CN105159275A - Closed-loop test platform used for instrument and control system of nuclear reactor and driven by real-time simulation data - Google Patents

Closed-loop test platform used for instrument and control system of nuclear reactor and driven by real-time simulation data Download PDF

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CN105159275A
CN105159275A CN201510501933.3A CN201510501933A CN105159275A CN 105159275 A CN105159275 A CN 105159275A CN 201510501933 A CN201510501933 A CN 201510501933A CN 105159275 A CN105159275 A CN 105159275A
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real
reactor
data
module
time simulation
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CN105159275B (en
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杨明翰
汪建业
宋勇
徐鹏
王亮
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Hefei Institutes of Physical Science of CAS
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Hefei Institutes of Physical Science of CAS
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    • GPHYSICS
    • G05CONTROLLING; REGULATING
    • G05BCONTROL OR REGULATING SYSTEMS IN GENERAL; FUNCTIONAL ELEMENTS OF SUCH SYSTEMS; MONITORING OR TESTING ARRANGEMENTS FOR SUCH SYSTEMS OR ELEMENTS
    • G05B23/00Testing or monitoring of control systems or parts thereof
    • G05B23/02Electric testing or monitoring
    • G05B23/0205Electric testing or monitoring by means of a monitoring system capable of detecting and responding to faults
    • G05B23/0208Electric testing or monitoring by means of a monitoring system capable of detecting and responding to faults characterized by the configuration of the monitoring system
    • G05B23/0213Modular or universal configuration of the monitoring system, e.g. monitoring system having modules that may be combined to build monitoring program; monitoring system that can be applied to legacy systems; adaptable monitoring system; using different communication protocols
    • GPHYSICS
    • G05CONTROLLING; REGULATING
    • G05BCONTROL OR REGULATING SYSTEMS IN GENERAL; FUNCTIONAL ELEMENTS OF SUCH SYSTEMS; MONITORING OR TESTING ARRANGEMENTS FOR SUCH SYSTEMS OR ELEMENTS
    • G05B2219/00Program-control systems
    • G05B2219/30Nc systems
    • G05B2219/33Director till display
    • G05B2219/33324What to diagnose, whole system, test, simulate

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  • Physics & Mathematics (AREA)
  • General Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Automation & Control Theory (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The invention discloses a closed-loop test platform used for an instrument and control system of a nuclear reactor and driven by real-time simulation data The platform comprises a nuclear reactor real-time simulation platform and a signal transmission array. Before test, a configuration data in the signal transmission array downloads variable data and attribute information to a data processing module; the data processing module refreshes variable values which represent onsite sensor signals of the reactor according to real-time simulation data provided by the reactor real-time simulation platform, and addresses corresponding sub channels in an IO module according to related address information; the IO module converts the real-time simulation data into electric signals, transmits the electric signals to the instrument and control system, and converts real-time control signals emitted by the tested instrument and control system into real-time control data; and the real-time control data is back fed to the nuclear reactor real-time simulation platform via the signal transmission array to realize closed-loop test. The closed-loop test platform can greatly improve the test credibility and the test efficiency.

Description

A kind of nuclear reactor I&C system closed loop test platform of real-time simulation data-driven
Technical field
The present invention relates to the instrument in nuclear engineering and control field, be specifically related to a kind of nuclear reactor I&C system closed loop test platform of real-time simulation data-driven.
Background technology
In current nuclear industry field, Instrument and control system is just play important role, it has very important impact for the safe operation of nuclear reactor, is related to the life security of nuclear reactor operations staff, is also related to the safety of property, reactor surrounding enviroment.
In order to ensure the normal operation of reactor I&C system, need to test it before reactor I&C system formally comes into operation, the content of test comprises: the architecture testing of system, communication test, control algolithm are tested and interlock protection test.Presently used reactor I&C system method of testing is mainly and directly utilizes signal generator to produce signal, as switching signal, sinusoidal signal, random signal etc., and is transferred to reactor I&C system and tests.The shortcoming of the method is that drive singal is not come from nuclear reactor, lacks authenticity.Therefore, the method is merely able to the test realizing hardware view, as the test of communication, framework aspect; For software view test, as control algolithm test, interlock protection test, then cannot realize.In addition, this method of testing is mainly to control in units of rack or process system, overall for tested object with nuclear reactor I&C system, and in nuclear reactor, is to there is the relation that highly is coupled between each process system.Above problem shows, existing method of testing has certain limitation.
Summary of the invention
The technical problem to be solved in the present invention proposes one with nuclear reactor I&C system entirety for tested object, the platform that the heap I&C system hardware view of realization response simultaneously and software view are tested.On the one hand, utilize reactor real-time simulation platform to generate real-time simulation data, and be converted to electric signal by Signal transmissions array and be sent to tested I&C system; On the other hand, the control signal that tested I&C system exports is converted into real-time control data and feeds back to reactor real-time simulation platform by Signal transmissions array, realizes the control to reactor realistic model.This test platform can realization response heap I&C system hardware view test; comprise system architecture test, communication test; and the test of software view; comprise control algolithm test, interlock protection test; greatly improve the confidence level of reactor I&C system test; improve testing efficiency, save testing cost, ensure the safety of reactor operation.
The technical solution used in the present invention is as follows:
The nuclear reactor I&C system closed loop test platform of real-time simulation data-driven, this test platform comprises: nuclear reactor real-time simulation platform, responds real-time control data for generation of real-time simulation data; Signal transmissions array, be connected by Real-time data interface with nuclear reactor real-time simulation platform, and be connected by signal wire with tested nuclear reactor I&C system, it can convert the real-time simulation data coming from real-time simulation platform to true electric signal and send to nuclear reactor I&C system, converts the real-time control signal coming from I&C system to real-time control data simultaneously and sends to emulation platform.
Wherein, this test platform can be used for the I&C system test of fission-type reactor, magnetic confinement fusion reactor and fusion-fission hybrid reactor, and content measurement comprises: the architecture testing of reactor I&C system, communication test, reactor control algolithm are tested and interlock protection test.
Wherein, described nuclear reactor real-time simulation platform comprises: plasma dynamics emulation module, neutron dynamics emulation module, thermohydraulics emulation module and sequential scheduling module; Under the effect of sequential scheduling module, this emulation platform can be real-time the plasma dynamics model of operation reactor, neutron dynamics model and thermohydraulics model, realize the real-time simulation to fission reactor, magnetic confinement fusion reactor and fusion-fission hybrid reactor.
Wherein, described Signal transmissions array comprises: configuration server, for creating the variable representing reactor spot sensor signal and reactor I&C system control signal, and set up corresponding variable's attribute, comprise unit, types of variables, be subordinate to subsystem, real-time variable value, variate-value bound, corresponding transmission channel address; Data processing module, for downloading the variable data in configuration server, carries out addressing to data transmission channel, and carries out data double-way transmission with I/O module; I/O module, exports reactor I&C system to for real-time simulation data are converted into electric signal, and in the future the control signal of autothermal reactor I&C system is converted into real-time control data and inputs in data processing module.
Wherein, in described Signal transmissions array, described transmission channel address comprises three parts: data processing module address, I/O module address, I/O module sub-channel address.
Wherein, in described Signal transmissions array, described Signal transmissions array data transmission and switch process as follows:
Step (1), I&C system test start before, variable data and attribute are downloaded in data processing module by configuration server;
Step (2), extract transmission channel address information and resolve to three parts: data processing module address, I/O module address, I/O module subchannel address, and whether verification msg processing module address is correct, if incorrect, re-starts download;
Step (3), start test after, the real-time simulation data that first data processing module provides according to reactor real-time simulation platform are to representing that the variate-value of reactor spot sensor signal refreshes;
Step (4), according to the corresponding I/O module of I/O module addressing of address;
Step (5), again according to the subchannel in the corresponding I/O module of I/O module subchannel address addressing;
Step (6), for output module, real-time simulation data are converted into electric signal and are exported to by signal wire in reactor I&C system; For load module, the control signal of autothermal reactor I&C system is converted into real-time control data and transfers in data processing module in the future;
Step (7), data processing module refresh according to the variate-value of the real-time control data received to expression I&C system control signal, and transfer in reactor real-time simulation platform;
Step (8), return step (3), restart next circulation.
The present invention's advantage is compared with prior art:
(1), the present invention adopts the test of the I&C system that can realize fission reactor, magnetic confinement fusion reactor and fusion-fission hybrid reactor.
(2) the present invention is overall for tested object with nuclear reactor I&C system, disposablely completes all content measurements, comprising: the architecture testing of reactor I&C system, communication test, the test of reactor control algolithm and interlock protection test.
(3) the present invention can increase substantially the confidence level of test, and promotes testing efficiency.
Accompanying drawing explanation
Fig. 1 be the present invention a kind of time the emulated data primary structure schematic diagram of nuclear reactor I&C system closed loop test platform that drives.
Fig. 2 is fission reactor realistic model framework.
Fig. 3 is fusion reactor realistic model framework.
Fig. 4 is nuclear reactor emulation platform sequential control step.
Fig. 5 is configuration server internal variable constructive process.
Fig. 6 is data transmission and flow path switch in Signal transmissions array.
Embodiment
The present invention is further illustrated below in conjunction with accompanying drawing and specific embodiment.
As shown in Figure 1, this test platform mainly includes nuclear reactor emulation platform and Signal transmissions array.
Nuclear reactor emulation platform, mainly by nuclear reactor emulation module, comprises plasma dynamics emulation module, neutron dynamics emulation module, thermohydraulics emulation module, and a sequential scheduling module composition.This emulation platform runs based on a high performance computation workstation.Nuclear reactor emulation module can set up corresponding kinetic model according to the specific design parameter of nuclear reactor.During for fission reactor modeling, neutron dynamics emulation module and thermohydraulics emulation module is used to carry out modeling according to the framework shown in Fig. 2; For the ease of maintenance and the amendment of realistic model, thermal-hydraulic model is divided into different submodels according to the process system of reactor.By thermal-hydraulic border before different submodels, as heat, flow, pressure, be coupled.Neutron dynamics model is also coupled with thermal-hydraulic model by heat as a submodel.During for magnetic confinement fusion reactor or fusion-fission hybrid reactor, plasma dynamics emulation module, neutron dynamics emulation module, thermohydraulics emulation module is used to carry out modeling according to the framework of Fig. 3.Wherein plasma dynamics realistic model is coupled with neutron dynamics emulation module by neutron correlation properties as a submodel.When nuclear reactor emulation platform runs, the mode according to Fig. 4 is ensured the real time execution emulated by sequential scheduling module: all submodels are divided into several groups; In each group, submodel quantity is less than or equal to the CPU quantity at operation station, and each submodel operates in different CPU; The each group of computing carrying out a time step successively, until all groups all complete the computing of a time step; If operation time is altogether T exc, a real-time operation cycle is T clk, so remaining free time is T idl=T clk-T exc; If T idl>=0, so next sequential scheduling module will suspend computing T idlcontinue after time to enter next execution cycle; If T idl<0, so emulates termination and reports an error.When emulation platform normally runs, the storage emulating operating mode can be carried out at any time, the operating mode stored can be reintroduced back to simultaneously.
Signal transmissions array is primarily of configuration server, and I/O module and data processing module form.
Configuration server is mainly used in creating the variable representing reactor spot sensor signal and reactor I&C system control signal, and sets up corresponding variable's attribute, as shown in Figure 5.Variable's attribute has two kinds, and one is base attribute, comprises variable name, variable description, unit, real-time simulation value, is subordinate to system; Another kind is extended attribute, comprises the upper limit, lower limit, corresponding transmission channel address.According to the base attribute of variable, configuration server can realize carrying out data interaction with emulation platform; According to base attribute and the extended attribute of variable, configuration server can realize to data processing module downloading data or the function that uploads data.
I/O module and data processing module are mainly used in the conversion between real time data and electric signal.First data processing module downloads variable data storing from configuration server, then carries out addressing according to the address in variable extended attribute, and that carries out between real time data and electric signal after addressing completes is mutual.Total transmission and switch process be as shown in Figure 6:
Step (1), I&C system test start before, variable data and attribute are downloaded in data processing module by configuration server;
Step (2), extract transmission channel address information and resolve to three parts: data processing module address, I/O module address, I/O module subchannel address, and whether verification msg processing module address is correct, if incorrect, re-starts download;
Step (3), start test after, the real-time simulation data that first data processing module provides according to reactor real-time simulation platform are to representing that the variate-value of reactor spot sensor signal refreshes;
Step (4), according to the corresponding I/O module of I/O module addressing of address;
Step (5), again according to the subchannel in the corresponding I/O module of I/O module subchannel address addressing;
Step (6), for output module, real-time simulation data are converted into electric signal and are exported to by signal wire in reactor I&C system; For load module, the control signal of autothermal reactor I&C system is converted into real-time control data and transfers in data processing module in the future;
Step (7), data processing module refresh according to the variate-value of the real-time control data received to expression I&C system control signal, and transfer in reactor real-time simulation platform;
Step (8), return step (3), restart next circulation.

Claims (6)

1. a nuclear reactor I&C system closed loop test platform for real-time simulation data-driven, it is characterized in that, this closed loop test platform comprises:
Nuclear reactor real-time simulation platform, for generation of real-time simulation data, and makes response to real-time control data;
Signal transmissions array, be connected by Real-time data interface with nuclear reactor real-time simulation platform, and be connected by signal wire with tested nuclear reactor I&C system, it can convert the real-time simulation data coming from real-time simulation platform to true electric signal and send to nuclear reactor I&C system, converts the real-time control signal coming from I&C system to real-time control data simultaneously and sends to emulation platform.
2. the nuclear reactor I&C system closed loop test platform of real-time simulation data-driven according to claim 1; it is characterized in that: this closed loop test platform can be used for the I&C system test of fission-type reactor, magnetic confinement fusion reactor and fusion-fission hybrid reactor, and content measurement comprises: the architecture testing of reactor I&C system, communication test, reactor control algolithm are tested and interlock protection test.
3. the nuclear reactor I&C system closed loop test platform of real-time simulation data-driven according to claim 1, it is characterized in that, described nuclear reactor real-time simulation platform comprises: plasma dynamics emulation module, neutron dynamics emulation module, thermohydraulics emulation module and sequential scheduling module; Under the effect of sequential scheduling module, this emulation platform can be real-time the plasma dynamics model of operation reactor, neutron dynamics model and thermohydraulics model, realize the real-time simulation to fission reactor, magnetic confinement fusion reactor and fusion-fission hybrid reactor.
4. the nuclear reactor I&C system closed loop test platform of real-time simulation data-driven according to claim 1, it is characterized in that, described Signal transmissions array comprises:
Configuration server, for creating the variable representing reactor spot sensor signal and reactor I&C system control signal, and set up corresponding variable's attribute, comprising: unit, types of variables, be subordinate to subsystem, real-time variable value, variate-value bound, corresponding transmission channel address;
Data processing module, for downloading the variable data in configuration server, carries out addressing to data transmission channel, and carries out data double-way transmission with I/O module;
I/O module, exports reactor I&C system to for real-time simulation data are converted into electric signal, and in the future the real-time control signal of autothermal reactor I&C system is converted into real-time control data and inputs in data processing module.
5. the nuclear reactor I&C system closed loop test platform of real-time simulation data-driven according to claim 4, it is characterized in that, the described transmission channel address described in Signal transmissions array comprises three parts: data processing module address, I/O module address, I/O module sub-channel address.
6. the nuclear reactor I&C system closed loop test platform of real-time simulation data-driven according to claim 4, is characterized in that, the described transmission of Signal transmissions array data described in Signal transmissions array and switch process as follows:
Step (1), I&C system test start before, variable data and attribute are downloaded in data processing module by configuration server;
Step (2), extract transmission channel address information and resolve to three parts: data processing module address, I/O module address, I/O module subchannel address, and whether verification msg processing module address is correct, if incorrect, re-starts download;
Step (3), start test after, the real-time simulation data that first data processing module provides according to reactor real-time simulation platform are to representing that the variate-value of reactor spot sensor signal refreshes;
Step (4), according to the corresponding I/O module of I/O module addressing of address;
Step (5), again according to the subchannel in the corresponding I/O module of I/O module subchannel address addressing;
Step (6), for output module, real-time simulation data are converted into electric signal and are exported to by signal wire in reactor I&C system; For load module, the control signal of autothermal reactor I&C system is converted into real-time control data and transfers in data processing module in the future;
Step (7), data processing module refresh according to the variate-value of the real-time control data received to expression I&C system control signal, and transfer in reactor real-time simulation platform;
Step (8), return step (3), restart next circulation.
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Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN109522356A (en) * 2018-11-13 2019-03-26 中国核动力研究设计院 A kind of nuclear reactor digital experiment platform
CN109639520A (en) * 2018-11-28 2019-04-16 北京广利核系统工程有限公司 A kind of Computer Aided Measurement of reactor protection system network communication
CN110580566A (en) * 2019-06-24 2019-12-17 上海核工程研究设计院有限公司 Instrument control system black box test system
CN114911172A (en) * 2022-06-13 2022-08-16 江苏方洋能源科技有限公司 Nuclear energy heat supply device self-starting and stopping control simulation system and test method

