CN106340329B - Reactor thermo-hydraulics simulation test device and hydrodynamic characteristics analogy method - Google Patents

Reactor thermo-hydraulics simulation test device and hydrodynamic characteristics analogy method Download PDF

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Publication number
CN106340329B
CN106340329B CN201610930458.6A CN201610930458A CN106340329B CN 106340329 B CN106340329 B CN 106340329B CN 201610930458 A CN201610930458 A CN 201610930458A CN 106340329 B CN106340329 B CN 106340329B
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reactor
pump
resistance
analogue body
cold section
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CN106340329A (en
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唐瑜
黄彦平
徐建军
谢添舟
谭曙时
彭兴建
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Nuclear Power Institute of China
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Nuclear Power Institute of China
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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/001Mechanical simulators
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/017Inspection or maintenance of pipe-lines or tubes in nuclear installations
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Abstract

The invention discloses reactor thermo-hydraulics simulation test device, including reactor analogue body, steam generator analogue body and main circulation pump, wherein, steam generator analogue body entrance and exit is exported by pipeline and reactor analogue body respectively, main circulation pump entrance is connected, and main circulation pump outlet is connected by pipeline and reactor analogue body entrance.Pipeline between steam generator analogue body entrance and the outlet of reactor analogue body is provided with hot arc resistance regulation part, the pipeline that steam generator analogue body is exported between main circulation pump entrance is provided with cold section of resistance regulation part and check-valves, and the pipeline between main circulation pump outlet and reactor analogue body entrance is provided with pump roadlock power regulating part and Venturi meter.The invention also discloses the hydrodynamic characteristics analogy method based on above-mentioned reactor thermo-hydraulics simulation test device.It is convenient to carry out when hydrodynamic characteristics are adjusted into consistent with reactor prototype during present invention application, the test efficiency of simulated test can be lifted.

Description

Reactor thermo-hydraulics simulation test device and hydrodynamic characteristics analogy method
Technical field
The present invention relates to reactor thermo-hydraulics and security technology area, specifically reactor thermo-hydraulics simulated test fills Put and hydrodynamic characteristics analogy method.
Background technology
In existing large nuclear power station or nuclear power unit, various therrmodynamic systems it is huge, it is difficult to use full-scale mould The mode of plan carries out experiment.Therefore, filled frequently with the systems modelling that prototype is carried out to contracting ratio according to certain simulation rules Put the hot-working hydraulic characteristic for carrying out research reactor system.It is accurate that conventional simulation rules include geometric similarity criterion, kinematic similarity Then and the equal criterion of related dimensionless crack length, wherein, kinematic similarity criterion need to ensure when applying simulation test device with it is former The hydrodynamic characteristics of type are consistent.Due to simulation test device in physical dimension it is different from prototype, experimental rig need to be entered Row hydrodynamic characteristics are simulated, and control it consistent with the dynamics of prototype plant.Existing reactor thermo-hydraulics system mould When intending experimental rig application, process is relatively complicated when hydrodynamic characteristics are adjusted into consistent with prototype, and this has a strong impact on The test efficiency of simulated test.
The content of the invention
It is an object of the invention to overcome the deficiencies of the prior art and provide a kind of reactor thermo-hydraulics simulated test dress Put, it is convenient to carry out when hydrodynamic characteristics are adjusted into consistent with reactor prototype, can lift the experiment effect of simulated test Rate.The invention also discloses the hydrodynamic characteristics analogy method of above-mentioned experimental rig.
