CN104484528A - Nuclear power unit power and electric hybrid simulation platform based on PSCAD - Google Patents

Abstract

The invention discloses a nuclear power unit power and electric hybrid simulation platform based on PSCAD, and belongs to the technical field of a PSCAD electric power system. The nuclear power unit power and electric hybrid simulation platform adopts the following steps that 1, in a flow process of preparing data required by simulation, relevant parameters of power and electric operation links in a nuclear power plant are obtained; 2, the flow process for building a nuclear power plant simulation model comprises the processes of building a mathematical model and building each module in the PSCAD environment according to the operation parameters; 3, in the flow process for building an integral simulation platform, the built inside modules and the automatically generated element models are connected and combined according to the connection information of each module. The nuclear power unit power and electric hybrid simulation platform has the advantages that better operability is realized, the model is greatly optimized, the structure is simple, the realization is easy, the simulation efficiency is improved, the power setting value is regulated according to different output rated power of a power generator, and the load operation mode is determined.

Description

A kind of nuclear power generating sets power based on PSCAD, electrically hybrid simulation platform

Technical field

The present invention relates to Simulating technique in Electric Power System field, more particularly, relate to the foundation of a kind of nuclear power generating sets power based on PSCAD, electrically hybrid simulation platform.

Background technology

China is Nuclear Power Development just energetically; nuclear power access electric system after will and system between produce significant impact; along with the continuous increase of electrical network peak-valley difference and the large-scale development of nuclear power; the necessity that nuclear power participates in peak regulation is more aobvious outstanding; for nuclear power development tendency and system grid connection requirement, need to participate in peak regulation and system daily load characteristic variations to nuclear power, the Steam Generator in Load Follow pattern of nuclear power generating sets and peak regulation range require to carry out further investigation; to this, be necessary that syncaryon electric model sets up nuclear power generating sets emulation platform.

There is the model of some PWR nuclear power plants at present, 2 classes can be divided into by its purpose: a class has been the emulator being mainly used in training nuclear power plant staff, and they establish detailed nuclear power plant's control and protection system model; Another kind of is model for studying nuclear power plant and electric system long term dynamics process or simulated program.The link that these models are considered is more, and exponent number is higher, generally more than 20 rank, is up to 50 multistage, not easily realizes.

For present situation, need the consolidated project emulation platform setting up nuclear power station and electrical network synthetic operation for researching and analysing nuclear power and power grid joint peaking operation.

Summary of the invention

The object of the present invention is to provide a kind of power based on PSCAD, electric integrated emulation platform model, is applicable to the simplification of nuclear power generating sets realistic model in PSCAD, and in PSCAD, carry out load-following capacity analysis and peak regulation method demonstration.

For achieving the above object, the technical solution adopted in the present invention is:

Based on the nuclear power generating sets power of PSCAD, electrically a hybrid simulation platform, comprise presurized water reactor module, generator module and equivalent electrical network module; Presurized water reactor module is connected with generator module by steam turbine and speed regulator, generator module directly with equivalent electrical network model calling;

Performing step is as follows:

Step 1) obtain emulation desired parameters: the concrete following parameter obtaining nuclear power plant's power and electrical operation link: neutron pile parameter, steam generator parameter, power control system parameter, steam turbine and governor parameter thereof, Generator Parameters, nuclear power station outlet operational factor, network equivalence parameter;

Step 2) set up nuclear power station emulation module: founding mathematical models, according to step 1) in operational factor, in PSCAD environment, build emulation module step as follows:

Step (1) nuclear power station operational factor, comprising: neutron flux parameter, hot line temperature parameter, cold line temperature parameter, vapor pressure parameter, valve opening parameter and output mechanical power parameter; Nuclear power station operational factor principle of work comprises nuclear power station basic power generation operation principle and each model physical principle; Corresponding mathematical model; The each model of physical principle comprises: neutron dynamics model, core fuel temperature model, primary Ioops cooling medium average temperature model, model steam generator, Power control model, steam turbine and governor model, generator model, equivalent electric network model;

Step (2) is built presurized water reactor module according to the mathematical model set up in step (1), sets up according to PSCAD master library module the generator model that the emulation platform needed for nuclear power generating sets carries;