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN101996693A (en) * 2009-08-25 2011-03-30 北京广利核系统工程有限公司 Configuration system for reactor protection system
CN102508972A (en) * 2011-11-09 2012-06-20 北京化工大学 Modeling method for hydrogen energy reactor
CN102789169A (en) * 2012-05-25 2012-11-21 中国核动力研究设计院 Numerical model processing method for simulation of digital instrument control system of nuclear power plant
CN103853052A (en) * 2012-11-30 2014-06-11 中广核工程有限公司 Design method for nuclear power station reactor control system

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN101996693A (en) * 2009-08-25 2011-03-30 北京广利核系统工程有限公司 Configuration system for reactor protection system
CN102508972A (en) * 2011-11-09 2012-06-20 北京化工大学 Modeling method for hydrogen energy reactor
CN102789169A (en) * 2012-05-25 2012-11-21 中国核动力研究设计院 Numerical model processing method for simulation of digital instrument control system of nuclear power plant
CN103853052A (en) * 2012-11-30 2014-06-11 中广核工程有限公司 Design method for nuclear power station reactor control system

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
杨宗伟等: "核电站仿真技术在反应堆控制系统调试中的应用", 《核动力工程》 *

Cited By (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN109522356A (en) * 2018-11-13 2019-03-26 中国核动力研究设计院 A kind of nuclear reactor digital experiment platform
CN109522356B (en) * 2018-11-13 2022-03-11 中国核动力研究设计院 Nuclear reactor digital experiment system
CN109639520A (en) * 2018-11-28 2019-04-16 北京广利核系统工程有限公司 A kind of Computer Aided Measurement of reactor protection system network communication
CN109639520B (en) * 2018-11-28 2020-12-04 北京广利核系统工程有限公司 Computer-aided test method for network communication of reactor protection system
CN110580566A (en) * 2019-06-24 2019-12-17 上海核工程研究设计院有限公司 Instrument control system black box test system
CN114911172A (en) * 2022-06-13 2022-08-16 江苏方洋能源科技有限公司 Nuclear energy heat supply device self-starting and stopping control simulation system and test method

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