The present invention, which solves the above problems, to be achieved through the following technical solutions:Reactor thermo-hydraulics simulated test fills Put, including reactor analogue body, steam generator analogue body and main circulation pump, the steam generator analogue body entrance and exit Connected respectively by pipeline and the outlet of reactor analogue body, main circulation pump entrance, the main circulation pump outlet is by pipeline and instead Heap analogue body entrance is answered to connect;Pipeline between steam generator analogue body entrance and reactor the analogue body outlet is provided with Hot arc resistance regulation part, the pipeline between the steam generator analogue body outlet and main circulation pump entrance are provided with cold section of resistance Regulating part and check-valves, the check-valves between cold section of resistance regulation part and main circulation pump, main circulation pump outlet with Pipeline between reactor analogue body entrance is provided with pump roadlock power regulating part and Venturi meter, pump road resistance regulation Part is between main circulation pump and Venturi meter.Reactor-loop is divided into pump road and Fei Beng roads during present invention application to enter Row hydrodynamic characteristics are simulated, wherein, pump road includes main circulation pump, check-valves, pump roadlock power regulating part and connection three Pipeline, the primary Ioops other parts in addition to pump road are Fei Beng roads.Under forced circulation operating mode, operate and produce by main circulation pump Regime flow, Fei Beng roads are carried out to be segmented hydrodynamic characteristics simulation.It is different according to fluid density, Fei Beng roads are divided into two Section, first paragraph include hot arc pipeline(Reactor analogue body is exported to evaporator analogue body entrance pipeline section)With reactor analogue body, It is referred to as hot arc.Second segment includes cold segment pipe(Evaporator analogue body is exported to check-valves entrance pipeline section)With steam generator mould Intend body, be referred to as cold section.Under the conditions of Natural Circulation, by the Cool Hot Core discrepancy in elevation and density of simulation test device of the present invention Gravity head caused by difference produces stable natural circulation flow, and hydrodynamic characteristics simulation is carried out to pump road.Wherein, cold core For the geometric center of steam generator analogue body, hot core is the geometric center of reactor analogue body reactor core.
In order that it is easy to test pressure differential during present invention application, and further, reactor thermo-hydraulics simulation test device, also Including hot arc pressure difference transmitter, cold section of pressure difference transmitter and pump road pressure difference transmitter, the hot arc pressure difference transmitter and pump road pressure Pipeline of the positive pressure side of both poor transmitters between pump roadlock power regulating part and Venturi meter is connected, hot arc pressure difference pick-up Both device and cold section of pressure difference transmitter pipeline of the negative pressure end between hot arc resistance regulation part and steam generator analogue body connect Logical, the positive pressure side of cold section of pressure difference transmitter and pump road pressure difference transmitter negative pressure end are between cold section of resistance regulation part and check-valves Pipeline is connected.
Further, reactor thermo-hydraulics simulation test device, in addition to voltage-stablizer, the voltage-stablizer and reaction heap mould The outlet for intending body is connected.Can be by adjusting the water level of voltage-stablizer, to the reference pressure of reactor analogue body during present invention application It is adjusted.
Further, the hot arc resistance regulation part, cold section of resistance regulation part and pump roadlock power regulating part use orifice plate. The present invention is using orifice plate as resistance regulation part, and dismounting is convenient, and during experiment, its hydrodynamic characteristics will not occur Change, reliability are high.
Based on the hydrodynamic characteristics analogy method of above-mentioned reactor thermo-hydraulics simulation test device, including Fei Beng roads Hydrodynamic characteristics are simulated and the simulation of pump road hydrodynamic characteristics;
Fei Beng roads hydrodynamic characteristics simulation comprises the following steps:
Step A1, hot arc resistance regulation part and cold section of resistance are determined according to the forced circulation base operation condition of reactor-loop The resistance coefficient value reached needed for both regulating parts, and adjust hot arc resistance regulation part and cold section of resistance regulation part reaches required Resistance coefficient value;
Step A2, start main circulation pump, regulation flow to standard flow, adjust reactor thermo-hydraulics simulation test device Reactor analogue body its temperature and pressure is reached a reference value;
Step A3, hot arc pressure drop, cold section of pressure drop are gathered, and using Venturi meter collection flow, then according to test Value calculates hot arc and cold section of resistance coefficient;
Step A4, by the hot arc calculated and cold section of resistance coefficient and the resistance coefficient target value of setting, if partially Difference is in the error range of permission, then hydrodynamic characteristics simulation is completed, otherwise, according to the big minor adjustment hot arc resistance of deviation Regulating part and cold section of resistance regulation part, repeat step A3~A4, untill error range of the resistance coefficient in permission;
Pump road hydrodynamic characteristics simulation comprises the following steps:
Step B1, reach according to needed for the Natural Circulation base operation condition of reactor-loop determines pump roadlock power regulating part Resistance coefficient value, and controlling pump roadlock power regulating part reaches required resistance coefficient value;
Step B2, adjusting the reactor analogue body of reactor thermo-hydraulics simulation test device makes its pressure and mean temperature Reach a reference value;
Step B3, pump road pressure drop is gathered, and using Venturi meter collection flow, pump is then calculated according to test value The resistance coefficient on road;
Step B4, by the resistance coefficient on the pump road calculated and the resistance coefficient target value of setting, if deviation is permitting Perhaps in error range, the hydrodynamic characteristics simulation on Ze Beng roads is completed, otherwise, according to the big minor adjustment pump roadlock power of deviation Regulating part, repeat step B3~B4, untill error range of the pump roadlock force coefficient in permission.The present invention is in forced circulation bar Under part, to each section of the primary Ioops in addition to pump road(Fei Beng roads)Carry out hydrodynamic characteristics simulation;It is right under the conditions of Natural Circulation Pump road carries out hydrodynamic characteristics simulation.The Fei Beng roads of the present invention carry out dividual simulation according to cold section and hot arc, not only ensure Loop total fluid dynamics is consistent with prototype, it is ensured that the hydrodynamics distribution character and prototype phase of experimental rig Seemingly, can more accurately mock-up reactor transient response.Therefore, according to the hydrodynamic characteristics analogy method of the present invention After carrying out hydrodynamic characteristics simulation, experimental rig can meet to carry out forced circulation and the stable state under naturally circulated condition and wink The requirement of state simulated test.
Further, the step A1 comprises the following steps:
Step A1.1, the base operation condition of forced circulation is determined according to reactor prototype primary Ioops operational factor, wherein, force The base operation condition of circulation includes the benchmark pressure drop on benchmark thermal parameter and reactor prototype Fei Beng roads;
Step A1.2, cold section of simulation test device and hot arc are calculated with benchmark thermal parameter according to benchmark pressure drop needed for reach The resistance coefficient desired value arrived;
Step A1.3, according to resistance coefficient desired value and the resistance coefficient without resistance regulation part front simulation experimental rig Difference obtains needing the resistance coefficient value provided by resistance regulation part;
Step A1.4, adjust hot arc resistance regulation part and cold section of resistance regulation part reaches the resistance coefficient value calculated.
Further, in the base operation condition of the forced circulation benchmark thermal parameter include standard flow, fiducial temperature and Reference pressure.
Further, the step B1 comprises the following steps:
Step B1.1, the base operation condition of Natural Circulation is determined according to reactor prototype primary Ioops operational factor, wherein, it is natural The base operation condition of circulation includes benchmark thermal parameter and the resistance coefficient on reactor prototype pump road;
Step B1.2, according to archetypal pump roadlock force coefficient and the resistance coefficient without resistance regulation part front simulation experimental rig Difference obtain needing the resistance coefficient value provided by resistance regulation part;
Step B1.3, regulation pump roadlock power regulating part reaches the resistance coefficient value calculated.
Further, benchmark thermal parameter includes average reactor temperature and operation in the base operation condition of the Natural Circulation Pressure.
In summary, the invention has the advantages that:(1)Simulation test device overall structure letter of the present invention It is single, it is easy to implement, cost is low, and the present invention passes through the pipe between steam generator analogue body entrance and the outlet of reactor analogue body Road is provided with cold on the pipeline provided with hot arc resistance regulation part, between the outlet of steam generator analogue body and main circulation pump entrance Section resistance regulation part and main circulation pump outlet reactor analogue body entrance between pipeline on be provided with pump road resistance regulation Part so that the present invention can meet the simulation requirement of dynamics under forced circulation and naturally circulated condition simultaneously, control fluid Simple operation when dynamics is consistent with prototype, it is convenient to carry out, the test efficiency of simulated test can be lifted.
