CN109002741B - Method and system for simulating transmission power of primary and secondary loop systems of pressurized water reactor nuclear motor unit - Google Patents
Method and system for simulating transmission power of primary and secondary loop systems of pressurized water reactor nuclear motor unit Download PDFInfo
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Abstract
The invention discloses a method and a system for simulating the transmission power of a first loop system and a second loop system of a pressurized water reactor nuclear motor unit, wherein the method comprises the following steps: initializing parameters of the pressurized water reactor nuclear power unit; obtaining the step electric quantity data according to a preset rule; solving a primary loop system model and a secondary loop system model of the pressurized water reactor nuclear power unit to obtain calculation parameters; calculating final valve output power in the pressurized water reactor nuclear power system model by using the calculation parameters, and outputting the final valve output power, namely, the power transmitted by a first loop system and a second loop system of the pressurized water reactor nuclear power system; according to the method and the system, the specific enthalpy of main steam and water supply is fitted, the heat efficiency of the side-discharge unit and the unit heat efficiency are considered, and the enthalpy drop method in unit time is calculated, so that the problem that the transmission power of a first loop system and a second loop system of a nuclear power unit model in the existing power system is difficult to calculate accurately is solved, and the simulation precision of the nuclear power model is improved.
Description
Technical Field
The invention relates to the field of power systems, in particular to a method and a system for simulating transmission power of a first loop system and a second loop system of a pressurized water reactor nuclear power unit.
Background
Currently, the nuclear power in China is rapidly developed, the capacity of the nuclear power in China in a shipping installation is 5800 kilowatts by 2020, the capacity in the shipping installation is 3000 kilowatts, and the nuclear power installation ratio is increased from 1% in 2015 to 5% in 2020. With the increasing proportion of nuclear power in a power system, particularly with the gradual commissioning of large nuclear power bases in eastern coastal areas, many new problems will occur in the operation of the power grid. Because nuclear safety and power grid safety have significant social political effects, dynamic characteristics of the nuclear power unit after being connected to the power grid must be studied deeply, and safe and stable operation of the nuclear power unit and the power grid is ensured.
The pressurized water reactor nuclear power unit used as main stream nuclear power in China can be divided into two mutually isolated parts according to the principle, namely a primary loop system for producing steam by nuclear fission and a secondary loop system for pushing a steam turbine to do work and generate power by saturated wet steam. Wherein, the primary part of the primary loop is the nuclear power unit different from the conventional unit; the two-loop system has the same function as the conventional unit, but has the characteristics of low main steam parameter, small enthalpy drop, high humidity and flow rate and the like. In order to accurately reflect the dynamic characteristics of the nuclear power unit under disturbance, a detailed mathematical model of the transfer power between the first loop system and the second loop system needs to be established.
However, a nuclear power unit model for power grid stability simulation mainly focuses on modeling research of a primary loop system, and two modes exist for modeling of a secondary loop system. One of the modes is to accurately model according to the thermodynamic principle, but the model is too complex, the calculated amount is too large, and the model is difficult to be practically applied to a simulation program of a power system especially when nuclear power occupies a certain proportion in a power grid. The other mode is also the current mainstream mode, and is based on a thermal power unit model, modeling is carried out by adopting a mode of actually measuring parameters, and even the thermal power unit model is directly adopted for replacement. Because the power transfer characteristics between the first loop system and the second loop system cannot be considered, the errors of the models are large, and the dynamic characteristics of an actual unit are difficult to accurately reflect.