Step (3) carries out dynamic equivalent to the outlet of equivalent electrical network; Set up the Equivalent Model needed for the selection of PSCAD master library;

Step 3) set up overall emulation platform: according to water-water reactor module, the link information of generator module and equivalent electrical network module, is undertaken being connected combination by the presurized water reactor internal module established and automatically-generating module; Described presurized water reactor internal module comprises: neutron dynamics model, core fuel temperature, coolant temperature dynamic model, hot line cold line temperature model, model steam generator, Power control model, steam turbine and governor model thereof; Described automatically-generating module is that PSCAD master library module comprises generator main body and excitation system model thereof and equivalent electric network model;

Set up the parameter needed for each mathematical model of presurized water reactor internal model and generator, electric parameter needed for equivalent power network modeling, comprising: the rated power of generator, rated voltage, reactance, the supply voltage of torque and equivalent electrical network, frequency, resistance, reactance.

Advantage of the present invention is:

1. the present invention carries out modeling to PWR of Nuclear Power Station first in PSCAD simulation software, and by steam turbine first by power, electrical operation connects, and can react nuclear power generating sets load-following capacity comprehensively and really.

2. the present invention has good operability, according to the different adjustment power setting valve of the rated power that generator exports, determines load operation mode.

3. the present invention is under PSCAD environment, under not affecting the external characteristic of equivalent electrical network, optimizes model structure greatly, makes circuit simple, easily realizes, improve simulation efficiency.

Accompanying drawing explanation

Fig. 1 is entire block diagram of the present invention.

Fig. 2 is PSCAD emulation platform functional diagram of the present invention.

Fig. 3 is model buildings process flow diagram.

Fig. 4-1 is one of simulation curve figure.

Fig. 4-2 is simulation curve figure bis-.

Fig. 4-3 is simulation curve figure tri-.

Fig. 4-4 is simulation curve figure tetra-.

Fig. 4-5 is simulation curve figure five.

Fig. 4-6 is simulation curve figure six.

Fig. 4-7 is simulation curve figure seven.

Embodiment

Below in conjunction with accompanying drawing Fig. 1 of the present invention, Fig. 2, Fig. 3, Fig. 4-1, Fig. 4-2, Fig. 4-3, Fig. 4-4, Fig. 4-5, Fig. 4-6, Fig. 4-7, carries out clear to the technical scheme in the embodiment of the present invention, complete description.

Based on the nuclear power generating sets power of PSCAD, electrically a hybrid simulation platform, comprise presurized water reactor module, generator module and equivalent electrical network module; Presurized water reactor module is connected with generator module by steam turbine and speed regulator, generator module directly with equivalent electrical network model calling;

Performing step is as follows:

Step 1) obtain emulation desired parameters: the concrete following parameter obtaining nuclear power plant's power and electrical operation link: neutron pile parameter, steam generator parameter, power control system parameter, steam turbine and governor parameter thereof, Generator Parameters, nuclear power station outlet operational factor, network equivalence parameter;

Step 2) set up nuclear power station emulation module: founding mathematical models, according to step 1) in operational factor, in PSCAD environment, build emulation module step as follows:

Step (1) nuclear power station operational factor, comprising: neutron flux parameter, hot line temperature parameter, cold line temperature parameter, vapor pressure parameter, valve opening parameter and output mechanical power parameter; Nuclear power station operational factor principle of work comprises nuclear power station basic power generation operation principle and each model physical principle; Corresponding mathematical model; The each model of physical principle comprises: neutron dynamics model, core fuel temperature model, primary Ioops cooling medium average temperature model, model steam generator, Power control model, steam turbine and governor model, generator model, equivalent electric network model;

Step (2) is built presurized water reactor module according to the mathematical model set up in step (1), sets up according to PSCAD master library module the generator model that the emulation platform needed for nuclear power generating sets carries;

Step (3) carries out dynamic equivalent to the outlet of equivalent electrical network; Set up the Equivalent Model needed for the selection of PSCAD master library;

Step 3) set up overall emulation platform: according to water-water reactor module, the link information of generator module and equivalent electrical network module, is undertaken being connected combination by the presurized water reactor internal module established and automatically-generating module; Described presurized water reactor internal module comprises: neutron dynamics model, core fuel temperature, coolant temperature dynamic model, hot line cold line temperature model, model steam generator, Power control model, steam turbine and governor model thereof; Described automatically-generating module is that PSCAD master library module comprises generator main body and excitation system model thereof and equivalent electric network model;

Set up the parameter needed for each mathematical model of presurized water reactor internal model and generator, electric parameter needed for equivalent power network modeling, comprising: the rated power of generator, rated voltage, reactance, the supply voltage of torque and equivalent electrical network, frequency, resistance, reactance.

Described presurized water reactor module comprises: reactor core model, model steam generator, reactor control system model, cooling medium main pump model and steam turbine model;

Wherein reactor core model comprises neutron power plant module, reactor fuel and coolant temperature dynamic model, hot line cold line temperature model;

A. the mathematical model of neutron power plant module is:

$\left\{\begin{array}{c}\mathrm{\Δn}=\frac{1}{s+\frac{\mathrm{\β}}{l}}(\frac{1}{l}\mathrm{\Δ\ρ}+\mathrm{\λ\ΔC})\\ \mathrm{\ΔC}=\frac{1}{s+\mathrm{\λ}}\frac{\mathrm{\β}}{l}\mathrm{\Δn}\end{array}\right.$

In formula:

Δ n is neutron flux; L is mean neutron lifetime; β is delayed neutron ratio altogether, β=∑ β _i; λ is delayed neutron disintegration constant; ρ is: the reactivity that reactor core is total;

B. the mathematical model of reactor fuel and coolant temperature dynamic model is:

$\left\{\begin{array}{c}\frac{{\mathrm{d\ΔT}}_F}{\mathrm{dt}}=\frac{{\mathrm{fP}}_0}{m_F{c}_{\mathrm{PF}}}\mathrm{\Δn}+\frac{\mathrm{hA}}{{2m}_F{c}_{\mathrm{PF}}}({\mathrm{\ΔT}}_{\mathrm{\θ}1}+{\mathrm{\ΔT}}_{\mathrm{\θ}2}-{2\mathrm{\ΔT}}_F)\\ \frac{{\mathrm{d\ΔT}}_{\mathrm{\θ}1}}{\mathrm{dt}}=\frac{(1-f)P_0}{m_C{c}_{\mathrm{PC}}}\mathrm{\Δn}+\frac{\mathrm{hA}}{m_C{c}_{\mathrm{PC}}}({\mathrm{\ΔT}}_F-{\mathrm{\ΔT}}_{\mathrm{\θ}1})+\frac{{\stackrel{\·}{m}}_C}{m_C}({\mathrm{\ΔT}}_{\mathrm{CL}}-{\mathrm{\ΔT}}_{\mathrm{\θ}1})\\ \frac{{\mathrm{d\ΔT}}_{\mathrm{\θ}2}}{\mathrm{dt}}=\frac{(1-f)P_0}{m_C{c}_{\mathrm{PC}}}\mathrm{\Δn}+\frac{\mathrm{hA}}{m_C{c}_{\mathrm{PC}}}({\mathrm{\ΔT}}_F-{\mathrm{\ΔT}}_{\mathrm{\θ}1})+\frac{{\stackrel{\·}{m}}_C}{m_C}({\mathrm{\ΔT}}_{\mathrm{\θ}1}-{\mathrm{\ΔT}}_{\mathrm{\θ}2})\end{array}\right.$ In formula:

Δ T _f: core fuel temperature deviation; F: the number percent of core power shared by reactor core heats up; p ₀: reactor core initial power; m _f: reactor fuel quality; c _pF: reactor fuel specific heat; H: from fuel to cooling the overall heat transfer coefficient cutd open; A: the total heat conduction area from fuel to cooling medium; Δ T _{θ 1}: temperature deviation is cutd open in the cooling of reactor core porch; Δ T _{θ 2}: core exit place coolant temperature deviation; m _c: Core cooling agent quality; C _pc: Core cooling agent specific heat; M: the mass rate that Core cooling agent is total;

