CN108052019B - Method and system for inhibiting calculation overflow of fluid model of full-range simulator of nuclear power station - Google Patents

Method and system for inhibiting calculation overflow of fluid model of full-range simulator of nuclear power station Download PDF

Info

Publication number
CN108052019B
CN108052019B CN201711353028.3A CN201711353028A CN108052019B CN 108052019 B CN108052019 B CN 108052019B CN 201711353028 A CN201711353028 A CN 201711353028A CN 108052019 B CN108052019 B CN 108052019B
Authority
CN
China
Prior art keywords
abnormal
model
parameters
teaching
fluid
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Active
Application number
CN201711353028.3A
Other languages
Chinese (zh)
Other versions
CN108052019A (en
Inventor
胡晓亮
袁媛
王晓星
王学良
庄进
温志青
王勇刚
蔡瑞忠
张黎明
王群峰
赖厚晶
吴毅
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
China General Nuclear Power Corp
China Nuclear Power Engineering Co Ltd
Original Assignee
China General Nuclear Power Corp
China Nuclear Power Engineering Co Ltd
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by China General Nuclear Power Corp, China Nuclear Power Engineering Co Ltd filed Critical China General Nuclear Power Corp
Priority to CN201711353028.3A priority Critical patent/CN108052019B/en
Publication of CN108052019A publication Critical patent/CN108052019A/en
Application granted granted Critical
Publication of CN108052019B publication Critical patent/CN108052019B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Images

Classifications

    • GPHYSICS
    • G05CONTROLLING; REGULATING
    • G05BCONTROL OR REGULATING SYSTEMS IN GENERAL; FUNCTIONAL ELEMENTS OF SUCH SYSTEMS; MONITORING OR TESTING ARRANGEMENTS FOR SUCH SYSTEMS OR ELEMENTS
    • G05B17/00Systems involving the use of models or simulators of said systems
    • G05B17/02Systems involving the use of models or simulators of said systems electric
    • GPHYSICS
    • G09EDUCATION; CRYPTOGRAPHY; DISPLAY; ADVERTISING; SEALS
    • G09BEDUCATIONAL OR DEMONSTRATION APPLIANCES; APPLIANCES FOR TEACHING, OR COMMUNICATING WITH, THE BLIND, DEAF OR MUTE; MODELS; PLANETARIA; GLOBES; MAPS; DIAGRAMS
    • G09B9/00Simulators for teaching or training purposes

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Physics & Mathematics (AREA)
  • Theoretical Computer Science (AREA)
  • Automation & Control Theory (AREA)
  • Business, Economics & Management (AREA)
  • Educational Administration (AREA)
  • Educational Technology (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The invention discloses a method for inhibiting the calculation overflow of a fluid model of a full-range simulator of a nuclear power station, wherein the fluid model comprises a fluid network model and a reactor core thermal hydraulic model, and the method comprises the following steps: monitoring parameters transmitted between the fluid network model and the reactor core thermal hydraulic model in real time by the teaching and control console; when the teaching and control console monitors that the parameters are abnormal, the operation function of the abnormal module to which the abnormal parameters belong is frozen, and the abnormal module is controlled to output according to the parameters operated before freezing. The invention also discloses a system for inhibiting the fluid model calculation overflow of the full-range simulator of the nuclear power station. The method can effectively inhibit the calculation overflow of the fluid model of the simulator, and avoid the whole collapse of the running of the simulator.