Disclosure of Invention
In order to solve the problem that the existing simulation model of the pressurized water reactor nuclear power unit cannot completely simulate the characteristics of the nuclear power unit and fails to consider the power transmission between a first loop system and a second loop system so as to cause larger simulation error, the invention provides a method and a system for simulating the transmission power of the first loop system and the second loop system of the pressurized water reactor nuclear power unit; the method and the system realize the accurate simulation of the transfer power between the nuclear steam supply system and the prime mover by fitting the specific enthalpy of the saturated wet steam of the nuclear steam turbine, taking the heat efficiency of the side-discharge unit and the unit into consideration and adopting a method for calculating the enthalpy drop in unit time, and the method for simulating the transfer power of the first loop system and the second loop system of the pressurized water reactor nuclear power unit comprises the following steps:
initializing parameters of the pressurized water reactor nuclear power unit;
Obtaining the step electric quantity data according to a preset rule;
Solving a primary loop system model and a secondary loop system model of the pressurized water reactor nuclear power unit to obtain calculation parameters; the calculated parameters comprise the steam temperature T s at the side of a second loop of the steam generator, the effective steam demand coefficient k se of the steam turbine and the steam flow f stm2 of a side-exhaust system of the steam turbine;
Calculating final valve output power in the pressurized water reactor nuclear power system model by using the calculation parameters;
Further, calculating final valve output power in the pressurized water reactor nuclear power system model by using the calculation parameters, wherein the calculating comprises calculating specific enthalpy of steam, specific enthalpy of feedwater and total steam flow in corresponding step sizes according to the calculation parameters;
further, the method for calculating the specific enthalpy of steam comprises the following steps:
Obtaining the steam temperature T s of the secondary loop side of the steam generator in the secondary loop system model of the pressurized water reactor nuclear power unit in the calculated parameters;
fitting the change relation between the main steam specific enthalpy and the temperature of the nuclear turbine, and obtaining a fitting coefficient k 0、k1、k2、k3;
Calculating the steam specific enthalpy value h s according to the temperature; meanwhile, considering the pressure factor, the calculation formula is as follows:
further, the calculation method of the total steam flow comprises the following steps:
Obtaining a steam turbine rated main steam flow f stmn, a steam turbine effective steam demand coefficient k se and a steam turbine side-exhaust system steam flow f stm2 in a two-loop system model of the pressurized water reactor nuclear power unit in the calculation function;
Calculating the main steam flow f stm1 of the steam turbine; the calculation method of the main steam flow is f stm1＝ksefstmn;
calculating an actual total steam flow f stm, wherein the total steam flow f stm is the sum of the main steam flow of the steam turbine and the steam flow of the side-by-side exhaust system;
further, the method for calculating the specific enthalpy of the water supply comprises the following steps:
Obtaining a total steam flow f stm;
Fitting the water supply specific enthalpy h w of the secondary loop side of the steam generator in a sectional mode, and calculating to obtain a fitting coefficient k 4、k5;
The specific enthalpy h w of the water supply at the second loop side of the steam generator is calculated, and the calculation mode of the specific enthalpy of the water supply at the second loop side of the steam generator is as follows: h w＝k4+k5fstm;
According to the water supply specific enthalpy of the second loop side of the steam generator, calculating the actual water supply specific enthalpy h in which is sent to the steam generator to participate in the calculation of the second loop through an inertia link, wherein the actual water supply specific enthalpy h in is as follows:
Further, the method for calculating the final valve output power includes:
Obtaining the thermal efficiency eta of the two loops according to the power of the two loops of the last step in the electrical quantity data of the step and the thermal equilibrium diagram of the unit;
Obtaining steam specific enthalpy h s, water supply specific enthalpy h in, main steam flow f stm1 of the steam turbine and rated power P M0 of the steam turbine of the second loop;
The calculation formula of the final valve output power P GV is as follows:
Further, the calculation parameters are obtained by carrying out cross iteration solution on the first loop system model and the second loop system model;
Further, the electrical quantity data of the step length is obtained by calculating parameters including calculation parameters and final valve output power parameters in the previous step length according to a set numerical integration algorithm; and solving the primary loop system model and the secondary loop system model of the pressurized water reactor nuclear power unit according to the electric quantity data of the step length.
The first loop system and the second loop system transfer power simulation system of the pressurized water reactor nuclear power unit comprise:
The initialization unit is used for initializing and setting parameters of the pressurized water reactor nuclear power unit;
the electrical quantity data calculation unit calculates electrical quantity data of the step length according to a preset rule;
The model calculation unit is used for solving a primary loop system model and a secondary loop system model of the pressurized water reactor nuclear power unit to obtain calculation parameters; the calculated parameters comprise the steam temperature T s at the side of a second loop of the steam generator, the effective steam demand coefficient k se of the steam turbine and the steam flow f stm2 of a side-exhaust system of the steam turbine;
The comprehensive calculation unit is used for calculating the final valve output power in the pressurized water reactor nuclear power system model by utilizing the calculation parameters output by the model calculation unit;
Further, the comprehensive calculation unit is used for calculating the steam specific enthalpy, the water supply specific enthalpy and the total steam flow in the corresponding step length according to the calculation parameters;
further, the comprehensive calculation unit is used for calculating the specific vapor enthalpy;
The comprehensive calculation unit fits the change relation between the main steam specific enthalpy and the temperature of the nuclear turbine according to the steam temperature T s at the secondary loop side of the steam generator in the secondary loop system model of the pressurized water reactor nuclear power unit in the calculation parameters, and obtains a fitting coefficient k 0、k1、k2、k3;
The comprehensive calculation unit calculates the steam specific enthalpy value h s according to the temperature; the calculation formula is as follows:
Further, the comprehensive calculation unit is used for calculating the total steam flow;
the comprehensive calculation unit calculates the main steam flow f stm1 of the steam turbine according to the rated main steam flow f stmn of the steam turbine, the effective steam demand coefficient k se of the steam turbine and the steam flow f stm2 of a side-exhaust system of the steam turbine in the two-loop system model of the pressurized water reactor nuclear power unit in the calculation function; the calculation method of the main steam flow is f stm1＝ksefstmn;
The comprehensive calculation unit is used for calculating the actual total steam flow f stm, and the total steam flow f stm is the sum of the main steam flow of the steam turbine and the steam flow of the side-exhaust system;
further, the comprehensive calculation unit is used for calculating the specific enthalpy of the water supply;
The comprehensive calculation unit obtains the main steam flow f stm, fits the water supply specific enthalpy h w of the two loops of the steam generator in a sectional mode, and calculates a fitting coefficient k 4、k5;
The comprehensive calculation unit is used for calculating the water supply specific enthalpy h w of the second loop side of the steam generator, and the calculation mode of the water supply specific enthalpy of the second loop side of the steam generator is as follows: h w＝k4+k5fstm;
the comprehensive calculation unit calculates the actual water supply specific enthalpy h in which is sent to the steam generator to participate in the two-loop calculation through an inertia link according to the water supply specific enthalpy at the two-loop side of the steam generator, and the actual water supply specific enthalpy h in is as follows:
Further, the comprehensive calculation unit is used for obtaining the thermal efficiency eta of the two loops according to the power of the two loops of the last step in the electrical quantity data of the step and the thermal equilibrium diagram of the unit;
The comprehensive calculation unit is used for calculating the final valve output power P GV; the calculation formula of the final valve output power P GV is as follows:
Wherein h s is steam specific enthalpy, h in is water specific enthalpy, f stm1 is main steam flow of the steam turbine, and P M0 is rated power of the steam turbine;
further, the model calculation unit obtains calculation parameters by performing cross iteration solution on the first loop system model and the second loop system model;
Further, the electrical quantity data calculation unit calculates and obtains electrical quantity data of the step length according to a set numerical integration algorithm through parameters including calculation parameters and final valve output power in the last step length;
and the model calculation unit solves a first loop system model and a second loop system model of the pressurized water reactor nuclear power unit through the electric quantity data of the step length.
The beneficial effects of the invention are as follows: according to the technical scheme, the method and the system for simulating the transmission power of the first loop system and the second loop system of the pressurized water reactor nuclear power unit are provided, by fitting the specific enthalpy of main steam and water supply to the saturated wet steam of a nuclear turbine, considering the heat efficiency of the side discharge and the unit, adopting a method for calculating enthalpy drop in unit time, realizing accurate simulation of the transmission power between a nuclear steam supply system and a prime motor, more accurately reflecting the dynamic process of power change between the first loop and the second loop of the nuclear power unit, overcoming the difficulty of overlarge dynamic errors of a model caused by the conventional method for calculating the inlet power of a thermal power turbine for simple application, solving the problem that the transmission power of the first loop system and the second loop system of the nuclear power unit is difficult to accurately calculate in the stable calculation of the conventional power system, improving the simulation precision of the nuclear power model, and providing technical support for researching the mutual influence and coordination control between the nuclear power unit and a power grid.
Drawings
Exemplary embodiments of the present invention may be more completely understood in consideration of the following drawings:
FIG. 1 is a flow chart of a method for simulating the power transmitted by a first loop system and a second loop system of a pressurized water reactor nuclear motor unit according to an embodiment of the invention;
fig. 2 is a block diagram of a power transmission simulation system of a first loop system and a second loop system of a pressurized water reactor nuclear motor unit according to an embodiment of the present invention.
Detailed Description
The exemplary embodiments of the present invention will now be described with reference to the accompanying drawings, however, the present invention may be embodied in many different forms and is not limited to the examples described herein, which are provided to fully and completely disclose the present invention and fully convey the scope of the invention to those skilled in the art. The terminology used in the exemplary embodiments illustrated in the accompanying drawings is not intended to be limiting of the invention. In the drawings, like elements/components are referred to by like reference numerals.
Unless otherwise indicated, terms (including technical and scientific terms) used herein have the same meaning as commonly understood by one of ordinary skill in the art. In addition, it will be understood that terms defined in commonly used dictionaries should be interpreted as having a meaning that is consistent with their meaning in the context of the relevant art and will not be interpreted in an idealized or overly formal sense.
FIG. 1 is a flow chart of a method for simulating the power transmitted by a first and a second loop systems of a pressurized water reactor nuclear motor unit according to an embodiment of the invention; the method realizes accurate simulation of the transfer power between a nuclear steam supply system and a prime motor by fitting the specific enthalpy of main steam and water supply and considering the heat efficiency of a side-row unit and a unit and adopting a method for calculating enthalpy drop in unit time, and the method for simulating the transfer power of a first loop system and a second loop system of a pressurized water reactor nuclear power unit comprises the following steps:
step 110, initializing parameters of the pressurized water reactor nuclear power unit;
The parameters of the pressurized water reactor nuclear power unit for initialization setting comprise initialization tide basic data, a system network, a first loop system and a second loop system of the nuclear power unit and corresponding interface parameters;
Step 120, obtaining the current step length electric quantity data according to a preset rule;
Further, the step electric quantity data are obtained by calculating parameters including calculation parameters and final valve output power parameters in the previous step according to a set numerical integration algorithm;
Step 130, solving a primary loop system model and a secondary loop system model of the pressurized water reactor nuclear power unit to obtain calculation parameters; the calculated parameters comprise the steam temperature T s at the side of a second loop of the steam generator, the effective steam demand coefficient k se of the steam turbine and the steam flow f stm2 of a side-exhaust system of the steam turbine;
Further, the calculation parameters are obtained by carrying out cross iteration solution on the first loop system model and the second loop system model;
the primary loop system model and the secondary loop system model of the pressurized water reactor nuclear power unit are solved according to the electric quantity data of the step length;
step 140, calculating the final valve output power in the pressurized water reactor nuclear power system model by using the calculation parameters;
Further, calculating final valve output power in the pressurized water reactor nuclear power system model by using the calculation parameters, wherein the calculating comprises calculating specific enthalpy of steam, specific enthalpy of feedwater and total steam flow in corresponding step sizes according to the calculation parameters;
further, the method for calculating the specific enthalpy of steam comprises the following steps:
Obtaining the steam temperature T s of the secondary loop side of the steam generator in the secondary loop system model of the pressurized water reactor nuclear power unit in the calculated parameters;
fitting the change relation between the main steam specific enthalpy and the temperature of the nuclear turbine, and obtaining a fitting coefficient k 0、k1、k2、k3;
Because the main steam of the nuclear turbine is wet saturated steam, the relative humidity is stabilized at 100%, and therefore, the influence caused by humidity change can be not considered in the enthalpy curve. Therefore, when the vapor specific enthalpy value curve is fitted, the influence of humidity change is not considered, but the influence of pressure factors is considered; the fitting mode can adopt a least square method. Therefore, in the practical application of dynamic simulation of the electric power system, the fitting curve is used for simulating the specific enthalpy of steam;
Calculating the steam specific enthalpy value h s according to the temperature; meanwhile, considering the pressure factor, the calculation formula is as follows:
further, the calculation method of the total steam flow comprises the following steps:
Obtaining a steam turbine rated main steam flow f stmn, a steam turbine effective steam demand coefficient k se and a steam turbine side-exhaust system steam flow f stm2 in a two-loop system model of the pressurized water reactor nuclear power unit in the calculation function;
the total steam flow is determined by the two loop sides of the steam generator and is influenced by an effective steam demand limiting link, the opening of a regulating valve and the pressure difference between the front and the back of the valve; according to the method, the total steam flow of the nuclear power unit model is calculated, a valve flow correction curve is set, and effective steam demand limitation is defined in a proportional link with amplitude limitation;
Calculating the main steam flow f stm1 of the steam turbine; the calculation method of the main steam flow is f stm1＝ksefstmn;
calculating an actual total steam flow f stm, wherein the total steam flow f stm is the sum of the main steam flow of the steam turbine and the steam flow of the side-by-side exhaust system;
further, the method for calculating the specific enthalpy of the water supply comprises the following steps:
Obtaining the total steam flow f stm; the main steam flow f stm is obtained through the calculation in the last step;
the actual characteristic of specific enthalpy of the water supply is complex, and the specific enthalpy of the water supply is closely related to a plurality of devices such as a low-pressure heater, a high-pressure heater, a deaerator and the like of a water supply system; in the simplified model, according to the characteristic that the water supply process is mainly influenced by the steam extraction amount of the steam turbine, and the steam extraction amount of the steam turbine is closely related to the power level of a unit, a unit heat balance diagram is adopted, and the water supply specific enthalpy is fitted in a sectional mode according to the power level of the unit;
Fitting the water supply specific enthalpy h w of the secondary loop side of the steam generator in a sectional mode, and calculating to obtain a fitting coefficient k 4、k5;
The specific enthalpy h w of the water supply at the second loop side of the steam generator is calculated, and the calculation mode of the specific enthalpy of the water supply at the second loop side of the steam generator is as follows: h w＝k4+k5fstm;
According to the water supply specific enthalpy of the second loop side of the steam generator, calculating the actual water supply specific enthalpy h in which is sent to the steam generator to participate in the calculation of the second loop through an inertia link, wherein the actual water supply specific enthalpy h in is as follows:
Further, the method for calculating the final valve output power includes:
Obtaining the thermal efficiency eta of the two loops according to the power of the two loops of the last step in the electrical quantity data of the step and the thermal equilibrium diagram of the unit;
The heat efficiency of the steam turbine is an important index of the unit efficiency, and main factors influencing the heat efficiency include new steam parameters, exhaust steam pressure, the ratio of effective enthalpy drop of steam to ideal enthalpy drop, and the like;
In the invention, a unit thermal equilibrium diagram is adopted as a tool to calculate the thermal efficiency, and appropriate correction is carried out to compensate the error generated by modeling the equivalent of the two-loop thermodynamic process; in this example, table 1 gives the unit thermal efficiency of the reference unit at different powers:
Obtaining steam specific enthalpy h s, water supply specific enthalpy h in, main steam flow f stm1 of the steam turbine and rated power P M0 of the steam turbine of the second loop;
The calculation formula of the final valve output power P GV is as follows:
Fig. 2 is a block diagram of a first and second loop system transfer power simulation system of a pressurized water reactor nuclear motor unit according to an embodiment of the present invention, as shown in fig. 2, the system includes:
An initialization unit 210, where the initialization unit 210 is configured to perform initialization setting on parameters of the pressurized water reactor nuclear power unit;
an electrical quantity data calculation unit 220, wherein the electrical quantity data calculation unit 220 calculates electrical quantity data of the step length according to a preset rule;
Further, the electrical quantity data calculation unit 220 calculates and obtains the electrical quantity data of the step according to the set numerical integration algorithm through the parameters including the calculation parameters and the final valve output power in the previous step;
The model calculation unit 230, the model calculation unit 230 is configured to solve a first loop system model and a second loop system model of the pressurized water reactor nuclear motor unit to obtain calculation parameters; the calculated parameters comprise the steam temperature T s at the side of a second loop of the steam generator, the effective steam demand coefficient k s of the steam turbine and the steam flow f stm2 of a side-exhaust system of the steam turbine;
Further, the model calculation unit 230 obtains calculation parameters by performing cross iteration solution on the first loop system model and the second loop system model;
the model calculation unit 230 solves a first loop system model and a second loop system model of the pressurized water reactor nuclear power unit through the electric quantity data of the step length;
The comprehensive calculation unit 240 is configured to calculate final valve output power in the pressurized water reactor nuclear power system model by using the calculation parameters output by the model calculation unit;
Further, the comprehensive calculating unit 240 is configured to calculate the specific steam enthalpy, the specific feedwater enthalpy and the total steam flow in the corresponding step according to the calculation parameters;
further, the comprehensive calculating unit 240 is configured to calculate the specific enthalpy of steam;
The comprehensive calculation unit 240 fits the change relation between the main steam specific enthalpy and the temperature of the nuclear turbine according to the steam temperature T s at the secondary loop side of the steam generator in the secondary loop system model of the pressurized water reactor nuclear power unit in the calculation parameters, and obtains a fitting coefficient k 0、k1、k2、k3;