(2)Fluid is carried out to the Fei Beng roads of reactor thermo-hydraulics systems modelling device and pump road during present invention application Dynamics is simulated, after completing hydrodynamic characteristics simulation, the hydrodynamic characteristics of experimental rig and reactor prototype Completely the same, stable state and transient simulation experiment for experimental rig development forced circulation or under naturally circulated condition have established base Plinth.
(3)The present invention carries out dividual simulation using Shi Feibeng roads according to cold section and hot arc, not only ensure that loop total fluid Dynamics is consistent with prototype, it is ensured that the hydrodynamics distribution character of experimental rig is similar to prototype, can be more The transient response of mock-up reactor exactly.
(4)The present invention it is versatile, cost is low, reliability is high, apply also for other heating power systems except out-of-pile The simulated test of system, there is preferable market application foreground.
Brief description of the drawings
Accompanying drawing described herein is used for providing further understanding the embodiment of the present invention, forms one of the application Point, do not form the restriction to the embodiment of the present invention.In the accompanying drawings:
Fig. 1 is the structural representation of reactor thermo-hydraulics simulation test device in a specific embodiment of the invention.
Corresponding parts title is marked in accompanying drawing:1st, reactor analogue body, 2, hot arc resistance regulation part, 3, steam hair Raw device analogue body, 4, cold section of resistance regulation part, 5, check-valves, 6, main circulation pump, 7, pump roadlock power regulating part, 8, venturi flow Meter, 9, hot arc pressure difference transmitter, 10, cold section of pressure difference transmitter, 11, pump road pressure difference transmitter, 12, voltage-stablizer.
Embodiment
For the object, technical solutions and advantages of the present invention are more clearly understood, with reference to embodiment and accompanying drawing, to this Invention is described in further detail, and exemplary embodiment of the invention and its explanation are only used for explaining the present invention, do not make For limitation of the invention.
Embodiment 1:
As shown in figure 1, reactor thermo-hydraulics simulation test device, including the simulation of reactor analogue body 1, steam generator Body 3 and main circulation pump 6, wherein, the entrance and exit of steam generator analogue body 3 is gone out by pipeline and reactor analogue body 1 respectively Mouth, the entrance of main circulation pump 6 are connected, and the outlet of main circulation pump 6 passes through pipeline and the connection of the entrance of reactor analogue body 1.The present embodiment Pipeline between the entrance of steam generator analogue body 3 and reactor analogue body 1 export is provided with hot arc resistance regulation part 2, steam The pipeline that generator analogue body 3 is exported between the entrance of main circulation pump 6 is provided with cold section of resistance regulation part 4 and check-valves 5, non-return Valve 5 is between cold section of resistance regulation part 4 and main circulation pump 6.The outlet of main circulation pump 6 and reactor analogue body 1 of the present embodiment Pipeline between entrance is provided with pump roadlock power regulating part 7 and Venturi meter 8, and pump roadlock power regulating part 7 is located at major cycle Between pump 6 and Venturi meter 8.
When the present embodiment is applied respectively under forced circulation operating mode and naturally circulated condition to reactor-loop system mould The Fei Beng roads and pump road for intending experimental rig carry out hydrodynamic characteristics simulation.It is true according to the operational factor of reactor prototype first The forced circulation base operation condition of Ding Feibeng roads simulation and the Natural Circulation base operation condition of pump road simulation.Meanwhile determine the non-pump of prototype The resistance or resistance coefficient of road and pump road under base operation condition, the mesh as the simulation of simulation test device hydrodynamic characteristics Mark.According to the difference of the existing resistance coefficient of device and target resistance coefficient, the resistance coefficient increment that orifice plate need to provide is calculated.With this For foundation, suitable orifice plate resistance piece is calculated and processes, and be placed on the appropriate location in loop.
