JPS5968696A - Reactor state monitoring device - Google Patents

Abstract

(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to a nuclear reactor status monitoring device for monitoring the status of a nuclear reactor.

[Technical background of the invention and its problems] In order to operate a nuclear power plant safely and efficiently, it is necessary to monitor a large number of physical sites. Among these monitoring items, the one related to the health of the fuel is one of the most basic, and must be monitored with high precision to prevent contamination by radioactive materials.

In boiling water type light water reactors, thermal limit values for the fuel are monitored in the following way: as shown in Figure 1, the neutron flux inside the reactor 1 and the core flow are monitored. , thermo-hydraulic data 3 such as temperature, pressure, flow rate, etc. of feed water flow, etc., and control rod position information 4 are sent to a computer 6 via a process input/output device 5 from sensors installed for each measurement. The power distribution (flow rate distribution, etc.) in the core is calculated using the input nl, the core performance calculation program 71 and the core performance calculation constants 72 stored in advance in the auxiliary storage device 7.

Various thermal limit values are calculated based on these distributions.

Monitoring of power distribution, various thermal limit values, etc. through core performance calculations has conventionally been performed approximately once every hour due to computer load and calculation speed limitations, and the calculation results are provided to operators. is an output device such as a typewriter or line printer [
It is output through 8e. The analysis of these calculation results is usually left to the manual labor of operators and the like, resulting in a considerable amount of work being required for the analysis. Furthermore, since core performance calculations are performed only once every hour in principle, it has been difficult to adequately follow transient changes. Furthermore, when investigating past history, it is necessary to manually create graphs from a large amount of data.

As mentioned above, in the past, core condition monitoring was often performed based on the results processed by operators, and it was necessary to monitor various aspects such as the load on operators, early detection of abnormalities, and analysis of abnormality history. It's not efficient.

[Object of the Invention] The object of the present invention is to perform core performance calculations in a short time period by using a high-speed calculation device, and to store the data obtained as historical data.

We added various editing processes to this and created a high-density color CRT.
By providing information to operators using display devices such as display devices, it is possible to monitor the reactor in a detailed manner with less time delay, and this enables early detection of load reduction abnormalities for operators. The object of the present invention is to obtain a nuclear reactor condition monitoring device that can obtain extremely useful results for abnormality analysis and the like.

[Summary of the invention]

The present invention provides a reactor status input seven-build, a process input/output processing device that processes input signals inputted thereby, and a high-speed calculation device that performs calculations related to reactor status monitoring.
an auxiliary storage device for accumulating the results; a display control device for displaying the reactor state; and a display device for displaying the reactor state based on a signal from the display control device;
It consists of a display recording device that records the content displayed on this display device, a dialogue control device for dialogue with operators, and a dialogue input/output device, and monitors the reactor status in short cycles. The system is characterized in that the results are given to the operator in a format that is easy to analyze.

[Embodiments of the invention]

An embodiment of the present invention will be described. As can be seen from Fig. 2, the neutron flux measurement value 2 inside the reactor 1, thermo-hydraulic data 3 such as temperature, pressure, flow rate of the core flow, feed water flow, etc., and control rod position information 4 are each The sensor is input to the computer 6 via the process input/output device 5, and the core performance calculation is executed using the high-speed calculation device 9 using the core performance calculation program 71 and the core performance calculation constant 72, and the calculation result is The data is stored in the auxiliary storage device 7 as historical data 17.

As a result, the display control device 1o, the display device 11, the dialogue control device 12. By using the dialogue input/output device 13, the information is presented in an edited form according to the operator's request. Further, the display is recorded by the display recording device 14. Furthermore, an abnormality in a monitored item is detected by the alarm monitoring device 15 and notified to the operator by the alarm output device 16.

Next, we will monitor the critical power ratio, which is a thermal limit value index for monitoring damage due to overheating of fuel rods in boiling water reactors.
An example of this will be explained below.

Regarding the state of the reactor 1, neutron flux measurement values 2, thermo-hydraulic data 3, and control rod position information 4 are input into the computer 6 from each sensor via the process input/output device 5. In the computer 6, a core performance calculation program 71 is executed by the high speed arithmetic unit 9 in short periods using these data and the core performance calculation constants 72 stored in the main storage 70 or the auxiliary storage 7 in advance. Run and exit distribution within the core.

Determine flow rate distribution and water density distribution. Furthermore, the critical power ratio is calculated for each fuel assembly using the results of these distributions. These results are stored in the auxiliary storage device 7 as historical data 17 in chronological order.

Here, the furnace calculated at time , t) and the set of data are D
(t).

D(t) = (p(t), v(t), w(t),
CPR(t) , --・・) --・・(1) However, p(t) : Output distribution at time t v(t) : Water density distribution at time -1 w(t) : At time t Flow rate distribution CPR4t) : Limit power ratio distribution at time t Every time core performance calculation is executed, limit values such as the limit power ratio are compared with respective limit values by the alarm monitoring device 15. By definition, if the limit value of the limit output ratio CPR, (t) is CPRlim.

CPR(su<CP Rl im --
In case (2), there is a high possibility of fuel damage. in this case.

The alarm monitoring device 15 determines that an abnormality has occurred, and the alarm output device 1
6 or a warning message is output to the display device 11 to remind the operator to pour the amount.

If such an abnormality occurs, the operator requests display of abnormality analysis data through the interactive input/output device 13 such as a CRT display, keyboard, or light pen.