The comprehensive calculation unit 240 calculates the specific vapor enthalpy value h s according to temperature; the calculation formula is as follows:
further, the comprehensive calculating unit 240 is configured to calculate the total steam flow;
The comprehensive calculation unit 240 calculates the main steam flow f stm1 of the steam turbine according to the rated main steam flow f stmn of the steam turbine, the effective steam demand coefficient k s of the steam turbine and the steam flow f stm2 of a side-exhaust system of the steam turbine in the two-loop system model of the pressurized water reactor nuclear power unit in the calculation function; the calculation method of the main steam flow is f stm1＝ksefstmn;
The comprehensive calculation unit 240 is configured to calculate an actual total steam flow f stm, where the total steam flow f stm is a sum of the main steam flow of the steam turbine and the steam flow of the bypass system;
further, the comprehensive calculating unit 240 is configured to calculate the specific enthalpy of feedwater;
The comprehensive calculation unit 240 obtains the total steam flow f stm, fits the water supply specific enthalpy h w of the two loops side of the steam generator in a sectional mode, and calculates a fitting coefficient k 4、k5;
The comprehensive calculating unit 240 is configured to calculate a specific enthalpy h w of water supply on the second circuit side of the steam generator, where the specific enthalpy of water supply on the second circuit side of the steam generator is calculated by: h w＝k4+k5fstm;
The comprehensive calculation unit 240 calculates the actual specific enthalpy h in of the water fed to the steam generator to participate in the two-loop calculation through the inertia link according to the specific enthalpy of the water fed at the two-loop side of the steam generator, wherein the actual specific enthalpy h in is as follows:
further, the comprehensive calculation unit 240 is configured to obtain the two-loop thermal efficiency η according to the two-loop power of the last step in the current step electrical quantity data and the thermal equilibrium diagram of the unit;
The comprehensive calculation unit 240 is configured to calculate the final valve output P GV; the calculation formula of the final valve output power P GV is as follows:
Wherein h s is steam specific enthalpy, h in is water specific enthalpy, f stm1 is main steam flow of the steam turbine, and P M0 is rated power of the steam turbine.
In the description provided herein, numerous specific details are set forth. However, it is understood that embodiments of the disclosure may be practiced without these specific details. In some instances, well-known methods, structures and techniques have not been shown in detail in order not to obscure an understanding of this description.
Those skilled in the art will appreciate that the modules in the apparatus of the embodiments may be adaptively changed and disposed in one or more apparatuses different from the embodiments. The modules or units or components of the embodiments may be combined into one module or unit or component and, furthermore, they may be divided into a plurality of sub-modules or sub-units or sub-components. Any combination of all features disclosed in this specification (including any accompanying claims, abstract and drawings), and all of the processes or units of any method or apparatus so disclosed, may be used in combination, except insofar as at least some of such features and/or processes or units are mutually exclusive. Each feature disclosed in this specification (including any accompanying claims, abstract and drawings), may be replaced by alternative features serving the same, equivalent or similar purpose, unless expressly stated otherwise. Reference to step numbers in this specification is used solely to distinguish between steps and is not intended to limit the time or logical relationship between steps, including the various possible conditions unless the context clearly indicates otherwise.
Furthermore, those skilled in the art will appreciate that while some embodiments described herein include some features but not others included in other embodiments, combinations of features of different embodiments are meant to be within the scope of the disclosure and form different embodiments. For example, any of the embodiments claimed in the claims may be used in any combination.
Various component embodiments of the present disclosure may be implemented in hardware, or in software modules running on one or more processors, or in a combination thereof. The present disclosure may also be implemented as an apparatus or system program (e.g., a computer program and a computer program product) for performing a portion or all of the methods described herein. Such a program embodying the present disclosure may be stored on a computer readable medium, or may have the form of one or more signals. Such signals may be downloaded from an internet website, provided on a carrier signal, or provided in any other form.
It should be noted that the above-mentioned embodiments illustrate rather than limit the disclosure, and that those skilled in the art will be able to design alternative embodiments without departing from the scope of the appended claims. The word "comprising" does not exclude the presence of elements or steps not listed in a claim. The word "a" or "an" preceding an element does not exclude the presence of a plurality of such elements. The disclosure may be implemented by means of hardware comprising several distinct elements, and by means of a suitably programmed computer. In the unit claims enumerating several means, several of these means may be embodied by one and the same item of hardware.
The foregoing is merely a specific embodiment of the disclosure, and it should be noted that it will be apparent to those skilled in the art that various improvements, modifications, and variations can be made without departing from the spirit of the disclosure, and such improvements, modifications, and variations are considered to be within the scope of the application.
Claims (2)
1. A method for simulating the transmission power of a first loop system and a second loop system of a pressurized water reactor nuclear motor unit, comprising the following steps:
initializing parameters of the pressurized water reactor nuclear power unit;
Obtaining electrical quantity data in a current step length according to a preset rule;
the electrical quantity data in the current step length is obtained by calculating parameters including calculation parameters and final valve output power parameters in the previous step length according to a set numerical integration algorithm; the primary loop system model and the secondary loop system model of the pressurized water reactor nuclear power unit are solved according to the electric quantity data of the step length;
Solving a primary loop system model and a secondary loop system model of the pressurized water reactor nuclear power unit to obtain calculation parameters; the calculated parameters comprise the steam temperature T s at the side of a second loop of the steam generator, the effective steam demand coefficient k se of the steam turbine and the steam flow f stm2 of a side-exhaust system of the steam turbine;
Calculating final valve output power in the pressurized water reactor nuclear power system model by using the calculation parameters; the final valve output power is the power transmitted by a first loop system and a second loop system of the pressurized water reactor nuclear motor unit
Calculating final valve output power in the pressurized water reactor nuclear power system model by using the calculation parameters, wherein the calculation of the final valve output power comprises the steps of calculating steam specific enthalpy, water supply specific enthalpy, main steam flow and total steam flow in corresponding step sizes according to the calculation parameters;
The calculation method of the specific enthalpy of steam comprises the following steps: obtaining the steam temperature T s of the secondary loop side of the steam generator in the secondary loop system model of the pressurized water reactor nuclear power unit in the calculated parameters;
fitting the change relation between the main steam specific enthalpy and the temperature of the nuclear turbine, and obtaining a fitting coefficient k 0、k1、k2、k3;
calculating the steam specific enthalpy value according to the temperature; meanwhile, considering the pressure factor, the calculation formula is as follows:
wherein p s is a pressure factor;
the calculation method of the total steam flow comprises the following steps:
Obtaining a steam turbine effective steam demand coefficient k se and a steam turbine side-exhaust system steam flow f stm2 in a two-loop system model of the pressurized water reactor nuclear power unit in the steam turbine rated main steam flow f stmn and the calculated parameters;
Calculating the main steam flow f stm1 of the steam turbine; the calculation method of the main steam flow is f stm1＝ksefstmn;
calculating an actual total steam flow f stm, wherein the total steam flow f stm is the sum of the main steam flow of the steam turbine and the steam flow of the side-by-side exhaust system;
the method for calculating the specific enthalpy of the water supply comprises the following steps:
Obtaining a total steam flow f stm;
Fitting the water supply specific enthalpy h w of the secondary loop side of the steam generator in a sectional mode, and calculating to obtain a fitting coefficient k 4、k5;
The specific enthalpy h w of the water supply at the second loop side of the steam generator is calculated, and the calculation mode of the specific enthalpy of the water supply at the second loop side of the steam generator is as follows: h w＝k4+k5fstm;
According to the water supply specific enthalpy of the second loop side of the steam generator, calculating the actual water supply specific enthalpy h in which is sent to the steam generator to participate in the calculation of the second loop through an inertia link, wherein the actual water supply specific enthalpy h in is as follows:
The calculation method of the final valve output power comprises the following steps: obtaining the thermal efficiency eta of the two loops according to the power of the two loops of the last step in the electrical quantity data in the current step and the thermal equilibrium diagram of the unit;
Obtaining steam specific enthalpy h s, water supply specific enthalpy h in, main steam flow f stm1 of the steam turbine and rated power of the steam P M0 turbine of the two loops;
The calculation formula of the final valve output power P GV is as follows:
The calculation parameters are obtained by carrying out cross iteration solution on the first loop system model and the second loop system model.