Based on the hydrodynamic characteristics analogy method of above-mentioned reactor thermo-hydraulics simulation test device, including Fei Beng roads Hydrodynamic characteristics are simulated and the simulation of pump road hydrodynamic characteristics;Wherein, Fei Beng roads hydrodynamic characteristics simulation includes Following steps:Step A1, hot arc resistance regulation part 2 and cold section of resistance are determined according to the forced circulation base operation condition of reactor-loop The resistance coefficient value that power regulating part 4 reaches needed for both, and adjust hot arc resistance regulation part 2 and cold section of resistance regulation part 4 reaches Required resistance coefficient value;Step A2, start main circulation pump 6, regulation flow to standard flow, adjust reactor thermo-hydraulics mould Intending the reactor analogue body 1 of experimental rig makes its temperature and pressure reach a reference value;Step A3, hot arc pressure drop, cold section of pressure are gathered Drop, and flow is gathered using Venturi meter 8, hot arc and cold section of resistance coefficient are then calculated according to test value;Step A4, by the hot arc calculated and cold section of resistance coefficient and the resistance coefficient target value of setting, if deviation is in the mistake of permission In poor scope, then hydrodynamic characteristics simulation is completed, otherwise, according to the big minor adjustment hot arc resistance regulation part 2 of deviation and cold Section resistance regulation part 4, repeat step A3~A4, untill error range of the resistance coefficient in permission.
Step A1 comprises the following steps:Step A1.1, forced circulation is determined according to reactor prototype primary Ioops operational factor Base operation condition, wherein, the base operation condition of forced circulation includes benchmark thermal parameter and the base pressure on reactor prototype Fei Beng roads Drop;Step A1.2, reach according to needed for benchmark pressure drop and benchmark thermal parameter calculate cold section of simulation test device and hot arc Resistance coefficient desired value;Step A1.3, according to resistance coefficient desired value and the resistance without resistance regulation part front simulation experimental rig The difference of force coefficient obtains needing the resistance coefficient value provided by resistance regulation part;Step A1.4, hot arc resistance regulation is adjusted Part 2 and cold section of resistance regulation part 4 reach the resistance coefficient value calculated.Wherein, benchmark thermal technology in the base operation condition of forced circulation Parameter includes standard flow, fiducial temperature and reference pressure.
Cold section of resistance coefficient desired value calculation formula:
In formula, ρCLFor cold section of fluid density, Δ PCLFor cold section of benchmark pressure drop, ACLFor cold segment pipe circulation area, W is
Standard flow.
Hot arc resistance coefficient desired value calculation formula:
In formula, ρHLFor hot arc fluid density, Δ PHLFor hot arc benchmark pressure drop, AHLFor hot arc pipeline flow area, W is base
Quasi- flow.
The hydrodynamic characteristics simulation of pump road comprises the following steps:Step B1, according to the Natural Circulation of reactor-loop Base operation condition determines the resistance coefficient value reached needed for pump roadlock power regulating part 7, and controlling pump roadlock power regulating part 7 reaches required Resistance coefficient value;Step B2, adjusting the reactor analogue body 1 of reactor thermo-hydraulics simulation test device makes its pressure and puts down Equal temperature reaches a reference value;Step B3, pump road pressure drop is gathered, and flow is gathered using Venturi meter 8, then according to test Value calculates the resistance coefficient on pump road;Step B4, by the resistance coefficient on the pump road calculated and the resistance coefficient desired value of setting Contrast, if deviation, in the error range of permission, the hydrodynamic characteristics simulation on Ze Beng roads is completed, otherwise, according to deviation Big minor adjustment pump roadlock power regulating part 7, repeat step B3~B4, untill error range of the pump roadlock force coefficient in permission.