At this time, the input data includes display output items, the fuel assembly number of the first time period to be analyzed in the historical data to be analyzed, and the like.

The display output item is limit output ratio history data output.

Limit output ratio distribution plane 2-dimensional display, output distribution 1-dimensional.

These include two-dimensional display, flow rate distribution display, water density distribution display, etc.

The operator's request is sent to the computer 61C via the dialogue control device 12.
The computer 6 performs necessary editing on the history data D (t) (tmin < t <: tmax) according to the request, and the result is sent to the display control device 10.
It is displayed on the display device 11 via a graphic display, a plotter display, etc. However, tmin is the analysis start time specified by the operator, and tmax is the analysis end time specified by the operator.

FIG. 3 shows an example of a display screen when a request is made to display historical data of the limit output ratio. In this display, if the value of the limit output ratio becomes less than CP R1im, the display in that area changes to red, etc., making it easier for the operator to analyze. In the figure, ■ marks are red and X marks are green. Various distribution displays (1-dimensional, 2-dimensional.

3D), the data D for each display data time interval ΔT+ (generally, take a value that is an integer multiple of the core performance calculation execution time interval ΔTo) specified by the operator.
([) is displayed at a time interval of display update interval ΔT2 according to the request of the operating point.

In other words, if the time when 1 display started is 10, then tO+
tO+△T,,to+2ΔT! A display screen of the distribution based on the following data is output every time. D, (tmin), D (tmin +
ΔT1), D (tmin-)j2ΔT1)...
. . . It is also possible to stop or restart the screen update progress at any time according to a request from the operator via the interaction input/output device 13.

These display screens are recorded and saved by the display/recording device 14 at the operator's request or automatically. Furthermore, when it is possible to display data collected at a plurality of different times within one screen, such as in a one-dimensional distribution display, it is also possible to display them in groups. FIG. 4 shows an example where three sets of data can be displayed on one screen. In this case, if to is the time when 1 display started, then s to + to + Δ'
I'2. to+2△T2. . . . The calculation results based on the next group of data are displayed. (D (t
min), l) (tmin +△'l'l)
, D (tmin-1-2△T1', '))
, ('D (tmli+3△T+ )+D(tmin
-1-4ΔT1), D(tmin+5ΔT1)
) + (D (tmin+5△jl), D
(tmin+7ΔT1), D(tmin+8ΔT
t) ) Meeting 1 Suga-Michi 0 In the above example, the explanation was given using the monitoring of the limit power ratio as an example, but monitoring of other limit values such as core power, core flow rate, axial power distribution, etc. The same can be done. Further, in the above-mentioned embodiment, the explanation was given using the case where an abnormality occurs as an example, but a similar analysis can be carried out in a normal state as well at the request of the operator.

In addition, in the above embodiment, the data for display is collected by the computer 6.
Although the explanation has been made assuming that the screen data editing 5 creation function is executed in the display control device 10, a configuration in which the screen data editing 5 creation function is executed in the display control device 10 is also possible. It is also possible to predict the future behavior of a nuclear reactor based on the historical data stored using the method of this embodiment. Furthermore, in the above-described embodiment, the high-speed arithmetic device is described as being built into the computer 1, but an additional high-speed arithmetic device can also be provided with similar functionality.

[Effects of the Invention] The present invention enables core condition monitoring, which was conventionally calculated hourly, with monitoring of limit values and the creation of historical data being done manually by operators, to enable core performance calculations to be performed in a short period of time. The core state data at each point in time is stored as historical data, and core state analysis in the event of an abnormality is provided to the operators through graphical displays, making it possible to execute it intuitively and quickly. . Furthermore, since the alarm output in the event of an abnormality is carried out by a computer, there is no possibility of the system being overlooked, which is highly beneficial for ensuring safety. In addition, it becomes possible for the operator μ to extract necessary information from the controller through dialogue, and a significant load reduction is realized.

[Brief explanation of drawings]

FIG. 1 is a block diagram showing a conventional example, FIG. 2 is a block diagram showing an embodiment of the present invention, FIG. 3 is an explanatory diagram showing an example of a display screen of the present invention, and FIG. 4 is a block diagram showing an example of a display screen of the present invention. FIG. 5 is a flowchart showing the operation of the present invention. 1... Nuclear reactor 2... Neutron flux measurement value 3... Thermal hydraulic data 4... Control rod position information 5... Process input/output device 6... Calculator 7... Auxiliary storage device 70... Main memory device 71... Core performance calculation program 72... Constant for core performance calculation 8... Output device 9... High speed calculation Device 91...Arithmetic device 10...Display control device 11...Display device 12...Dialogue control device 13...Dialogue input/output device 14...
・Display record bag (position 15... alarm monitoring device 16)
...Alarm output device 17...Historical data (7317) Agent Patent attorney Kensuke Chika (and 1 other person) Fig. 3 Fig. 4

Claims (1)

[Scope of Claims] A reactor status input sensor, a process input/output processing device that processes input signals input by the sensor, a high-speed calculation device that performs calculations related to reactor status monitoring, and an auxiliary device that accumulates the results. storage device. A display control device for fully displaying the reactor status, a display device for displaying the reactor status based on signals from the display control device, and a display recording device for recording the content displayed on the display device. , which consists of a dialogue control device for dialogue with operators and an input/output device for dialogue, monitors the condition of the reactor in short cycles and instructs the operators on the results in a format that is easy to analyze. A nuclear reactor condition monitoring device characterized by: