH+ΔPHP) (2)
in formula (2):
delta P' -the steady state pressure head, MPa, that the feed pump should reach;
PSG-steam generator pressure, MPa;
ΔPV-setting a pressure difference, MPa, of the water supply regulating valve;
ΔPHthe water level pressure difference between the steam generator and the deaerator is MPa;
ΔPHP-resistance loss of high pressure feedwater heater, MPa;
PDE-operating pressure of the deaerator, MPa;
ΔPξ-loss of feed line pressure;
wherein, PSG＝f1(G) Wherein f is1() Third order or third order obtained for fitting static characteristic dataOrder of the above expression;
ΔPHcalculated by the following formula (3):
ΔPH＝ρg(HSG-HDE) (3)
in formula (3):
HSG-steam generator elevation, m;
HDE-deaerator elevation, m;
ρ is the fluid density.
Pressure loss delta P of water supply pipelineξObtained by the following formula (4):
in the formula (4), the reaction mixture is,
zeta is the water supply pipeline resistance coefficient;
ΔPξ-pipe pressure loss, MPa;
rho-fluid density, kg/m3；
A-flow area, m3；
Wherein the feed water pipe resistance coefficient ζ is obtained by the following formula (5):
in formula (5):
ζ -coefficient of resistance of the pipeline;
xi-local drag coefficient;
λ -pipe friction coefficient;
l-total deployed length of pipe (including attachment length), m;
d-inner diameter of the tube, m;
wherein λ is a pipe friction coefficient obtained by the following formula (6):
in formula (6):
η -dynamic viscosity of the fluid, kg/(m.s).
And S3, finally, solving to obtain the normalized rotating speed which the feed water pump should reach at the flow rate through a steady state pressure head balance equation delta P ═ delta P'.
And substituting the water supply flow into a steady state pressure head balance equation, solving and calculating through the equation to obtain a normalized rotating speed alpha, and obtaining the rotating speed of the water supply pump after the flow changes according to the calculation result.
Next, the present embodiment calculates data of the normalized rotation speed α of the feed pump in an actual environment by the above method.
The present embodiment is based on the following assumptions: the feed water density at the inlet of the feed water pump is substantially constant and the steady state head characteristic of the feed water pump can be fitted as a function of the normalized rotational speed and the mass flow rate of the pump.
In the embodiment, the water supply system is provided with three water supply pumps, the rated flow of a single pump is 56t/h, and the rated lift is 500mH2O, rated rotation speed 2975r/min, and obtaining a fitting coefficient k by fitting according to a performance curve of the feed pump by adopting a least square method0＝5.99、k17.52E-03 and k2＝3.1E-04。
When the total water supply flow is 160t/h and the three water supply pumps normally operate, the pressure of the steam generator can be 3.9MPa according to the static characteristic relational expression of the steam generator; calculating according to the pressure loss of the pipeline to obtain the pressure loss of the pipeline to be 0.3 MPa; the differential pressure of the feed water regulating valve is set to be 0.3MPa, the differential pressure of the water level in the steam generator and the deaerator is 0.02MPa, the resistance loss of the high-pressure feed water heater is 0.04MPa, and the working pressure of the deaerator is 0.25 MPa. According to the data, the steady state pressure head delta P' which the feed pump should reach is 4.36MPa under the feed water flow.
And solving a steady-state pressure head balance equation to obtain the normalized rotating speed of the single pump under the flow rate of 0.969.
It will be understood by those skilled in the art that the foregoing is only a preferred embodiment of the present invention, and is not intended to limit the invention, and that any modification, equivalent replacement, or improvement made within the spirit and principle of the present invention should be included in the scope of the present invention.
Details not described in the present specification belong to the prior art known to those skilled in the art.
Claims (6)
1. A method for calculating the rotating speed of a variable-frequency water feeding pump of a nuclear power plant is characterized by comprising the following steps of:
according to the pump head characteristic curve fitting function, obtaining a relation between a pump steady-state pressure head and a normalized rotating speed of the water feeding pump at a certain flow rate;
and finally, solving to obtain the normalized rotating speed which the feed pump should reach under the flow through a steady pressure head balance equation.
2. The method for calculating the rotating speed of the variable-frequency water feeding pump of the nuclear power plant as claimed in claim 1, wherein the relation between the steady-state pressure head and the normalized rotating speed of the pump under a certain flow rate of the water feeding pump is obtained as follows:
ΔP＝k0·α2+k1·G·α+k2G2
in the formula: delta P is the steady state pressure head of the feed pump; k is a radical of0、k1、k2is a fitting coefficient, α is the normalized feed pump rotating speed,
n is the actual pump speed, n0Rated speed of the pump; g is the mass flow.
3. The method for calculating the rotating speed of the variable-frequency water feeding pump of the nuclear power plant as claimed in claim 2, wherein the method comprises the following steps: according to the pump flow and lift characteristic curve, performing second-order curve fitting on the steady-state pressure head-flow of the pump by adopting a least square method, wherein the second-order curve fitting is performed by using a delta P (k) value0+k1·G+k2G2Fitting is carried out to obtain a fitting coefficient k0、k1、k2。
4. The method for calculating the rotating speed of the variable-frequency water feeding pump of the nuclear power plant as claimed in claim 1, wherein the steady-state pressure head which the water feeding pump should reach at the flow rate is obtained by calculating according to the following formula:
ΔP'＝ΔPξ+PSG-PDE+(ΔPV+ΔPH+ΔPHP)
in the formula: delta P' is the steady state pressure head that the feed pump should reach; delta PξIs the pressure loss of the water supply pipeline; pSGIs the steam generator pressure; delta PVSetting a pressure difference for the feed water regulating valve; delta PHThe water level pressure difference between the steam generator and the deaerator; delta PHPResistance loss for high pressure feedwater heaters; pDEThe working pressure of the deaerator;
wherein: pSG＝f1(G)，f1() The static characteristic data is fitted to obtain a third order or more expression;
ΔPH＝ρg(HSG-HDE)，HSGis the elevation of the steam generator; hDEIs the deaerator elevation, and rho is the fluid density.
5. The method for calculating the rotating speed of the variable-frequency water feeding pump of the nuclear power plant as claimed in claim 4, wherein the pressure loss of the water feeding pipeline is obtained by the following formula:
in the formula,. DELTA.PξZeta is the water supply pipeline resistance coefficient, ρ is the fluid density, and A is the flow area for pipeline pressure loss.
6. The method for calculating the rotating speed of the variable-frequency water feeding pump of the nuclear power plant as claimed in claim 4, wherein the resistance coefficient ζ of the water feeding pipeline is obtained by the following formula:
in the formula: zeta is the resistance coefficient of the pipeline, xi is the local resistance coefficient, lambda is the friction coefficient of the pipeline, L is the total expansion length of the pipeline, and D is the inner diameter of the pipe;
wherein,
in the formula:
eta-the dynamic viscosity of the fluid.
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN113719334A (en) * | 2021-08-13 | 2021-11-30 | 义乌吉利动力总成有限公司 | Method for determining variable displacement engine oil pump control strategy |
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Application publication date: 20201002 |