Description

Method and system for inhibiting calculation overflow of fluid model of full-range simulator of nuclear power station
Technical Field
The invention relates to the technical field of nuclear power stations, in particular to a method and a system for inhibiting calculation overflow of a fluid model of a full-range simulator of a nuclear power station.
Background
In the development of the current domestic nuclear power project full-range simulator, an internationally advanced reactor core thermal hydraulic model RELAP5-3D and a fluid network model FLOWBASE are mostly adopted to respectively model the reactor core and a primary loop thermal hydraulic, nuclear island auxiliary and conventional island systems, and the two are coupled to jointly realize the real-time simulation of the full-range and full-working-condition dynamic operating characteristics of a reference unit.
FLOWBASE abstracts the thermal system piping of the primary loop auxiliary system and the secondary loop system into a fluid network, and simplifies the transmission and transient problems of fluid in the piping into the problems of transient pressure of each node of the fluid network and flow on each flow channel. RELAP5-3D is used to build a core thermodynamic hydraulic model that can accurately calculate neutron flux, reactivity, reactor power and decay heat and their distribution to meet the simulation requirements for the whole range of the off-core measurement system and the simulation accurate calculation for the temperature rise of the coolant passing through the core. For RELAP5-3D to accurately calculate reactivity, FLOWBASE modeled a calculation and interface with RELAP5-3D reactivity feedback factors. The interface model accurately calculates the relevant reactivity feedback factor through heat transfer from the core fuel node or segment to the thermal hydraulic node or segment, and provides the required input for reactivity calculation to the neutron dynamic node or segment of RELAP5-3D through the interface model. Thus, for the overall fluid model, the stability of the FLOWBASE algorithm mainly determines the stability margin of the fluid model,
with the deepening of the training depth or the expansion of the range of the user, the user successively finds that the simulation of the full-range simulator in the simulation operation of partial low-load or special accident working conditions is interrupted due to the fact that the operation is stopped due to model calculation overflow. By investigating such problems, it is found that most of the calculated overflow is caused by that the FLOWBASE transmits abnormal parameters under large disturbance (simulation of fault working conditions of a part of the console setup, such as a loop break, cavitation of a main centrifugal pump, unilateral water loss of a heat exchanger and the like) to a downstream flow network, and the calculated overflow is caused by that the interface data transmitted to the RELAP5 by the FLOWBASE exceeds a reasonable range. However, at present, no research aiming at the calculation overflow of a fluid model of a nuclear power simulator is available, and an engineering processing method capable of effectively inhibiting the calculation overflow and guaranteeing the fault condition of the normal training part of the simulator is explored, so that the method is a technical innovation with remarkable social and economic benefits.
Disclosure of Invention
The invention provides a method and a system for inhibiting calculation overflow of a fluid model of a full-range simulator of a nuclear power station, aiming at the problems in the prior art, and the method and the system can effectively inhibit the calculation overflow of the fluid model of the simulator and avoid the integral collapse of the running of the simulator.
The technical scheme provided by the invention for the technical problem is as follows:
in one aspect, the invention provides a method for suppressing the calculation overflow of a fluid model of a full-range simulator of a nuclear power station, wherein the fluid model comprises a fluid network model and a core thermal hydraulic model, and the method comprises the following steps:
monitoring parameters transmitted between the fluid network model and the reactor core thermal hydraulic model in real time by the teaching and control console;
when the teaching and control console monitors that the parameters are abnormal, the operation function of the abnormal module to which the abnormal parameters belong is frozen, and the abnormal module is controlled to output according to the parameters operated before freezing.
Further, before the teaching console monitors the parameters transmitted between the fluid network model and the core thermohydraulic model in real time, the method further comprises the following steps:
and inserting a large disturbance fault condition causing calculation overflow into the simulator by the teaching and control console, so that the fluid model calculates overflow under the fault condition.
Further, the teaching and control console monitors parameters transmitted between the fluid network model and the core thermal hydraulic model in real time, and specifically comprises:
the teaching and control console acquires parameters transmitted between the fluid network model and the reactor core thermal hydraulic model, and updates a pre-established parameter state table; the parameter state table is a corresponding relation table of each parameter and the module to which the parameter state table belongs;
and the teaching and control console monitors each parameter in the parameter state table respectively, and if the monitored parameter exceeds a corresponding preset threshold value, the parameter is judged to be abnormal.
Furthermore, a module in the parameter state table is a control body simulated by the fluid model and comprises a valve, a pump body, a water tank, a heat exchanger and various transmitters; the parameters in the parameter state table comprise pressure, temperature, flow and enthalpy values.
Further, when the teaching console monitors that the parameter is abnormal, the method freezes the operation function of the abnormal module to which the abnormal parameter belongs, and specifically comprises the following steps:
when the teaching and control console monitors that the parameters are abnormal, an alarm is triggered, and an operator is prompted to perform manual intervention;
and if the parameters are abnormally recovered to be normal after the manual intervention within the preset time, the teaching and control console stops alarming.
If the manual intervention is not carried out or the manual intervention is not carried out within the preset time or the abnormal parameter is not recovered, the operation function of the abnormal module to which the abnormal parameter belongs is frozen, and the operation of the abnormal module is stopped.
Further, the suppression method further comprises:
and during the freezing period of the abnormal module, the teaching and control console reminds the freezing information of the abnormal module so that an operator can perform manual intervention according to the freezing information.
Further, the suppression method further comprises:
and during the freezing period of the abnormal module, if the abnormal parameters are restored to be normal through manual intervention, the teaching and control console finishes the freezing state of the abnormal module, restores the operation function of the abnormal module and switches the output of the abnormal module into real-time operation output in an undisturbed manner.
Further, the suppression method further comprises:
and during the freezing period of the abnormal module, if the abnormal parameters are not recovered to be normal all the time, the teaching and control console keeps the abnormal module in a frozen state all the time until the simulation is finished.
On the other hand, the invention provides a system for applying the method for inhibiting the overflow calculation of the fluid model of the full-range simulator of the nuclear power station, wherein the system comprises an analog simulation server and a teaching and control console connected with the analog simulation server; a fluid model is constructed in the simulation server and comprises a fluid network model and a reactor core thermal hydraulic model;
the teaching and control console is used for monitoring parameters transmitted between the fluid network model and the reactor core thermal hydraulic model in real time, freezing the operation function of an abnormal module to which the abnormal parameters belong when the parameters are monitored to be abnormal, and controlling the abnormal module to output according to the parameters operated before freezing.
The technical scheme provided by the embodiment of the invention has the following beneficial effects:
parameters transmitted between the fluid network model and the reactor core thermal hydraulic model are monitored in real time through the teaching and control console, measures are adopted when the parameters are abnormal, the abnormal module is guaranteed to enter a freezing state under the condition that the abnormal module is overflowed in a calculation mode, parameter isolation is achieved, meanwhile, the abnormal module is enabled to output according to the state before freezing, accordingly, the phenomenon that the whole simulation of the simulator is interrupted due to the fact that the abnormal parameters are transmitted to the whole fluid model is avoided, and the teaching and control console has important significance for guaranteeing normal training and examinations of the simulator.
Drawings
In order to more clearly illustrate the technical solutions in the embodiments of the present invention, the drawings needed to be used in the description of the embodiments will be briefly introduced below, and it is obvious that the drawings in the following description are only some embodiments of the present invention, and it is obvious for those skilled in the art to obtain other drawings based on these drawings without creative efforts.
Fig. 1 is a schematic flow chart of a method for suppressing overflow of a fluid model calculation of a full-range simulator of a nuclear power plant according to an embodiment of the present invention;
fig. 2 is a schematic structural diagram of an undisturbed switching module in a method for suppressing overflow of a fluid model calculation of a full-range simulator of a nuclear power plant according to an embodiment of the present invention;
fig. 3 is a schematic specific flowchart of a method for suppressing overflow of a fluid model of a full-range simulator of a nuclear power plant according to an embodiment of the present invention;
fig. 4 is a schematic structural diagram of a system for suppressing overflow calculated by a fluid model of a full-range simulator of a nuclear power plant according to a second embodiment of the present invention.
Detailed Description
In order to solve the technical problems of simulation interruption and the like caused by calculation overflow of a fluid model of a nuclear power station full-range simulator in the prior art, the invention aims to provide a method for inhibiting calculation overflow of the fluid model of the nuclear power station full-range simulator, which has the core thought that: the module freezing method for effectively inhibiting the calculation overflow is provided, the fluid model parameters which easily cause the crash of a simulator are monitored and frozen, and the whole simulation process is ensured not to be terminated by the module with a local calculation error.
In order to make the objects, technical solutions and advantages of the present invention more apparent, embodiments of the present invention will be described in detail with reference to the accompanying drawings.
Example one
The embodiment of the invention provides a method for inhibiting the calculation overflow of a fluid model of a full-range simulator of a nuclear power station, wherein the fluid model comprises a fluid network model and a reactor core thermal hydraulic model, and the method comprises the following steps:
s1, monitoring parameters transmitted between the fluid network model and the reactor core thermal hydraulic model in real time by a teaching and control console;
and S2, freezing the operation function of the abnormal module to which the abnormal parameter belongs when the teaching console monitors that the parameter is abnormal, and controlling the abnormal module to output according to the operated parameter before freezing.
It should be noted that various modules are provided for the simulation of the fluid network model and the core thermal hydraulic model, and parameters are interacted among the various modules. Under normal conditions, each module receives the parameters of the upstream flow network for operation and outputs the operated parameters to the link of the downstream flow network. In this embodiment, the teaching console monitors important parameters transmitted between the fluid network model and the core thermal hydraulic model in real time, and if the monitored parameters are abnormal, the module to which the abnormal parameters belong, i.e., the abnormal module, is frozen, and the abnormal module is stopped from receiving the upstream flow network parameters, and the operation function of the upstream flow network parameters is stopped, so that the upstream flow network parameters are output according to the parameters operated under normal conditions.
Further, before step S1, before the instruction console monitors parameters transmitted between the fluid network model and the core thermo-hydraulic model in real time, the method further includes:
and inserting a large disturbance fault working condition which can cause calculation overflow into the simulator by the teaching and control console, so that the fluid model calculates overflow under the fault working condition.