C. the mathematical model of hot line cold line model is:

$\left\{\begin{array}{c}{\mathrm{\ΔT}}_{\mathrm{HL}}={\mathrm{\τ}}_{\mathrm{HL}}\frac{\mathrm{d\Δ}{T}_{\mathrm{\θ}2}}{\mathrm{dt}}+{\mathrm{\ΔT}}_{\mathrm{\θ}2}\\ {\mathrm{\ΔT}}_{\mathrm{CL}}={\mathrm{\τ}}_{\mathrm{CL}}\frac{{\mathrm{d\ΔT}}_P}{\mathrm{dt}}+{\mathrm{\ΔT}}_P\end{array}\right.$

In formula:

Δ T _hL: the variable quantity of hot line temperature; Δ T _cL: the variable quantity of cold line temperature; Δ T _p: steam generator primary Ioops coolant temperature variable quantity; τ _hL: hot line time constant; τ _cL: cold line time constant;

Described model steam generator comprises primary Ioops coolant temperature model, the temperature model of U-shaped metal tube and secondary coolant circuit system vapor pressure model;

The mathematical model of model steam generator is:

$\left\{\begin{array}{c}\frac{{\mathrm{d\ΔT}}_P}{\mathrm{dt}}=\frac{1}{{\mathrm{\τ}}_P}(k_{\mathrm{pm}}{\mathrm{\ΔT}}_m+k_{\mathrm{pc}}{\mathrm{\ΔT}}_{\mathrm{HL}}-{\mathrm{\ΔT}}_P)\\ \frac{{\mathrm{d\ΔT}}_m}{\mathrm{dt}}=\frac{1}{{\mathrm{\τ}}_m}(k_{\mathrm{mp}}{\mathrm{\ΔT}}_p+k_{\mathrm{ms}}{\mathrm{\ΔP}}_S-{\mathrm{\ΔT}}_m)\\ \frac{{\mathrm{d\ΔP}}_S}{\mathrm{dt}}=\frac{1}{{\mathrm{\τ}}_{\mathrm{ps}}}(k_{\mathrm{psm}}{\mathrm{\ΔT}}_m-k_{\mathrm{psy}}\mathrm{\Δy}-{\mathrm{\ΔP}}_S)\end{array}\right.$

In formula:

Δ T _m: metal tube temperature deviation; Δ Ps: secondary circuit vapor pressure deviation; Δ y: valve opening deviation; τ _p: primary Ioops cooling medium time constant; τ _m: metal tube time constant; τ _ps: secondary circuit steaming time constant; k _pm: metal tube temperature coefficient; k _pc: hot line temperature coefficient; k _mp: coolant temperature coefficient; k _ms: pressure-temperature coefficient; k _psm: metal tube pressure coefficient; k _psy: valve pressure coefficient.

The described constant scheme of reactor control system model cooling medium medial temperature, this temperature constant scheme cooling medium medial temperature is not exerted oneself with nuclear power station and is changed, favourable to primary Ioops system.

Described cooling medium main pump mathematical model:

$T_{\mathrm{jp}}=\frac{{\mathrm{d\ω}}_p}{\mathrm{dt}}=M_{\mathrm{pe}}-M_{\mathrm{pm}}$

$M_{\mathrm{pe}}=k_{e1}\frac{U_{1*}^2(1-\frac{{\mathrm{\ω}}_{p^{*}}}{f_{1*}})}{[1+k_{e2}{f}_{1*}^2{(1-\frac{w_{p^{*}}}{f_{1*}})}^2]f_{1*}}$

$M_{\mathrm{pm}}={\mathrm{\ω}}_p^2$

$\frac{{\stackrel{\·}{m}}_c}{{\stackrel{\·}{m}}_{\mathrm{cn}}}=\frac{{\mathrm{\ω}}_p}{{\mathrm{\ω}}_{\mathrm{pn}}}$

In formula: ω _p: main pump frequency; M _pe: main pump electromagnetic torque; M _pm: main pump mechanical output; f _1*: station service bus frequency; U _1*station service busbar voltage.

Power is passed to synchronous generator by torque patterns as power section by steam turbine by presurized water reactor, generates electricity and is transported to electrical network, and mains frequency and Feedback of Power are then changed the reaction of presurized water reactor power to turbine system by generator; During nuclear power generating sets load carrying, be connected by generator with between electrical network; Generator is contacted by steam turbine and speed regulator thereof and nuclear reactor system; The steam turbine structure of PWR nuclear power plant is 4 cylinders double fluid resuperheat condensing-type saturated steam turbines, adopts power and frequency electric-liquid type speed regulator, can the change of responding power and frequency; The information that nuclear power plant outputs to electrical network only has the mechanical output of steam turbine, and the information that electrical network is input to nuclear power plant has rotating speed and the active power of generator, and is connected by generator, and generator is contacted by steam turbine and speed regulator thereof and presurized water reactor.

Described steam turbine employing rotating speed is the Half Speed 4 cylinder double fluid resuperheat condensing-type saturated vapor turbine of fired power generating unit half, and speed regulator adopts merit electrohydraulic governor model frequently, is made up of tachometric survey and regulator, measurement of power unit, relay and hydraulic oil motor.

Claims (8)

1., based on the nuclear power generating sets power of PSCAD, electrically a hybrid simulation platform, it is characterized in that:

Comprise presurized water reactor module, generator module and equivalent electrical network module; Presurized water reactor module is connected with generator module by steam turbine and speed regulator, generator module directly with equivalent electrical network model calling;

Performing step is as follows:

Step 1) obtain emulation desired parameters: the concrete following parameter obtaining nuclear power plant's power and electrical operation link: neutron pile parameter, steam generator parameter, power control system parameter, steam turbine and governor parameter thereof, Generator Parameters, nuclear power station outlet operational factor, network equivalence parameter;

Step 2) set up nuclear power station emulation module: founding mathematical models, according to step 1) in operational factor, in PSCAD environment, build emulation module step as follows:

Step (1) nuclear power station operational factor, comprising: neutron flux parameter, hot line temperature parameter, cold line temperature parameter, vapor pressure parameter, valve opening parameter and output mechanical power parameter; Nuclear power station operational factor principle of work comprises nuclear power station basic power generation operation principle and each model physical principle; Corresponding mathematical model; The each model of physical principle comprises: neutron dynamics model, core fuel temperature model, primary Ioops cooling medium average temperature model, model steam generator, Power control model, steam turbine and governor model, generator model, equivalent electric network model;

Step (2) is built presurized water reactor module according to the mathematical model set up in step (1), sets up according to PSCAD master library module the generator model that the emulation platform needed for nuclear power generating sets carries;

Step (3) carries out dynamic equivalent to the outlet of equivalent electrical network; Set up the Equivalent Model needed for the selection of PSCAD master library;

Step 3) set up overall emulation platform: according to water-water reactor module, the link information of generator module and equivalent electrical network module, is undertaken being connected combination by the presurized water reactor internal module established and automatically-generating module; Described presurized water reactor internal module comprises: neutron dynamics model, core fuel temperature, coolant temperature dynamic model, hot line cold line temperature model, model steam generator, Power control model, steam turbine and governor model thereof; Described automatically-generating module is that PSCAD master library module comprises generator main body and excitation system model thereof and equivalent electric network model.

2. nuclear power generating sets power according to claim 1, electrically hybrid simulation platform, is characterized in that:

Set up the parameter needed for each mathematical model of presurized water reactor internal model and generator, electric parameter needed for equivalent power network modeling, comprising: the rated power of generator, rated voltage, reactance, the supply voltage of torque and equivalent electrical network, frequency, resistance, reactance.

3. nuclear power generating sets power according to claim 1, electrically hybrid simulation platform, is characterized in that:

Described presurized water reactor module comprises: reactor core model, model steam generator, reactor control system model, cooling medium main pump model and steam turbine model;

Wherein reactor core model comprises neutron power plant module, reactor fuel and coolant temperature dynamic model, hot line cold line temperature model;

A. the mathematical model of neutron power plant module is:

$\left\{\begin{array}{c}\mathrm{\Δn}\frac{1}{s+\frac{\mathrm{\β}}{l}}(\frac{1}{l}\mathrm{\Δ\ρ}+\mathrm{\λ\ΔC})\\ \mathrm{\ΔC}=\frac{1}{s+\mathrm{\λ}}\frac{\mathrm{\β}}{l}\mathrm{\Δn}\end{array}\right.$