Step B1 specifically includes following steps:Step B1.1, nature is determined according to reactor prototype primary Ioops operational factor The base operation condition of circulation, wherein, the base operation condition of Natural Circulation includes benchmark thermal parameter and the resistance on reactor prototype pump road Coefficient;Step B1.2, according to archetypal pump roadlock force coefficient and the resistance coefficient without resistance regulation part front simulation experimental rig Difference obtains needing the resistance coefficient value provided by resistance regulation part;Step B1.3, adjust pump roadlock power regulating part 7 and reach meter The resistance coefficient value calculated.Wherein, benchmark thermal parameter includes average reactor temperature and fortune in the base operation condition of Natural Circulation Row pressure.
Pump roadlock force coefficient calculation formula is as follows:
In formula, ρPPFor pump road fluid density, tabled look-up acquisition by the temperature, pressure measured value of pump road fluid;ΔPPPFor pump road Drop measurement value, APPFor pump road pipeline flow area, W is flow measurements.
The present embodiment is in specific set, hot arc resistance regulation part 2, cold section of resistance regulation part 4 and pump roadlock power regulating part 7 Use orifice plate.When the present embodiment is implemented, orifice plate is gripped using two panels screwed flange.The present embodiment is adopted when applying With orifice plate resistance calculation formulae, by the pre- bore size for calculating hot arc resistance regulation part 2 of hot arc resistance coefficient increment, hindered by cold section Force coefficient increment and the bore size for calculating cold section of resistance regulation part 4 in advance, also using orifice plate resistance calculation formulae, calculate pump road in advance The bore size of resistance regulation part 7.
Orifice plate resistance coefficient calculation formula is as follows:
Wherein, K is orifice plate resistance coefficient, F1For upstream line circulation area, F0For orifice plate perforated area, D0Opened for orifice plate Bore dia, K0For intermediate variable, λ is frictional resistance system, L0For orifice plate thickness, G is mass velocity, and Re is Reynolds number, and μ is Power viscosity.
Exemplified by cold section, the determination method of orifice plate bore size is as follows:
The first step, determine that cold sector hole plate needs the target resistance COEFFICIENT K reached by cold section of resistance coefficient increment*
Second step, it is assumed that orifice plate opening diameter D0, orifice plate resistance coefficient K is calculated using above formula, with target resistance COEFFICIENT K*Than Relatively and iterate, finally make K and K*Difference within ± 1%, D now0For the bore size finally determined.
Embodiment 2:
The present embodiment is made that on the basis of embodiment 1 to be limited further below:The present embodiment also includes hot arc pressure difference Transmitter 9, cold section of pressure difference transmitter 10 and pump road pressure difference transmitter 11, wherein, hot arc pressure difference transmitter 9 and pump road pressure difference pick-up Both pipelines of positive pressure side between pump roadlock power regulating part 7 and Venturi meter 8 of device 11 are connected, hot arc pressure difference transmitter 9 and cold section of pressure difference transmitter 10 both pipelines of negative pressure end between hot arc resistance regulation part 2 and steam generator analogue body 3 Connect, cold section of 10 positive pressure side of pressure difference transmitter and the negative pressure end of pump road pressure difference transmitter 11 with cold section of resistance regulation part 4 and non-return Pipeline between valve 5 is connected.
Embodiment 3:
For the ease of adjusting the reference pressure of reactor analogue body 1, the present embodiment is on the basis of embodiment 1 or embodiment 2 On be made that and limit further below:The present embodiment also includes voltage-stablizer 12, wherein, voltage-stablizer 12 and reactor analogue body 1 Outlet is connected.
Above-described embodiment, the purpose of the present invention, technical scheme and beneficial effect are carried out further Describe in detail, should be understood that the embodiment that the foregoing is only the present invention, be not intended to limit the present invention Protection domain, within the spirit and principles of the invention, any modification, equivalent substitution and improvements done etc., all should include Within protection scope of the present invention.

