CN106297918A - A kind of output control device of supercritical electrical heating simulation transient state core heat release - Google Patents
A kind of output control device of supercritical electrical heating simulation transient state core heat release Download PDFInfo
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- CN106297918A CN106297918A CN201610929912.6A CN201610929912A CN106297918A CN 106297918 A CN106297918 A CN 106297918A CN 201610929912 A CN201610929912 A CN 201610929912A CN 106297918 A CN106297918 A CN 106297918A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/001—Mechanical simulators
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- Y—GENERAL 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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- General Engineering & Computer Science (AREA)
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Abstract
The invention discloses the output control device of a kind of supercritical electrical heating simulation transient state core heat release, adopt control module, power module including the core heat release analog module being sequentially connected with, measurement module, number；Core heat release analog module, controls dividual simulation and adds the transient power of the passage of heat；Measurement module, measures and adds the inlet flow rate of the passage of heat, the out temperature of fluid and the pressure of fluid；Number adopts control module, including the data collecting system being sequentially connected with, common calculation module, Reactivity feedback simulation, D/A output module；Power module, receives the analog quantity information that D/A output module provides, and is automatically adjusted dividual simulation and adds the power distribution of the passage of heat.The output control device of supercritical electrical heating of the present invention simulation transient state core heat release, the heating power that core heat release analog module adds the passage of heat is controlled, realize the reactive automatic feedback control to power of density, can be used for using the transient state physically and thermally work characteristic out-of-pile test under electrical heating Simulation Core core heat release.
Description
Technical field
The present invention relates to the power control techniques of electrical heating simulation transient state core heat release, be specifically related to a kind of supercritical electrical heating
The output control device of simulation transient state core heat release.
Background technology
Supercritical-Pressure Light Water Cooled Reactor is unique selected water cooled reator in the 4th generation of technology such as nuclear energy system.Owing to core structure is complicated, discrepancy
Mouth coolant density difference is relatively big, there is the crisis that out-phase flow instability occurs in reactor core.It addition, coolant density is violent
Change changes the field, slowing-down cross-section of reactor core, affects the power distribution of reactor core, changes the Density Distribution of coolant, thus formed
The special nuclear heat coupling feature that Supercritical-Pressure Light Water Cooled Reactor is potential, causes increase and the heap interior-heat of flow instability occurrence probability
The increase of work hydraulic parameters oscillation amplitude, affects the thermal-hydraulic safety of reactor.Therefore, in order to ensure Supercritical-Pressure Light Water Cooled Reactor
Safe operation, needs to carry out the nuclear heat Coupled Flow unstability experimentation of parallel port under super critical condition.
In Experiment of Thermophysics, need to simulate transient state core heat release with electrical heating, to reflect the nuclear heat coupling rule in actual reactor core
Rule.Need based on engineering background herein, propose a kind of novel supercritical electrical heating mould by technological innovation and experimental verification
Intend the output control device of transient state core heat release.
Summary of the invention
Present invention aim at providing the output control device of a kind of supercritical electrical heating simulation transient state core heat release, it is achieved thing
Reason calculates the coupling test simulation with thermal technology's phenomenon, with Transient Thermal waterpower and neutron thing under feedback condition strong in research reactor
Reason Parameters variation characteristic, provides experimental technique means for the economy and safety optimizing novel heap, is automatically adjusted bringing-up section
Power is distributed, thus realizes utilizing the power of electrical heating simulation transient state nuclear heat to control, and solves owing to core structure gateway is cold
But agent density acute variation, affects the power distribution of reactor core, increases thermal technology's hydraulic parameters in flow instability occurrence probability, heap
The technique of experimental simulation problems such as shock range increase.
The present invention is achieved through the following technical solutions:
The output control device of a kind of supercritical electrical heating simulation transient state core heat release, including the core heat release simulation mould being sequentially connected with
Block, measurement module, number adopt control module, power module；
Core heat release analog module, controls dividual simulation and adds the transient power of the passage of heat；
Measurement module, measures and adds the inlet flow rate of the passage of heat, the out temperature of fluid and pressure；
Number adopt control module, including the data collecting system being sequentially connected with, common calculation module, Reactivity feedback analog module,
D/A output module, the information of measurement module collection is transferred to common calculation module and carries out energy equation meter by data collecting system
Calculate, obtain the temperature parameter of experimental section and the fluid density information along journey, and by Reactivity feedback analog module, it is thus achieved that power
Change information, and through D/A output module, digital information is converted to analog quantity information；
Power module, receives the analog quantity information that D/A output module provides, and is automatically adjusted dividual simulation and adds the power of the passage of heat and divide
Cloth.
In prior art, supercritical water reactor, owing to core structure is complicated, gateway coolant density difference is relatively big, causes water-cooled
Heap core power non-uniform Distribution vertically, and then cause reactor core water parallel port flow instability.In Experiment of Thermophysics at present
The flowing instability Journal of Sex Research carried out, typically uses the simulation realized under the conditions of non-uniform wall thickness power non-uniform Distribution,
This mode can only obtain one group of fixing power distribution for a passage, it is impossible to realize the transient control to power distribution and
Orientation adjustment.
Inventor finds through a large amount of technological innovations and experimental verification, uses water parallel port stepwise adjustable electricity-saving heating dress
Put, water parallel port is carried out zone heating, and control device by the present invention every section of heating power is carried out independent transient state tune
Joint, thus meet in reactor thermo-hydraulics experimentation the simulation to non-uniform heating experiment condition.
The Poewr control method of supercritical electrical heating of the present invention simulation transient state core heat release is: to water parallel port
During zone heating, use measurement module, measure water parallel connection and add the inlet flow rate of the passage of heat, the out temperature of fluid, stream
The pressure of body i.e. fluid pressure and other parameters within adding the passage of heat, and the parameter information that this is recorded be transferred to number adopt control mould
Block, adopts the process of control module data through number and is converted to the receivable analog quantity information of power module, and power module is according to reception
Analog quantity information is automatically adjusted the power distribution of corresponding heating parallel port segmentation, thus realizes utilizing heating simulation transient state core to release
The power of heat controls.
Wherein, number is adopted the concrete data handling procedure of control module and is: number adopts the data acquisition that control module includes being sequentially connected with
Collecting system, common calculation module, Reactivity feedback analog module, D/A output module, measurement module measures the parameter information obtained
It is transferred to common calculation module after conversion, obtains temperature parameter and the density information of fluid of each experimental section of zone heating, so
After solved one-dimensional neutron-transport equation by Reactivity feedback analog module, obtain changed power information, then through D/A output module
Changed power information is converted to analog quantity information by digital information, it is provided that to power module.
The technical program center heat release analog module is the fuel assembly of reactor core or reactor, for the public affairs in core field
Know general knowledge；Measurement module is NI data collecting system, can add the import and export of the inlet temperature of the passage of heat, fluid accordingly by Quick Acquisition
Pressure within adding the passage of heat of temperature, fluid or fluid are in other physical parameters such as pressure of whole experimental loop, and are ability
The prior art in territory, its structure and principle no longer describe in detail；Data collecting system, the parameter mainly obtained from measurement module measurement
Extract in information, such as extract the flow parameter of core heat release analog module entrance, import and export fluid temperature (F.T.) parameter etc., its particular type
Number can be the data collecting card of DT9828, it is possible to for the data collecting system of NI-CRIO series；The main work of common calculation module
Be by from data acquisition system to the signal such as magnitude of voltage be converted to the signal such as temperature, pressure and flow of reality, logical
The existing equipment being known in the art with computing module, its structure and principle thereof are the common knowledge of art, no longer describe in detail.
Reactivity feedback analog module, extracts temperature parameter that common calculation module calculates, fluid along the density of journey
Information, by solving neutron-transport equation, it is thus achieved that changed power information, and the physical computing model used in the technical program is
One-dimensional neutron-transport equation, relative to the Point reactor nutron kinetics equation of the zero dimension used in prior art, one-dimensional neutron transport
Equation for Calculating is more accurate, has taken into full account that heating power edge adds the Changing Pattern of passage of heat axial direction, can be the truest
Reaction prototype reactor reactor core in the axial distribution situation of power.It is existing that Reactivity feedback analog module is known in the art
Equipment, its structure and principle thereof are the common knowledge of art, no longer describe in detail.
D/A output module, is converted into the corresponding signal of telecommunication by the changed power information that Reactivity feedback analog module obtains,
And flow to power module, the change heating power that power module is real-time, thus realize the nuclear reactivity feedback effect to power.
D/A output module, also known as D/A modular converter, converts digital signals into analogue signal.
Further, described power module is programmable modularized DC source, and programmable modularized DC source passes through
Direct current power control module carries out power control, the analog quantity that programmable modularized DC source carries according to D/A output module
Information, the power distribution of the fire end of regulation core heat release analog module, the control to simulation transient state core heat release power.
Further, described measurement module is NI data collecting system.One end of measurement module is connected with experimental stand, gathers
Thermal-hydraulic parameter in test loop, the other end is connected with the Feedback of Power program controlled in computer, the parameter that will gather
It is input to Power control procedures.And NI data collecting system, frequency acquisition is high, it is possible to reach 10 times per second, it is possible to truly reflect
The dynamic characteristic of Supercritical-Pressure Light Water Cooled Reactor, and in prior art, a long period nuclear reactivity is the most slow to the feedback procedure of power
Slowly, the most slowly, the persistent period is up to more than 600s in the change of heating power, it is impossible to true reflection Supercritical-Pressure Light Water Cooled Reactor flowing
Instable dynamic characteristic.
Further, described core heat release analog module is the fuel assembly of nuclear reactor or reactor.Core heat release mould
Plan module, as core heat release analog section, is two parallel ports, it is adaptable under super critical condition, core heat release Coupled Flow is unstable
Journal of Sex Research, it is possible to bear the pressure of 25MPa and the high temperature of 500 DEG C.
Further, what described core heat release analog module included two parallel connections adds the passage of heat, adds and arranges at least three in the passage of heat
Individual conducting copper, connects a power module respectively between adjacent conductive copper bar.
Further, described in add the port of export of the passage of heat and be connected with heat exchanger, storage tank successively, storage tank passes through plunger displacement pump
It is connected with the entrance point adding the passage of heat.
The present invention compared with prior art, has such advantages as and beneficial effect:
(1) present invention uses NI data collecting system as measurement module, and that quickly measures core heat release analog module adds the passage of heat
Inlet flow rate, import and export fluid temperature (F.T.), acquisition rate is faster than the transformation period yardstick of Transient Thermal phenomenon, can true and accurate anti-
Reflect actual transient changing rule.
(2) output control device of supercritical electrical heating transient simulation core heat release of the present invention, uses number to adopt control module, can
The parameter information of measurement module collection is converted to be supplied directly to the simulation of power module after volume of data processes
Amount information, power module can realize that corresponding heating region is added the passage of heat and heat, simultaneously can be according to analog quantity information
Change adjusts the power distribution adding passage of heat bringing-up section, thus realizes utilizing the power of electrical heating simulation transient state core heat release to control.
(3) output control device of supercritical electrical heating of the present invention simulation transient state core heat release, connects including certain signal and closes
The measurement module of system, number is adopted control module, power module, core heat release analog module, core heat release analog module is added the passage of heat
Heating power be controlled, it is achieved the reactive automatic feedback control to power of density, can be used for using electrical heating simulation heap
Transient state under core heat release physically and thermally work characteristic out-of-pile test.
Accompanying drawing explanation
Accompanying drawing described herein is used for providing being further appreciated by the embodiment of the present invention, constitutes of the application
Point, it is not intended that the restriction to the embodiment of the present invention.In the accompanying drawings:
Fig. 1 is the structural schematic block diagram of the present invention；
Fig. 2 is the core heat release analog module block diagram of the embodiment of the present invention 3；
Fig. 3 is the output control device control method flow chart of the embodiment of the present invention 5.
Detailed description of the invention
For making the object, technical solutions and advantages of the present invention clearer, below in conjunction with embodiment and accompanying drawing, to this
Invention is described in further detail, and the exemplary embodiment of the present invention and explanation thereof are only used for explaining the present invention, do not make
For limitation of the invention.
Embodiment 1:
As it is shown in figure 1, the output control device of the present invention a kind of supercritical electrical heating simulation transient state core heat release, including being sequentially connected with
Core heat release analog module, measurement module, number adopt control module, power module；
Core heat release analog module, controls dividual simulation and adds the transient power of the passage of heat；
Measurement module, measures and adds the inlet flow rate of the passage of heat, the out temperature of fluid and pressure；
Number adopt control module, including the data collecting system being sequentially connected with, common calculation module, Reactivity feedback simulation, D/A defeated
Going out module, the information of measurement module collection is transferred to conventional data module and carries out energy equation calculating by data collecting system,
To the temperature parameter of experimental section and fluid along the density information of journey, and by Reactivity feedback analog module, it is thus achieved that changed power
Information, and through D/A output module, digital information is converted to analog quantity information；
Wherein, power module is programmable modularized DC source, and programmable modularized DC source passes through DC power control
Module carries out power control.
Wherein, described measurement module is NI data collecting system.
In the present embodiment, core heat release analog module is reactor core.
Embodiment 2:
The present embodiment is in place of the difference of embodiment 1: core heat release analog module is the fuel assembly of reactor, and will implement
The output control device of the supercritical electrical heating simulation transient state core heat release described in example 1 controls for the power of fuel assembly.
Embodiment 3:
As in figure 2 it is shown, the present embodiment is in place of the difference of embodiment 1: core heat release analog module includes two heating in parallel
Passage, adds and arranges at least three conducting copper in the passage of heat, connects a power module between adjacent conductive copper bar respectively, and will be real
Execute the supercritical electrical heating described in example 1 and simulate the output control device of transient state core heat release for the mould of core heat release described in the present embodiment
The power intending module controls.
Concrete operation method is: connect a power module, NI data acquisition system between adjacent two conducting coppers
Adding the inlet flow rate of the passage of heat and import and export the temperature of fluid, number adopts the data collecting system of control system from NI data acquisition system
The inlet flow rate of the passage of heat, the out temperature of fluid, fluid is added in the pressure of experimental loop or heating needed for system extracts
The pressure and other parameters information of inner fluid passage, after conversion, calculates through conventional data and obtains the temperature parameter of experimental section, fluid density
Information, by this parameter information by solving one-dimensional neutron transport equation, obtains heating channel power change information, then by D/A
Digital information is lived where to be changed to analog quantity information by output module, it is provided that give corresponding power module, power module with add the passage of heat
One_to_one corresponding, direct current power control module can be according to the analog quantity information being supplied to by controlling DC source and then controlling heating
The power distribution of passage, thus realize utilizing the power of electrical heating simulation transient state core heat release to control.
Embodiment 4:
The present embodiment limits on the basis of embodiment 3 further, described in add the port of export of the passage of heat successively with heat exchanger, water storage
Case connects, and storage tank is connected with the entrance point adding the passage of heat by plunger displacement pump, constitutes the closed circuit of core heat release simulation experiment.
Embodiment 5:
Using a kind of supercritical electrical heating described in above-described embodiment to simulate the output control device of transient state core heat release, it is specifically controlled
Method processed is as it is shown on figure 3, in the case of the stable operation of test loop, start core heat release Power control procedures, owing to now returning
Road stable operation, core heat release module heating power is steady state value.Now give the disturbance of one, loop, such as, reduce loop flow, number
The flow in new moment, temperature, pressure and power will be gathered according to acquisition system.Meanwhile, these are collected by common calculation module
Voltage signal be converted into real flow value, force value, temperature value, performance number, and by the transmission of these parameters to reactive anti-
Feedback module.Reactivity feedback analog module carries out the power calculation based on one-dimensional neutron-transport equation and energy equation, obtains new
The performance number in moment, and this value is transmitted to direct current power control module by D/A output module, it is achieved electrical heating simulation core is released
The transient power of heat controls.
In the present embodiment, one-dimensional neutron transport equation and energy equation are the common knowledge of this area, no longer describe in detail.
Above-described detailed description of the invention, has been carried out the purpose of the present invention, technical scheme and beneficial effect further
Describe in detail, be it should be understood that the detailed description of the invention that the foregoing is only the present invention, be not intended to limit the present invention
Protection domain, all within the spirit and principles in the present invention, any modification, equivalent substitution and improvement etc. done, all should comprise
Within protection scope of the present invention.
Claims (6)
1. the output control device of supercritical electrical heating simulation transient state core heat release, it is characterised in that: include being sequentially connected with
Core heat release analog module, measurement module, number adopt control module, power module；
Core heat release analog module, controls dividual simulation and adds the transient power of the passage of heat；
Measurement module, measures and adds the inlet flow rate of the passage of heat, the out temperature of fluid and pressure；
Number adopt control module, including the data collecting system being sequentially connected with, common calculation module, Reactivity feedback analog module,
D/A output module, the parameter of measurement module collection is transferred to common calculation module and carries out energy equation meter by data collecting system
Calculate, obtain the temperature parameter of experimental section and the fluid density information along journey, and by Reactivity feedback analog module, it is thus achieved that power
Change information, and through D/A output module, digital information is converted to analog quantity information；
Power module, receives the analog quantity information that D/A output module provides, and regulation dividual simulation adds the power distribution of the passage of heat.
The output control device of a kind of supercritical electrical heating the most according to claim 1 simulation transient state core heat release, its feature
Being: described power module is programmable modularized DC source, programmable modularized DC source passes through DC power control
Module carries out power control.
The output control device of a kind of supercritical electrical heating the most according to claim 2 simulation transient state core heat release, its feature
It is: described measurement module is NI data collecting system.
The output control device of a kind of supercritical electrical heating the most according to claim 1 simulation transient state core heat release, its feature
It is: described core heat release analog module is the fuel assembly of nuclear reactor or reactor.
The output control device of a kind of supercritical electrical heating the most according to claim 1 simulation transient state core heat release, its feature
It is: what described core heat release analog module included two parallel connections adds the passage of heat, adds and arranges at least three conducting copper, phase in the passage of heat
A power module is connected respectively between adjacent conducting copper.
The output control device of a kind of supercritical electrical heating the most according to claim 5 simulation transient state core heat release, its feature
Be: described in add the port of export of the passage of heat and be connected with heat exchanger, storage tank successively, storage tank is by plunger displacement pump and adds the passage of heat
Entrance point connects.
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Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107945896A (en) * | 2017-11-10 | 2018-04-20 | 中国科学院近代物理研究所 | A kind of application method of high temperature and pressure water flow bulk effect simulator |
| CN112326286A (en) * | 2020-10-27 | 2021-02-05 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | Rod-shaped fuel element transient heat release simulation experiment device and method |
| CN114999687A (en) * | 2022-05-31 | 2022-09-02 | 中国核动力研究设计院 | Electric power adjusting method and system for nuclear reactor thermal hydraulic transient test |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0643282A (en) * | 1992-07-22 | 1994-02-18 | Ishikawajima Harima Heavy Ind Co Ltd | Hydrothermal force mock-up test device for integral pressurized water reactor |
| JPH11142579A (en) * | 1997-11-05 | 1999-05-28 | Mitsubishi Heavy Ind Ltd | Deterioration evaluation device of steam generator heat transfer tube |
| CN105225709A (en) * | 2015-08-26 | 2016-01-06 | 西南石油大学 | The reactor core electrical heating elements method for designing of Natural Circulation and forced circulation circuit system |
| CN105869685A (en) * | 2016-04-06 | 2016-08-17 | 哈尔滨工程大学 | Thermal hydraulic experiment device and method for simulating nuclear reactor neutron reactivity feedback process |
| CN105957568A (en) * | 2016-07-07 | 2016-09-21 | 中国核动力研究设计院 | System and method for simulating nuclear heat releasing by electric heating |
-
2016
- 2016-10-31 CN CN201610929912.6A patent/CN106297918B/en active Active
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0643282A (en) * | 1992-07-22 | 1994-02-18 | Ishikawajima Harima Heavy Ind Co Ltd | Hydrothermal force mock-up test device for integral pressurized water reactor |
| JPH11142579A (en) * | 1997-11-05 | 1999-05-28 | Mitsubishi Heavy Ind Ltd | Deterioration evaluation device of steam generator heat transfer tube |
| CN105225709A (en) * | 2015-08-26 | 2016-01-06 | 西南石油大学 | The reactor core electrical heating elements method for designing of Natural Circulation and forced circulation circuit system |
| CN105869685A (en) * | 2016-04-06 | 2016-08-17 | 哈尔滨工程大学 | Thermal hydraulic experiment device and method for simulating nuclear reactor neutron reactivity feedback process |
| CN105957568A (en) * | 2016-07-07 | 2016-09-21 | 中国核动力研究设计院 | System and method for simulating nuclear heat releasing by electric heating |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107945896A (en) * | 2017-11-10 | 2018-04-20 | 中国科学院近代物理研究所 | A kind of application method of high temperature and pressure water flow bulk effect simulator |
| CN112326286A (en) * | 2020-10-27 | 2021-02-05 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | Rod-shaped fuel element transient heat release simulation experiment device and method |
| CN114999687A (en) * | 2022-05-31 | 2022-09-02 | 中国核动力研究设计院 | Electric power adjusting method and system for nuclear reactor thermal hydraulic transient test |
| CN114999687B (en) * | 2022-05-31 | 2024-05-07 | 中国核动力研究设计院 | Nuclear reactor thermal hydraulic transient test electric power adjusting method and system |
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