In formula: Δ n is neutron flux; L is mean neutron lifetime; β is delayed neutron ratio altogether, β=∑ β _i; λ is delayed neutron disintegration constant; ρ is: the reactivity that reactor core is total;

B. the mathematical model of reactor fuel and coolant temperature dynamic model is:

$\left\{\begin{array}{c}\frac{{\mathrm{d\ΔT}}_F}{\mathrm{dt}}=\frac{{\mathrm{fP}}_0}{m_F{c}_{\mathrm{PF}}}\mathrm{\Δn}+\frac{\mathrm{hA}}{{2m}_F{c}_{\mathrm{PF}}}({\mathrm{\ΔT}}_{\mathrm{\θ}1}+{\mathrm{\ΔT}}_{\mathrm{\θ}2}-{2\mathrm{\ΔT}}_F)\\ \frac{{\mathrm{d\ΔT}}_{\mathrm{\θ}1}}{\mathrm{dt}}=\frac{(1-f)P_0}{m_C{c}_{\mathrm{PC}}}\mathrm{\Δn}+\frac{\mathrm{hA}}{m_C{c}_{\mathrm{PC}}}({\mathrm{\ΔT}}_F-{\mathrm{\ΔT}}_{\mathrm{\θ}1})+\frac{\stackrel{\·}{m_C}}{m_C}({\mathrm{\ΔT}}_{\mathrm{CL}}-{\mathrm{\ΔT}}_{\mathrm{\θ}1})\\ \frac{{\mathrm{d\ΔT}}_{\mathrm{\θ}2}}{\mathrm{dt}}=\frac{(1-f)P_0}{m_C{c}_{\mathrm{PC}}}\mathrm{\Δn}+\frac{\mathrm{hA}}{m_C{c}_{\mathrm{PC}}}({\mathrm{\ΔT}}_F-{\mathrm{\ΔT}}_{\mathrm{\θ}1})+\frac{{\stackrel{\·}{m}}_C}{m_C}({\mathrm{\ΔT}}_{\mathrm{\θ}1}-{\mathrm{\ΔT}}_{\mathrm{\θ}2})\end{array}\right.$

In formula: Δ T _f: core fuel temperature deviation; F: the number percent of core power shared by reactor core heats up; p ₀: reactor core initial power; m _f: reactor fuel quality; c _pF: reactor fuel specific heat; H: from fuel to cooling the overall heat transfer coefficient cutd open; A: the total heat conduction area from fuel to cooling medium; Δ T _{θ 1}: temperature deviation is cutd open in the cooling of reactor core porch; Δ T _{θ 2}: core exit place coolant temperature deviation; m _c: Core cooling agent quality; C _pc: Core cooling agent specific heat; M: the mass rate that Core cooling agent is total; .

C. the mathematical model of hot line cold line model is:

$\left\{\begin{array}{c}{\mathrm{\ΔT}}_{\mathrm{HL}}={\mathrm{\τ}}_{\mathrm{HL}}\frac{{\mathrm{d\ΔT}}_{\mathrm{\θ}2}}{\mathrm{dt}}+{\mathrm{\ΔT}}_{\mathrm{\θ}2}\\ {\mathrm{\ΔT}}_{\mathrm{CL}}={\mathrm{\τ}}_{\mathrm{CL}}\frac{{\mathrm{d\ΔT}}_P}{\mathrm{dt}}+{\mathrm{\ΔT}}_P\end{array}\right.$

In formula: Δ T _hL: the variable quantity of hot line temperature; Δ T _cL: the variable quantity of cold line temperature; Δ T _p: steam generator primary Ioops coolant temperature variable quantity; τ _hL: hot line time constant; τ _cL: cold line time constant.

