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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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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    • 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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Abstract

本发明公开了一种实时仿真数据驱动的核反应堆仪控系统闭环测试平台,包括;核反应堆实时仿真平台、信号传输阵列;开始测试前,信号传输阵列中的组态服务器将变量数据及属性信息下载至数据处理模块中;数据处理模块根据反应堆实时仿真平台提供的实时仿真数据对代表反应堆现场传感器信号的变量值进行刷新,再根据有关地址信息寻址相应的IO模块中的子通道;IO模块将实时仿真数据转换成为电信号传输至被测试仪控系统中,并将被测试仪控系统发出的实时控制信号转换为实时控制数据;实时控制数据将经过信号传输阵列反馈给核反应堆实时仿真平台以实现闭环测试。本发明大幅度提高测试的可信度,并提升测试效率。

The invention discloses a closed-loop test platform for a nuclear reactor instrument control system driven by real-time simulation data, comprising: a nuclear reactor real-time simulation platform and a signal transmission array; before starting the test, the configuration server in the signal transmission array downloads variable data and attribute information to In the data processing module; the data processing module refreshes the variable value representing the sensor signal of the reactor site according to the real-time simulation data provided by the reactor real-time simulation platform, and then addresses the sub-channel in the corresponding IO module according to the relevant address information; the IO module will real-time The simulation data is converted into electrical signals and transmitted to the tested instrument and control system, and the real-time control signal sent by the tested instrument and control system is converted into real-time control data; the real-time control data will be fed back to the nuclear reactor real-time simulation platform through the signal transmission array to achieve closed loop test. The invention greatly improves the credibility of the test and improves 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)

1.一种实时仿真数据驱动的核反应堆仪控系统闭环测试平台,其特征在于,该闭环测试平台包括:1. A nuclear reactor instrument and control system closed-loop test platform driven by real-time simulation data, is characterized in that, this closed-loop test platform comprises: 核反应堆实时仿真平台,用于产生实时仿真数据,并对实时的控制数据做出响应;Nuclear reactor real-time simulation platform, used to generate real-time simulation data and respond to real-time control data; 信号传输阵列,与核反应堆实时仿真平台通过实时数据接口连接,并与被测试核反应堆仪控系统通过信号线连接,其可以将来自于实时仿真平台的实时仿真数据转换成真实电信号并发送给核反应堆仪控系统,同时将来自于仪控系统的实时控制信号转换成实时的控制数据发送给仿真平台。The signal transmission array is connected with the real-time simulation platform of the nuclear reactor through the real-time data interface, and connected with the instrument and control system of the tested nuclear reactor through the signal line, which can convert the real-time simulation data from the real-time simulation platform into real electrical signals and send them to the nuclear reactor instrument At the same time, the real-time control signal from the instrument control system is converted into real-time control data and sent to the simulation platform. 2.根据权利要求1所述的实时仿真数据驱动的核反应堆仪控系统闭环测试平台,其特征在于:该闭环测试平台可用于核裂变反应堆、磁约束聚变反应堆以及聚变裂变混合堆的仪控系统测试,测试内容包括:反应堆仪控系统的架构测试、通信测试、反应堆控制算法测试以及联锁保护测试。2. the nuclear reactor instrument and control system closed-loop test platform driven by real-time simulation data according to claim 1, is characterized in that: this closed-loop test platform can be used for the instrument and control system test of nuclear fission reactor, magnetic confinement fusion reactor and fusion fission hybrid reactor , the test contents include: reactor I&C system architecture test, communication test, reactor control algorithm test and interlock protection test. 3.根据权利要求1所述的实时仿真数据驱动的核反应堆仪控系统闭环测试平台,其特征在于,所述的核反应堆实时仿真平台包括:等离子体动力学仿真模块、中子动力学仿真模块、热工水力学仿真模块以及时序调度模块;在时序调度模块的作用下,该仿真平台可以实时的运行反应堆的等离子体动力学模型、中子动力学模型以及热工水力学模型,实现对裂变反应堆、磁约束聚变反应堆以及聚变裂变混合堆的实时仿真。3. the nuclear reactor instrument and control system closed-loop test platform driven by real-time simulation data according to claim 1, is characterized in that, described nuclear reactor real-time simulation platform comprises: plasma dynamics simulation module, neutron dynamics simulation module, thermal Engineering-hydraulics simulation module and timing scheduling module; under the function of timing scheduling module, the simulation platform can run the plasma dynamics model, neutron dynamics model and thermal-hydraulics model of the reactor in real time, realizing fission reactor, Real-time simulation of magnetic confinement fusion reactors and fusion-fission hybrid reactors. 4.根据权利要求1所述的实时仿真数据驱动的核反应堆仪控系统闭环测试平台,其特征在于,所述的信号传输阵列包括:4. the nuclear reactor instrument and control system closed-loop test platform driven by real-time simulation data according to claim 1, is characterized in that, described signal transmission array comprises: 组态服务器,用于创建表示反应堆现场传感器信号以及反应堆仪控系统控制信号的变量,并建立相应的变量属性,包括:单位、变量类型、隶属子系统、实时变量值、变量值上下限、对应传输通道地址;The configuration server is used to create variables representing the reactor on-site sensor signals and the control signals of the reactor I&C system, and establish corresponding variable attributes, including: unit, variable type, subordinate subsystem, real-time variable value, variable value upper and lower limits, corresponding Transmission channel address; 数据处理模块,用于下载组态服务器中的变量数据,对数据传输通道进行寻址,并与IO模块进行数据双向传输;The data processing module is used to download the variable data in the configuration server, address the data transmission channel, and perform two-way data transmission with the IO module; IO模块,用于将实时仿真数据转换成为电信号输出至反应堆仪控系统,以及将来自反应堆仪控系统的实时控制信号转换成为实时的控制数据输入至数据处理模块中。The IO module is used to convert real-time simulation data into electrical signals and output them to the reactor I&C system, and convert real-time control signals from the reactor I&C system into real-time control data and input them to the data processing module. 5.根据权利要求4所述的实时仿真数据驱动的核反应堆仪控系统闭环测试平台,其特征在于,所述的信号传输阵列中所述的传输通道地址包括三个部分:数据处理模块地址、IO模块地址、IO模块中子通道地址。5. the nuclear reactor instrument and control system closed-loop test platform driven by real-time simulation data according to claim 4, is characterized in that, the transmission channel address described in the described signal transmission array comprises three parts: data processing module address, IO Module address, sub-channel address in the IO module. 6.根据权利要求4所述的实时仿真数据驱动的核反应堆仪控系统闭环测试平台,其特征在于,所述的信号传输阵列中所述的信号传输阵列数据传输及转换步骤如下:6. the nuclear reactor instrument and control system closed-loop test platform driven by real-time simulation data according to claim 4, is characterized in that, the signal transmission array data transmission and conversion steps described in the described signal transmission array are as follows: 步骤(1)、在仪控系统测试开始之前,将变量数据及属性由组态服务器下载至数据处理模块中;Step (1), before the instrument control system test starts, the variable data and attributes are downloaded from the configuration server to the data processing module; 步骤(2)、提取传输通道的地址信息并解析成三个部分:数据处理模块地址、IO模块地址、IO模块子通道地址,并验证数据处理模块地址是否正确,若不正确则重新进行下载;Step (2), extracting the address information of the transmission channel and parsing it into three parts: data processing module address, IO module address, IO module sub-channel address, and verifying whether the data processing module address is correct, if not correct, re-download; 步骤(3)、开始测试后,数据处理模块首先根据反应堆实时仿真平台提供的实时仿真数据对表示反应堆现场传感器信号的变量值进行刷新;Step (3), after starting the test, the data processing module first refreshes the variable value representing the reactor site sensor signal according to the real-time simulation data provided by the reactor real-time simulation platform; 步骤(4)、根据IO模块地址寻址相应的IO模块;Step (4), addressing the corresponding IO module according to the IO module address; 步骤(5)、再根据IO模块子通道地址寻址相应的IO模块中的子通道;Step (5), addressing the sub-channel in the corresponding IO module according to the sub-channel address of the IO module; 步骤(6)、对于输出模块,将实时仿真数据转换成为电信号并通过信号线输出至反应堆仪控系统中;对于输入模块,将来自反应堆仪控系统的控制信号转换成为实时控制数据并传输至数据处理模块中;Step (6), for the output module, convert the real-time simulation data into an electrical signal and output it to the reactor instrument and control system through the signal line; for the input module, convert the control signal from the reactor instrument and control system into real-time control data and transmit it to the In the data processing module; 步骤(7)、数据处理模块根据接收到的实时控制数据对表示仪控系统控制信号的变量值进行刷新,并传输至反应堆实时仿真平台中;Step (7), the data processing module refreshes the variable value representing the control signal of the instrument and control system according to the received real-time control data, and transmits it to the reactor real-time simulation platform; 步骤(8)、返回步骤(3),重新开始下一个循环。Step (8), return to step (3), start the next cycle again.
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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》 *

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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
CN114911172B (en) * 2022-06-13 2024-11-01 江苏方洋能源科技有限公司 Nuclear energy heating device self-start-stop control simulation system and test method

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