It should be noted that the teaching console can prompt the fluid model to calculate and overflow in a manner of inserting a fault condition into the simulator (under other normal simulation conditions, if an extreme condition is encountered, such as pump cavitation triggered by low pump inlet flow due to water loss of an upstream tank, the fluid model may also be finally calculated and overflow. Specifically, a coach clicks a fault list button on an operation interface of the teaching console, and pops up a secondary menu containing all faults which can be realized by the full-range simulator, wherein one item is 'break fault'; after clicking a 'break fault' button, popping up a list containing all break faults, wherein the list contains information such as names, positions and the like of the break faults; selecting a certain breach fault (such as a VVP master pipe) and clicking, popping up a fault activated panel menu, setting the activation time and the severity of the fault and the time for reaching the required severity on the panel menu, and clicking an 'insert' button after the setting is finished, so that the fault is triggered; after triggering, the state of the fault signal in the memory will change. The communication software scans the state change of the fault signal in the memory in real time, and once the state change of a certain fault signal is detected, the communication software packages relevant information of the fault, including a fault name and a fault degree, according to a certain format and then sends the information to the simulator through a network.
Further, in step S1, the monitoring console monitors parameters transmitted between the fluid network model and the core thermo-hydraulic model in real time, and specifically includes:
the teaching and control console acquires parameters transmitted between the fluid network model and the reactor core thermal hydraulic model, and updates a pre-established parameter state table; the parameter state table is a corresponding relation table of each parameter and the module to which the parameter state table belongs;
and the teaching and control console monitors each parameter in the parameter state table respectively, and if the monitored parameter exceeds a corresponding preset threshold value, the parameter is judged to be abnormal.
Furthermore, a module in the parameter state table is a control body simulated by the fluid model and comprises a valve, a pump body, a water tank, a heat exchanger and various transmitters; the parameters in the parameter state table comprise pressure, temperature, flow and enthalpy values.
It should be noted that the instruction console pre-establishes a state table of parameters transmitted from the fluid network model to the core thermal hydraulic model, that is, a parameter state table. The parameter state table comprises module information and parameter information transmitted from a fluid network model in a relevant module to a core thermal hydraulic model, wherein the range of the module with possible abnormity is limited in the core thermal hydraulic model simulation range: the system comprises a fuel heat exchange part, a fuel cladding heat exchange part, a main circulation loop, a voltage stabilizer, a steam generator secondary side, a main steam main pipe, a steam header, interfaces with other systems and the like. The modules which are possibly abnormal in the range comprise a valve, a pump body, a water tank, a heat exchanger, various transmitters and the like. The important parameter types transmitted from the fluid network model to the core thermal hydraulic model comprise pressure, temperature, flow, enthalpy value and the like.
In addition, the teaching and control console establishes a parameter threshold table aiming at faults which are easy to calculate typical overflow working conditions, such as typical overflow working conditions of breaches, typical overflow working conditions of pump cavitation, typical overflow working conditions of single-side water loss of a heat exchanger and the like. The table of the parameter threshold values of the typical overflow working condition of the breach is shown in table 1, the table of the parameter threshold values of the typical overflow working condition of the pump cavitation corrosion is shown in table 2, and the table of the parameter threshold values of the typical overflow working condition of the single-side water loss of the heat exchanger is shown in table 3.
Loop hot leg crevasse (more than 50 percent)
A loop cold leg break (in front of main pump) (more than 50%)
A loop cold leg break (after main pump) (more than 50%)
Broken opening of pipeline between top of pressure container and pressure release valve (100%)
No. 1 steam generator U-shaped tube bottom breakage (100%)
No. 1 steam generator U-shaped tube top rupture(100%)
Rupture of the main steam line in containment (more than 50%)
Rupture of the main steam line between the outside of containment and the 001VV main isolation valve (more than 50%)
TABLE 1
Figure BDA0001510622000000071
TABLE 2
Full stop of the SRI pump: SRI101RF/201RF/301RF heat exchanger lost heat traps
RRI pump full stop: RRI001, 003PO stop pump, RRI001/003RF lose the hot trap
GST pump stop all: GST101/201PO stop, 101 and 201RF loss hot trap
TABLE 3
The parameter threshold table is obtained according to empirical data of the simulation machine under steady-state working conditions and limit working conditions, and allows a simulation machine instructor to dynamically update according to changes of an actual unit.
And the teaching and control console monitors the parameters in the parameter state table in real time and sets an operation period so as to compare and judge the corresponding parameters in the parameter state table based on the parameter threshold value table in each operation period. And the teaching and control console judges the parameter state in real time, and if the parameter is found to exceed the corresponding data range in the parameter threshold value table, the parameter is judged to be abnormal.
Further, in step S2, when the console monitors that the parameter is abnormal, the method freezes the operation function of the abnormal module to which the abnormal parameter belongs, and specifically includes:
when the teaching and control console monitors that the parameters are abnormal, an alarm is triggered, and an operator is prompted to perform manual intervention;
if the abnormal parameters are recovered to be normal after manual intervention within the preset time, the teaching and control console stops alarming;
if the manual intervention is not carried out or the manual intervention is not carried out within the preset time or the abnormal parameter is not recovered, the operation function of the abnormal module to which the abnormal parameter belongs is frozen, and the operation of the abnormal module is stopped.
It should be noted that if there is an abnormal parameter, an alarm is triggered, and the alarm information includes the abnormal parameter and the abnormal module to which the abnormal parameter belongs. And the console is taught to prompt an operator to access manual operation within preset time, and the system state is adjusted. If the abnormal module does not finish the manual intervention in the preset time or the manual intervention does not correct the abnormal parameters, the teaching and control console automatically sends out a module operation freezing instruction, freezes the operation function of the abnormal module and takes over the output of the abnormal module. After the operation of the abnormal module is stopped, all the parameter outputs of the abnormal module are kept in the state before freezing. If the manual intervention is carried out within the preset time and the complete abnormal parameters are corrected, the teaching and control console checks the state of the abnormal parameters of the parameter state table, and if the parameter fluctuation is within the normal range of the parameter threshold table, the alarm is stopped. This process is to allow a predetermined time to avoid freezing the module when a parameter anomaly occurs for the first time
Further, the suppression method further comprises:
and during the freezing period of the abnormal module, the teaching and control console reminds the freezing information of the abnormal module so that an operator can perform manual intervention according to the freezing information.
It should be noted that the freeze information includes information about possible causes of module abnormality, etc. for the operator to view and perform manual intervention.
Further, the suppression method further comprises:
and during the freezing period of the abnormal module, if the abnormal parameters are restored to be normal through manual intervention, the teaching and control console stops alarming, ends the freezing state of the abnormal module, restores the operation function of the abnormal module, and switches the output of the abnormal module into real-time operation output in an undisturbed manner.
It should be noted that, if modification of the abnormal parameters is completed by manual intervention during freezing of the abnormal module, so that the abnormal parameters are restored to normal, the console is taught to check the state of the abnormal parameters in the parameter state table, if parameter fluctuation is within the normal range of the parameter threshold table, the alarm is terminated, the freezing state of the abnormal module is cancelled, the module receives the parameters of the upstream flow network again to start operation, and after undisturbed switching processing is performed on the output of the frozen state of the module and the output of real-time operation, the parameters of the real-time operation are output to the link of the downstream flow network to perform operation. And the undisturbed switching is adopted, so that the phenomenon that the sudden change of the parameters causes the endless disturbance of the flow network parameters again can be avoided.
The undisturbed switching is controlled and implemented by adopting an undisturbed switching module, as shown in fig. 2, the undisturbed switching module SFT includes an input terminal l1, an input terminal l2, a selection terminal SW, a slope switching terminal RT and an output terminal AV. During the module freezing period, the input terminal l1 inputs the parameter Var1 calculated before the module freezing, when the module is in normal operation, the input terminal l2 inputs the parameter Var2 calculated normally by the module, the slope switching terminal RT is the switching slope of two input values, is controlled by time, and is a preset fixed value. The select terminal SW is a select input and the default value is 0. During the module freezing period, the selection terminal SW is set to 0, and the value Var3 output by the output terminal AV is the value of the input terminal l1, namely the parameter Var1 of the operation before the module freezing; when the console cancels the freezing state of the module, the selection terminal SW is set to 1, and the output value Var3 of the output terminal AV is undisturbed switched to Var2 from Var 1.
Further, the suppression method further comprises:
and during the freezing period of the abnormal module, if the abnormal parameters are not recovered to be normal all the time, the teaching and control console keeps the abnormal module in a frozen state all the time until the simulation is finished.
It should be noted that, during the freezing period of the abnormal module, the teaching console prompts the freezing information of the abnormal module for manual intervention operation, and if no manual intervention is performed all the time in the simulation process, the abnormal module is always kept in the frozen state. And the teaching and control console maintains the original simulation state until the simulation is finished, namely the training course or the examination process is finished, a new initial working condition is called, and the optimization scheme is finished.
Referring to fig. 3, a specific flow diagram of a method for suppressing overflow of a fluid model calculation of a full-range simulator of a nuclear power plant according to an embodiment of the present invention is shown, where the method includes:
and S101, teaching a console to insert operation fault working conditions. The teaching console of the full-range simulator of the nuclear power station starts course training, faults (taking pump cavitation working conditions as an example) are inserted, and simulation courseware of the simulator is started.
S102, the fluid module calculates overflow. After the operation is carried out for a period of time, the valve opening at the downstream of the pump is overlarge, so that the local low pressure in a liquid flow channel in the simulation pipeline can vaporize liquid at the local part to cause the explosion of a large number of micro-bubbles to cause the occurrence of cavitation, the cavitation initiation of the upstream and downstream pumps can cause the fluctuation and oscillation of the pressure and enthalpy of the outlet of the pump and the flow of the pump, along with the delay of the cavitation time, the flow of the outlet generates positive and negative oscillation, the amount of vapor (gas) contained in the pump is increased, the vapor water parameter value exceeds the saturated water and vapor meter value, the calculation of related parameters of the pumps generates errors, the pressure, the enthalpy and the flow are suddenly increased or reduced greatly, the values are transmitted into a flow network communicated with the upstream and the downstream, and finally.
S103, displaying an overflow alarm by a console RELAP5-FLOWBASE overflow parameter state table. The console starts to read all the parameters transmitted by the simulation server of the simulator, calls all the parameter values contained in the RELAP5-FLOWBASE overflow parameter state table from the parameters, and writes the parameter values into the overflow parameter table, wherein the writing period is consistent with the simulation period of the simulator. In each simulation period, the teaching and control console scans each parameter value in the parameter table once to judge whether each parameter is in the range of the threshold value table, and if one parameter is not in the range of the threshold value, the teaching and control console immediately sends out overrun alarm information
And S104, selecting a manual intervention mode or automatically entering a module freezing mode. And within the default time of 1 minute set by the instructor, the teaching and control console continuously scans and judges each parameter of the parameter table in each simulation period. Check valve opening degree of teaching console waiting for manual intervention of simulator instructor for adjusting downstream of pump
And S105, manually intervening to restore to normal, and teaching the console to cancel the freezing mode. If the simulator instructor completes the adjustment, the cavitation phenomenon of the pump disappears, the parameters are recovered to be normal, the original overrun alarm is closed, and the system is recovered to be normal.
And S106, automatically entering a module freezing mode again when the manual intervention is unsuccessful. If no manual intervention is found within the set default time or the parameter of the manual intervention is still out of limit, all modules with abnormal parameters are taken over, and the modules are in a freezing mode. The outputs of the exception modules are all frozen at the overrun threshold.
S107, in the freezing state, if the manual intervention is successful, the freezing mode is exited, the control right of the module is cancelled by the teaching and control console, the module output is automatically switched to real-time operation output without disturbance, and the system is recovered to be normal. During the module is frozen, if manual intervention is performed, after the manual intervention is completed and modification is confirmed, the teaching console cancels the module freezing state, the module receives the upstream stream network parameters again to start operation, and the teaching console performs undisturbed switching on the module freezing state output and the real-time operation output and then obtains an output value to be used for downstream stream network link operation.
And S108, in the freezing state, if the manual intervention fails, continuing to freeze. If no manual intervention is always performed in the freezing process, or the parameters of the module cannot be restored to be within the threshold range through the manual intervention, the module is always kept in the frozen state until the fault simulation course is finished.
And S109, teaching the console to call in a new working condition. And (5) the instructor recalls the new initial working condition, the simulator completes initialization, and the process is ended.
The embodiment of the invention monitors the parameters transmitted between the fluid network model and the reactor core thermal hydraulic model in real time through the teaching and control console, adopts measures when the parameters are abnormal, ensures that the abnormal module enters a frozen state under the condition of overflow calculation, realizes parameter isolation, and simultaneously enables the abnormal module to output according to the state before freezing, thereby avoiding the interruption of the whole simulation of the simulator caused by transmitting the abnormal parameters to the whole fluid model, and having important significance for ensuring the normal training and examination of the simulator.
Example two
The embodiment of the invention provides a system capable of realizing the method for suppressing the calculation overflow of the fluid model of the full-range simulator of the nuclear power station, and referring to fig. 4, the system comprises an analog simulation server 1 and a teaching and control console 2 connected with the analog simulation server 1; a fluid model is constructed in the simulation server and comprises a fluid network model and a reactor core thermal hydraulic model;
the teaching and control console 2 is used for monitoring parameters transmitted between the fluid network model and the reactor core thermal hydraulic model in real time, freezing the operation function of an abnormal module to which the abnormal parameters belong when the monitored parameters are abnormal, and controlling the abnormal module to output according to the parameters operated before freezing.
The embodiment of the invention monitors the parameters transmitted between the fluid network model and the reactor core thermal hydraulic model in real time through the teaching and control console, adopts measures when the parameters are abnormal, ensures that the abnormal module enters a frozen state under the condition of overflow calculation, realizes parameter isolation, and simultaneously enables the abnormal module to output according to the state before freezing, thereby avoiding the interruption of the whole simulation of the simulator caused by transmitting the abnormal parameters to the whole fluid model, and having important significance for ensuring the normal training and examination of the simulator.
In summary, the invention provides a method and a system for inhibiting the calculation overflow of a fluid model of a full-range simulator of a nuclear power station, which have the following good practical effects: real-time scanning and updating of each simulation cycle are realized through an important overflow parameter state table and a parameter threshold table which are set at the early stage, judgment information of parameters transmitted to RELAP5 by FLOWBASE is obtained, isolation and freezing processing is carried out on an abnormal module to which the judged abnormal parameters belong, disturbance factors which possibly cause the breakdown of the whole simulation environment are controlled in a controllable range, a processing means is provided, and the capability of effectively inhibiting the calculation overflow of a full-range simulator flow network model is realized; the emergency treatment capacity of the nuclear power station full-range simulator under various complex working conditions is greatly improved, the availability of the nuclear power station full-range simulator is improved, and the nuclear power station full-range simulator has a good technical effect.
The above description is only for the purpose of illustrating the preferred embodiments of the present invention and is not to be construed as limiting the invention, and any modifications, equivalents, improvements and the like that fall within the spirit and principle of the present invention are intended to be included therein.

Claims (9)

1. A method for suppressing the calculation overflow of a fluid model of a full-range simulator of a nuclear power station is characterized in that the fluid model comprises a fluid network model and a core thermohydraulic model, and the method comprises the following steps:
monitoring parameters transmitted between the fluid network model and the reactor core thermal hydraulic model in real time by the teaching and control console;
when the teaching and control console monitors that the parameters are abnormal, freezing the operation function of an abnormal module to which the abnormal parameters belong, and controlling the abnormal module to output according to the parameters operated before freezing;
the teaching and control console monitors the parameters transmitted between the fluid network model and the reactor core thermal hydraulic model in real time, and specifically comprises:
the teaching and control console acquires parameters transmitted between the fluid network model and the reactor core thermal hydraulic model, and updates a pre-established parameter state table; the parameter state table is a corresponding relation table of each parameter and the module to which the parameter state table belongs;
and the teaching and control console monitors each parameter in the parameter state table respectively, and if the monitored parameter exceeds a corresponding preset threshold value, the parameter is judged to be abnormal.
2. The method for suppressing nuclear power plant full-scope simulator fluid model calculated spillover of claim 1, wherein prior to the instruction console monitoring in real time parameters communicated between the fluid network model and the core thermo-hydraulic model, further comprising:
and inserting a large disturbance fault condition causing calculation overflow into the simulator by the teaching and control console, so that the fluid model calculates overflow under the fault condition.
3. The method for suppressing nuclear power plant full-scope simulator fluid model calculation spillover of claim 1, wherein the modules in the parameter state table include respective control volumes simulated by the fluid models; the parameters in the parameter state table comprise pressure, temperature, flow and enthalpy values.
4. The method for suppressing the calculation overflow of the fluid model of the full-range simulator of the nuclear power plant as claimed in claim 1, wherein when the teaching console monitors that the parameter is abnormal, the teaching console freezes the operation function of the abnormal module to which the abnormal parameter belongs, and specifically comprises:
when the teaching and control console monitors that the parameters are abnormal, an alarm is triggered, and an operator is prompted to perform manual intervention;
if the manual intervention is not carried out or the manual intervention is not carried out within the preset time or the abnormal parameter is not recovered, the operation function of the abnormal module to which the abnormal parameter belongs is frozen, and the operation of the abnormal module is stopped.
5. The method for suppressing nuclear power plant full-scope simulator fluid model calculated spillover as defined in claim 4, further comprising:
and during the freezing period of the abnormal module, the teaching and control console reminds the freezing information of the abnormal module so that an operator can perform manual intervention according to the freezing information.
6. The method for suppressing nuclear power plant full-scope simulator fluid model calculated spillover as defined in claim 4, further comprising:
and if the abnormal parameters are recovered to be normal through manual intervention within the preset time, the teaching and control console stops alarming.
7. The method for suppressing nuclear power plant full-scope simulator fluid model calculated spillover as defined in claim 1, further comprising:
and during the freezing period of the abnormal module, if the abnormal parameters are restored to be normal through manual intervention, the teaching and control console finishes the freezing state of the abnormal module, restores the operation function of the abnormal module and switches the output of the abnormal module into real-time operation output in an undisturbed manner.
8. The method for suppressing nuclear power plant full-scope simulator fluid model calculated spillover of claim 7, further comprising:
and during the freezing period of the abnormal module, if the abnormal parameters are not recovered to be normal all the time, the teaching and control console keeps the abnormal module in a frozen state all the time until the simulation is finished.
9. A system for applying the method for suppressing the calculation of the overflow of the fluid model of the full-range simulator of the nuclear power plant according to any one of claims 1 to 8, wherein the system comprises an analog simulation server and a teaching console connected with the analog simulation server; a fluid model is constructed in the simulation server and comprises a fluid network model and a reactor core thermal hydraulic model;
the teaching and control console is used for monitoring parameters transmitted between the fluid network model and the reactor core thermal hydraulic model in real time, freezing the operation function of an abnormal module to which the abnormal parameters belong when the parameters are monitored to be abnormal, and controlling the abnormal module to output according to the parameters operated before freezing.
CN201711353028.3A 2017-12-15 2017-12-15 Method and system for inhibiting calculation overflow of fluid model of full-range simulator of nuclear power station Active CN108052019B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201711353028.3A CN108052019B (en) 2017-12-15 2017-12-15 Method and system for inhibiting calculation overflow of fluid model of full-range simulator of nuclear power station

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201711353028.3A CN108052019B (en) 2017-12-15 2017-12-15 Method and system for inhibiting calculation overflow of fluid model of full-range simulator of nuclear power station

Publications (2)

Publication Number Publication Date
CN108052019A CN108052019A (en) 2018-05-18
CN108052019B true CN108052019B (en) 2021-01-19

Family

ID=62132803

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201711353028.3A Active CN108052019B (en) 2017-12-15 2017-12-15 Method and system for inhibiting calculation overflow of fluid model of full-range simulator of nuclear power station

Country Status (1)

Country Link
CN (1) CN108052019B (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN110364047A (en) * 2019-07-03 2019-10-22 死海旅游度假有限公司 Virtual teaching system based on acousto-optic power technology

Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3919720A (en) * 1973-02-23 1975-11-11 Westinghouse Electric Corp Nuclear power plant training simulator modeling organization and method
CN1292554A (en) * 1999-07-05 2001-04-25 法玛通公司 Method for monitoring at least one running parameter of pile core of nuclear pile and its system
CN102142291A (en) * 2010-11-10 2011-08-03 中广核工程有限公司 Method and system for displaying monitoring parameters after nuclear power station accident
CN103973513A (en) * 2014-05-05 2014-08-06 中广核(北京)仿真技术有限公司 Remote monitoring method and system for full-range analog machines of nuclear power station
CN104299042A (en) * 2013-07-15 2015-01-21 中广核工程有限公司 Nuclear power station accident risk prediction method and system
CN104573032A (en) * 2015-01-14 2015-04-29 清华大学 Emergency simulation drilling all-in-one machine for nuclear emergency device
CN105223932A (en) * 2015-10-21 2016-01-06 中广核工程有限公司 Nuclear plant safety method for early warning, system and nuclear power station emulation technology platform
CN105512812A (en) * 2015-12-02 2016-04-20 中广核工程有限公司 Nuclear power plant equipment fault early warning analysis method and system based on dynamic simulation model

Patent Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3919720A (en) * 1973-02-23 1975-11-11 Westinghouse Electric Corp Nuclear power plant training simulator modeling organization and method
CN1292554A (en) * 1999-07-05 2001-04-25 法玛通公司 Method for monitoring at least one running parameter of pile core of nuclear pile and its system
CN102142291A (en) * 2010-11-10 2011-08-03 中广核工程有限公司 Method and system for displaying monitoring parameters after nuclear power station accident
CN104299042A (en) * 2013-07-15 2015-01-21 中广核工程有限公司 Nuclear power station accident risk prediction method and system
CN103973513A (en) * 2014-05-05 2014-08-06 中广核(北京)仿真技术有限公司 Remote monitoring method and system for full-range analog machines of nuclear power station
CN104573032A (en) * 2015-01-14 2015-04-29 清华大学 Emergency simulation drilling all-in-one machine for nuclear emergency device
CN105223932A (en) * 2015-10-21 2016-01-06 中广核工程有限公司 Nuclear plant safety method for early warning, system and nuclear power station emulation technology platform
CN105512812A (en) * 2015-12-02 2016-04-20 中广核工程有限公司 Nuclear power plant equipment fault early warning analysis method and system based on dynamic simulation model

Non-Patent Citations (2)

* Cited by examiner, † Cited by third party
Title
基于 Ovation 系统的核电站蒸汽发生器容错控制;邓志红;《中国优秀硕士学位论文全文数据库 工程科技Ⅱ辑》;20111215;第1-37页 *
用于教学实习的核电站虚拟仿真系统;邓华;《中国优秀硕士学位论文全文数据库 工程科技Ⅱ辑》;20170315(第03期);第14、58、70页 *

Also Published As

Publication number Publication date
CN108052019A (en) 2018-05-18

Similar Documents

Publication Publication Date Title
CN110675966B (en) System and method for isolating steam generator under heat transfer pipe rupture accident
CN108052019B (en) Method and system for inhibiting calculation overflow of fluid model of full-range simulator of nuclear power station
JP2014038006A (en) Nuclear reactor monitoring device and nuclear reactor control device
WO2024174847A1 (en) Steam generator water-level control method and system after shutdown of pressurized water reactor
CN107863168B (en) Method for analyzing withdrawal time of nuclear power unit when power operation loses final heat trap
CN110879541B (en) Transient offline simulation system of high-voltage direct-current valve cooling system
US9099207B2 (en) System, method, and program for monitoring reactor core
JP6666349B2 (en) How to manage shutdown of a pressurized water reactor
KR101631417B1 (en) Display method for Total Monitoring Of Turbine for the Power Plant
CN111457354B (en) Input control method and device for feed water heating system of thermal power plant
CN111271603B (en) Nuclear power station valve diaphragm maintenance method
CN113418661A (en) Monitoring method and system for steam generator of nuclear power plant
KR102698496B1 (en) Reinforcement learning model learning method and rule-based nuclear power plant operation automation method using the same
Yao et al. Optimization measures to reduce the influence of the network failure in DCS system of power plant
CN112906201B (en) Design method for loop system overpressure protection in pressurized water reactor operation state
CN115388559B (en) Flow abnormity determination method and device and air energy hot water system
CN110718312A (en) System and method for stopping safety injection in heat transfer pipe rupture accident
JP6192925B2 (en) Plant operation support apparatus and plant operation support method
CN113555141B (en) Intelligent monitoring method and system for nuclear power station and intelligent monitoring server
CN117724543A (en) Automatic control method and system for heating pipes before starting main steam pipeline of nuclear power plant
JPH0236398A (en) Automatic cooling operation device for operation from hot state to cold state of pressurized water nuclear power plant
Larsson et al. A revival of the alarm system: Making the alarm list useful during incidents
Wang et al. Simulated safety analysis of a total loss of feedwater accident in the steam generator of CPR1000 nuclear power plant
Guo et al. A Fault Simulation and Monitoring Method of DCS in Nuclear Power Plant Based on Virtual Platform
CN115263448A (en) Cold-state pre-warming starting control test method for steam turbine of gas-steam combined cycle unit

Legal Events

Date Code Title Description
PB01 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination
GR01 Patent grant
GR01 Patent grant