4. nuclear power generating sets power according to claim 3, electrically hybrid simulation platform, is characterized in that:

Described model steam generator comprises primary Ioops coolant temperature model, the temperature model of U-shaped metal tube and secondary coolant circuit system vapor pressure model;

The mathematical model of model steam generator is:

$\left\{\begin{array}{c}\frac{{\mathrm{d\ΔT}}_P}{\mathrm{dt}}=\frac{1}{{\mathrm{\τ}}_P}(k_{\mathrm{pm}}{\mathrm{\ΔT}}_m+k_{\mathrm{pc}}{\mathrm{\ΔT}}_{\mathrm{HL}}-{\mathrm{\ΔT}}_P)\\ \frac{{\mathrm{d\ΔT}}_m}{\mathrm{dt}}=\frac{1}{{\mathrm{\τ}}_m}(k_{\mathrm{mp}}{\mathrm{\ΔT}}_p+k_{\mathrm{ms}}{\mathrm{\ΔP}}_S-{\mathrm{\ΔT}}_m)\\ \frac{{\mathrm{d\ΔP}}_S}{\mathrm{dt}}=\frac{1}{{\mathrm{\τ}}_{\mathrm{ps}}}(k_{\mathrm{psm}}{\mathrm{\ΔT}}_m-k_{\mathrm{psy}}\mathrm{\Δy}-{\mathrm{\ΔP}}_S)\end{array}\right.$

In formula: Δ T _m: metal tube temperature deviation; Δ Ps: secondary circuit vapor pressure deviation; Δ y: valve opening deviation; τ _p: primary Ioops cooling medium time constant; τ _m: metal tube time constant; τ _ps: secondary circuit steaming time constant; k _pm: metal tube temperature coefficient; k _pc: hot line temperature coefficient; k _mp: coolant temperature coefficient; k _ms: pressure-temperature coefficient; k _psm: metal tube pressure coefficient; k _psy: valve pressure coefficient.

5. nuclear power generating sets power according to claim 3, electrically hybrid simulation platform, is characterized in that:

The described constant scheme of reactor control system model cooling medium medial temperature, this temperature constant scheme cooling medium medial temperature is not exerted oneself with nuclear power station and is changed, favourable to primary Ioops system.

6. nuclear power generating sets power according to claim 3, electrically hybrid simulation platform, is characterized in that:

Described cooling medium main pump mathematical model:

$T_{\mathrm{jp}}\frac{{\mathrm{d\ω}}_p}{\mathrm{dt}}=M_{\mathrm{pe}}-M_{\mathrm{pm}}$

$M_{\mathrm{pe}}=k_{e1}\frac{U_{1*}^2(1-\frac{{\mathrm{\ω}}_{p*}}{f_{1*}})}{[1+k_{e2}{f_{1*}^2(1-\frac{w_{p*}}{f_{1*}})}^2]f_{1*}}$

$M_{\mathrm{pm}}={\mathrm{\ω}}_p^2$

$\frac{\stackrel{\·}{m_c}}{\stackrel{\·}{m_{\mathrm{cn}}}}=\frac{{\mathrm{\ω}}_p}{{\mathrm{\ω}}_{\mathrm{pn}}}$

In formula: ω _p: main pump frequency; M _pe: main pump electromagnetic torque; M _pm: main pump mechanical output; f _1*: station service bus frequency; U _1*station service busbar voltage.

7. nuclear power generating sets power according to claim 1, electrically hybrid simulation platform, is characterized in that:

Power is passed to synchronous generator by torque patterns as power section by steam turbine by presurized water reactor, generates electricity and is transported to electrical network, and mains frequency and Feedback of Power are then changed the reaction of presurized water reactor power to turbine system by generator; During nuclear power generating sets load carrying, be connected by generator with between electrical network; Generator is contacted by steam turbine and speed regulator thereof and nuclear reactor system; The steam turbine structure of PWR nuclear power plant is 4 cylinders double fluid resuperheat condensing-type saturated steam turbines, adopts power and frequency electric-liquid type speed regulator, can the change of responding power and frequency; The information that nuclear power plant outputs to electrical network only has the mechanical output of steam turbine, and the information that electrical network is input to nuclear power plant has rotating speed and the active power of generator, and is connected by generator, and generator is contacted by steam turbine and speed regulator thereof and presurized water reactor.

8. nuclear power generating sets power according to claim 3, electrically hybrid simulation platform, is characterized in that:

Described steam turbine employing rotating speed is the Half Speed 4 cylinder double fluid resuperheat condensing-type saturated vapor turbine of fired power generating unit half, and speed regulator adopts merit electrohydraulic governor model frequently, is made up of tachometric survey and regulator, measurement of power unit, relay and hydraulic oil motor.