Claims (8)

1. reactor thermo-hydraulics simulation test device, it is characterised in that including reactor analogue body(1), steam generator mould Intend body(3)And main circulation pump(6), the steam generator analogue body(3)Entrance and exit passes through pipeline and reaction heap mould respectively Intend body(1)Outlet, main circulation pump(6)Entrance is connected, the main circulation pump(6)Outlet passes through pipeline and reactor analogue body(1) Entrance is connected;The steam generator analogue body(3)Entrance and reactor analogue body(1)Pipeline between outlet is provided with hot arc Resistance regulation part(2), the steam generator analogue body(3)Outlet and main circulation pump(6)Pipeline between entrance is provided with cold Section resistance regulation part(4)And check-valves(5), the check-valves(5)Positioned at cold section of resistance regulation part(4)With main circulation pump(6)It Between, the main circulation pump(6)Outlet and reactor analogue body(1)Pipeline between entrance is provided with pump roadlock power regulating part(7) And Venturi meter(8), the pump roadlock power regulating part(7)Positioned at main circulation pump(6)With Venturi meter(8)Between;
Also include hot arc pressure difference transmitter(9), cold section of pressure difference transmitter(10)And pump road pressure difference transmitter(11), the hot arc pressure Poor transmitter(9)With pump road pressure difference transmitter(11)Both positive pressure sides with pump roadlock power regulating part(7)And Venturi meter (8)Between pipeline connect, hot arc pressure difference transmitter(9)With cold section of pressure difference transmitter(10)Both negative pressure ends with hot arc resistance Regulating part(2)With steam generator analogue body(3)Between pipeline connect, cold section of pressure difference transmitter(10)Positive pressure side and pump road pressure Poor transmitter(11)Negative pressure end with cold section of resistance regulation part(4)And check-valves(5)Between pipeline connect.
2. reactor thermo-hydraulics simulation test device according to claim 1, it is characterised in that also including voltage-stablizer (12), the voltage-stablizer(12)With reactor analogue body(1)Outlet connect.
3. reactor thermo-hydraulics simulation test device according to claim 1 or 2, it is characterised in that the hot arc resistance Power regulating part(2), cold section of resistance regulation part(4)And pump roadlock power regulating part(7)Use orifice plate.
4. the hydrodynamics based on the reactor thermo-hydraulics simulation test device described in any one in claims 1 to 3 Simulated behavior method, it is characterised in that including the simulation of Fei Beng roads hydrodynamic characteristics and the simulation of pump road hydrodynamic characteristics;
Fei Beng roads hydrodynamic characteristics simulation comprises the following steps:
Step A1, hot arc resistance regulation part is determined according to the forced circulation base operation condition of reactor-loop(2)With cold section of resistance Regulating part(4)The resistance coefficient value reached needed for both, and adjust hot arc resistance regulation part(2)With cold section of resistance regulation part(4) Reach required resistance coefficient value;
Step A2, main circulation pump is started(6), regulation flow to standard flow, adjust reactor thermo-hydraulics simulation test device Reactor analogue body(1)Its temperature and pressure is set to reach a reference value;
Step A3, hot arc pressure drop, cold section of pressure drop are gathered, and uses Venturi meter(8)Flow is gathered, then according to test value Calculate hot arc and cold section of resistance coefficient;
Step A4, by the hot arc calculated and cold section of resistance coefficient and the resistance coefficient target value of setting, if deviation exists In the error range of permission, then hydrodynamic characteristics simulation is completed, otherwise, according to the big minor adjustment hot arc resistance regulation of deviation Part(2)With cold section of resistance regulation part(4), repeat step A3~A4, untill error range of the resistance coefficient in permission;
Pump road hydrodynamic characteristics simulation comprises the following steps:
Step B1, pump roadlock power regulating part is determined according to the Natural Circulation base operation condition of reactor-loop(7)It is required to reach Resistance coefficient value, and controlling pump roadlock power regulating part(7)Reach required resistance coefficient value;
Step B2, the reactor analogue body of reactor thermo-hydraulics simulation test device is adjusted(1)Make its pressure and mean temperature Reach a reference value;
Step B3, pump road pressure drop is gathered, and uses Venturi meter(8)Flow is gathered, pump is then calculated according to test value The resistance coefficient on road;
Step B4, by the resistance coefficient on the pump road calculated with setting resistance coefficient target value, if deviation is in permission In error range, the hydrodynamic characteristics simulation on Ze Beng roads is completed, otherwise, according to the big minor adjustment pump road resistance regulation of deviation Part(7), repeat step B3~B4, untill error range of the pump roadlock force coefficient in permission.