2. A pressurized water reactor nuclear power unit one-loop and two-loop system transfer power simulation system, the system comprising:
The initialization unit is used for initializing and setting parameters of the pressurized water reactor nuclear power unit;
the electrical quantity data calculation unit calculates electrical quantity data of the current step according to a preset rule;
The electrical quantity data calculation unit calculates and obtains electrical quantity data in the current step through parameters including calculation parameters and final valve output power in the last step according to a set numerical integration algorithm; the model calculation unit solves a primary loop system model and a secondary loop system model of the pressurized water reactor nuclear power unit through the electric quantity data of the step length;
The model calculation unit is used for solving a primary loop system model and a secondary loop system model of the pressurized water reactor nuclear power unit to obtain calculation parameters; the calculated parameters comprise the steam temperature T s at the side of a second loop of the steam generator, the effective steam demand coefficient k se of the steam turbine and the steam flow f stm2 of a side-exhaust system of the steam turbine;
The comprehensive calculation unit is used for calculating final valve output power in the pressurized water reactor nuclear power system model by utilizing the calculation parameters output by the model calculation unit and outputting the final valve output power as the transmission power of the first loop system and the second loop system of the pressurized water reactor nuclear power unit
The comprehensive calculation unit is used for calculating the specific steam enthalpy, the specific feed water enthalpy and the total steam flow in the corresponding step length according to the calculation parameters
The comprehensive calculation unit is used for calculating the specific enthalpy of steam; the comprehensive calculation unit calculates the steam temperature T s of the secondary loop side of the steam generator in the secondary loop system model of the pressurized water reactor nuclear power unit according to the calculation parameters;
fitting the change relation between the main steam specific enthalpy and the temperature of the nuclear turbine, and obtaining a fitting coefficient k 0、k1、k2、k3;
calculating the steam specific enthalpy value according to the temperature; meanwhile, considering the pressure factor, the calculation formula is as follows:
wherein p s is a pressure factor;
The comprehensive calculation unit is used for calculating the total steam flow; the comprehensive calculation unit is used for calculating the steam flow f stm2 of a turbine side-exhaust system according to the rated main steam flow f stmn of the turbine and the effective steam demand coefficient k se of the turbine in the two-loop system model of the pressurized water reactor nuclear power unit in the calculation parameters;
Calculating the main steam flow f stm1 of the steam turbine; the calculation method of the main steam flow is f stm1＝ksefstmn;
calculating an actual total steam flow f stm, wherein the total steam flow f stm is the sum of the main steam flow of the steam turbine and the steam flow of the side-by-side exhaust system;
the comprehensive calculation unit is used for calculating the specific enthalpy of the water supply;
The comprehensive calculation unit obtains the total steam flow f stm, fits the water supply specific enthalpy h w of the two loops of the steam generator in a sectional mode, and calculates a fitting coefficient k 4、k5;
The specific enthalpy h w of the water supply at the second loop side of the steam generator is calculated, and the calculation mode of the specific enthalpy of the water supply at the second loop side of the steam generator is as follows: h w＝k4+k5fstm;
According to the water supply specific enthalpy of the second loop side of the steam generator, calculating the actual water supply specific enthalpy h in which is sent to the steam generator to participate in the calculation of the second loop through an inertia link, wherein the actual water supply specific enthalpy h in is as follows:
the comprehensive calculation unit is used for obtaining the thermal efficiency eta of the two loops according to the power of the two loops of the last step in the electrical quantity data in the current step and the thermal equilibrium diagram of the unit;
Obtaining steam specific enthalpy h s, water supply specific enthalpy h in, main steam flow f stm1 of the steam turbine and rated power of the steam P M0 turbine of the two loops;
The calculation formula of the final valve output power P GV is as follows:
the model calculation unit obtains calculation parameters by carrying out cross iteration solution on the first loop system model and the second loop system model;
The electrical quantity data calculation unit calculates and obtains electrical quantity data of the current step through parameters including calculation parameters and final valve output power in the last step according to a set numerical integration algorithm; and the model calculation unit solves a first loop system model and a second loop system model of the pressurized water reactor nuclear power unit through the electric quantity data of the step length.
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Non-Patent Citations (4)
| Title |
|---|
| 基于PSASP自定义模型的核电机组动态响应仿真;赵洁;刘涤尘;熊莉;陈琪;杜治;雷庆生;;核动力工程(第03期);全文 * |
| 基于压水堆核电机组等效热降法的改进算法;王虎;齐光才;李少华;李常建;;核动力工程(第05期);全文 * |
| 核电机组一二回路耦合变工况分析;武心壮;;节能技术(第04期);全文 * |
| 核电机组二回路建模与动态仿真;葛斌;张俊礼;;电力自动化设备(06);全文 * |
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