5. hydrodynamic characteristics analogy method according to claim 4, it is characterised in that the step A1 includes following Step:
Step A1.1, the base operation condition of forced circulation is determined according to reactor prototype primary Ioops operational factor, wherein, forced circulation Base operation condition include the benchmark pressure drop on benchmark thermal parameter and reactor prototype Fei Beng roads;
Step A1.2, reach according to needed for benchmark pressure drop and benchmark thermal parameter calculate cold section of simulation test device and hot arc Resistance coefficient desired value;
Step A1.3, according to resistance coefficient desired value and the difference of the resistance coefficient without resistance regulation part front simulation experimental rig Obtain needing the resistance coefficient value provided by resistance regulation part;
Step A1.4, hot arc resistance regulation part is adjusted(2)With cold section of resistance regulation part(4)Reach the resistance coefficient value calculated.
6. hydrodynamic characteristics analogy method according to claim 5, it is characterised in that the benchmark of the forced circulation Benchmark thermal parameter includes standard flow, fiducial temperature and reference pressure in operating mode.
7. hydrodynamic characteristics analogy method according to claim 4, it is characterised in that the step B1 includes following Step:
Step B1.1, the base operation condition of Natural Circulation is determined according to reactor prototype primary Ioops operational factor, wherein, Natural Circulation Base operation condition include the resistance coefficient on benchmark thermal parameter and reactor prototype pump road;
Step B1.2, according to the difference of archetypal pump roadlock force coefficient and the resistance coefficient without resistance regulation part front simulation experimental rig It is worth to the resistance coefficient value for needing to provide by resistance regulation part;
Step B1.3, pump roadlock power regulating part is adjusted(7)Reach the resistance coefficient value calculated.
8. hydrodynamic characteristics analogy method according to claim 7, it is characterised in that the benchmark of the Natural Circulation Benchmark thermal parameter includes average reactor temperature and operating pressure in operating mode.
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CN111781235A (en) * 2020-07-07 2020-10-16 西安交通大学 Experimental device and method for simulating thermal influence of fuel surface sediments on reactor core
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Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3916445A (en) * 1973-02-23 1975-10-28 Westinghouse Electric Corp Training simulator for nuclear power plant reactor coolant system and method
CN105225708A (en) * 2015-08-26 2016-01-06 西南石油大学 A kind of Natural Circulation and forced circulation experimental loop system
CN105788679A (en) * 2016-03-30 2016-07-20 中国核动力研究设计院 Simulation system and calibration method for hydrodynamic power of parallel pump system of primary coolant circuit of reactor

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5682410A (en) * 1995-10-17 1997-10-28 General Electric Company Method for determining core flow rate and water temperature/density in boiling water reactor
JP5727862B2 (en) * 2011-05-19 2015-06-03 富士電機機器制御株式会社 Magnetic contactor
CN103474110B (en) * 2013-08-26 2016-03-02 上海交通大学 High Temperature High Pressure nuclear reactor test loop device

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3916445A (en) * 1973-02-23 1975-10-28 Westinghouse Electric Corp Training simulator for nuclear power plant reactor coolant system and method
CN105225708A (en) * 2015-08-26 2016-01-06 西南石油大学 A kind of Natural Circulation and forced circulation experimental loop system
CN105788679A (en) * 2016-03-30 2016-07-20 中国核动力研究设计院 Simulation system and calibration method for hydrodynamic power of parallel pump system of primary coolant circuit of reactor

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