JPH0313559B2 - - Google Patents

Description

[Detailed description of the invention] [Purpose of the invention] (Industrial application field) The present invention relates to a monitoring device for nuclear reactor equipment.

(Prior art) Conventionally, nuclear reactor equipment, such as boiling water nuclear power generation equipment, is configured so that the operating status of the equipment that makes up the equipment and the process amount of the equipment are all displayed on the control panel in the central control room. . This information is displayed on meters or on a CRT when operated by an operator.
Further, information that may affect safety is displayed using an alarm. Based on this information, the operator grasps and monitors the overall condition of the equipment, maintains safety, and detects abnormalities at an early stage if they occur.

(Problems to be Solved by the Invention) Conventionally, information such as the operating status and process amount of the above-mentioned devices has been configured to be displayed using meters, CRTs, alarms, and the like. For this reason, for example, when operating a boiling water nuclear power generation facility, approximately 600 switches must be operated based on information from approximately 300 instruments and approximately 1,000 alarms. This placed a heavy burden on the operator, and could also lead to inappropriate operations.

The purpose of the present invention is to organize the signals sent from the equipment side and display them in a summarized form, thereby making it easier to understand the overall status of the equipment, reducing the burden on the operator, and preventing inappropriate use. An object of the present invention is to obtain a monitoring device for nuclear reactor equipment that can reduce the possibility of erroneous operations.

[Structure of the invention]

(Means for Solving the Problems) In order to achieve the above object, the present invention provides a detector for measuring reactor power, reactor water level, reactor internal pressure, reactor containment vessel internal pressure, and radiation dose. , a signal converter that converts the analog signals measured by these detectors into digital signals, an engineering unit converter that converts the measurement signals from this signal converter into engineering units, and a signal that is processed by this engineering unit converter. a bar graph head display calculation unit that calculates the head of the bar graph based on the measured signal; a change rate calculation unit that calculates a temporal change rate from the measurement signal processed by the engineering unit conversion unit; a change rate display selection section that selects positive, negative, and zero, and a movable drawing information memory that stores signals processed by the engineering unit conversion section, the bar graph head display calculation section, the change rate calculation section, and the change rate display selection section. Then, the signals from this movable drawing information memory are used to display the reactor output, reactor water level, reactor internal pressure, reactor containment vessel internal pressure, and radiation dose as numerical values, a bar graph of these numerical values, and a rate of change of the numerical values. Provided is a monitoring device for nuclear reactor equipment characterized by comprising a display mechanism that displays on the same display screen an arrow pointing upward when positive and pointing downward when negative.

(Function) In the apparatus configured in this manner, important items among the process quantities of the nuclear reactor equipment are displayed on the same screen, making it possible to easily grasp the status of the entire equipment.

(Example) An example of the present invention will be described below with reference to FIGS. 1 to 3.

FIG. 1 is a schematic diagram of a monitoring device for nuclear reactor equipment according to the present invention. Boiling water nuclear power generation equipment (hereinafter referred to as equipment) 1 is equipped with a reactor pressure vessel 2 that houses a reactor core, and steam generated within this reactor pressure vessel 2 is sent to a turbine 3 to drive it. The turbine 3 drives a generator 5 to generate electricity, and the steam exiting the turbine 3 is sent to a condenser 4 where it is condensed and becomes condensed water. In addition, various types of equipment are also provided. This equipment 1 is equipped with detectors that detect the process amount or the operating status of each device, and signals from these detectors are sent to an input circuit 6.
is configured to be sent to. This input circuit 6 is configured to amplify each signal as necessary, convert it into a digital quantity, and send it to a signal processing circuit 7. This signal processing circuit 7 is configured to organize each signal and send these signals in a summarized form to the display mechanism 8. This display mechanism 8 is equipped with two CRTs 9 and 10, and the first
The CRT 9 is configured to summarize and always display the minimum information necessary for safe operation of the equipment 1, and the second CRT 10 is configured to display various detailed information by switching the keyboard 11. .

The first CRT 9 is configured to display information as shown in FIG. 2, for example. 12 is an item display column, starting from the top, reactor output 1
2a, reactor water level 12b, reactor pressure 12c,
The following items are displayed: reactor water amount 12d, containment vessel pressure 12e, and radiation dose 12f. Reference numeral 13 is a measured value display column in which measured values corresponding to each of the above items are displayed. This display is displayed as a bar graph 15 corresponding to the scale 14, and various limit value displays 16 are displayed above the scale 14 as necessary.
...is done. The measured value display column 13 is configured so that the measured values are displayed not only by the bar graphs 15 but also by the digital displays 17. Reference numeral 18 is a change rate display field, which is configured to display the change rate of the measured value in correspondence with each item. This display displays upward arrows 19 when the rate of change is positive, downward arrows 20 when the rate of change is negative, and horizontal lines 21 when the rate of change is zero. Display. In this change rate display column, the change rate is also displayed on a digital display 22.

The measured values and rate of change of each of these items have been processed by the signal processing circuit 7. For example, the measured value and rate of change of the reactor water level 12b have been processed as shown in Figure 3. Is displayed. 2 is a reactor pressure vessel, and this reactor pressure vessel 2 is provided with narrow area water level gauges 23a, 23b, and 23c. These narrow area water level gauges 23a, 23b, 23
All c measure the water level in the reactor pressure vessel 2 in a relatively narrow range, and the same structure
There are several. These narrow area water level gauges 23a, 2
Signals from 3b and 23c are sent to upper and lower limit check sections 24a, 24b and 24c, respectively. These upper and lower limit check sections 24a, 24b, and 24c detect whether the signal exceeds the measurement range of the narrow water level gauges 23a, 23b, and 23c, that is, whether there is upscaling, downscaling, or an abnormality in the power supply. However, if any of these abnormalities occur, messages 25a, 25b, 25c are displayed to the effect that the water level gauges 23a, 23b, 23c are out of order. If these abnormalities do not occur, the signals from the water level gauges 23a, 23b, and 23c are sent to comparators 26a, 26b, and 26c, respectively, to check whether the absolute value of the mutual deviation is smaller than the allowable deviation value e. Determine. If these deviations are below the allowable deviation value e, these signals are sent to the computing units 27a, 27b, 27c, and the average values G ₁ , G ₂ ,
G ₃ is required. In addition, if the deviation exceeds the allowable deviation value, the arithmetic units 27a, 27b, 27c
Let G ₁ , G ₂ , and G ₃ be each zero. The signals from these computing units 27a, 27b, and 27c are transmitted to the computing unit 2.
8, and the average value G of these signals G ₁ , G ₂ , G ₃ is determined. This average value is
Display on 9th grade. In addition, the arithmetic units 27a, 27
If the signals G ₁ , G ₂ , and G 3 from G 1 , G 2 , and G ₃ from G 2 and 27 C are all zero, it is assumed that all of the narrow-area water level gauges 23 a, 23 b, and 23 c have failed, and other water level measurement systems, such as large fluctuations in the reactor water level, are detected. At times, the mode shifts to the use mode of wide-area water level gauges installed to measure this or as back-up water level gauges for narrow-area water level gauges.

The water level measurement signal obtained in this way is processed as shown in Figure 4 to determine the rate of change, etc.
It is displayed on the CRT9 mentioned above. Reference numeral 29 denotes a signal converter, and the signal converter 29 converts an analog signal into a digital signal. This signal is converted into engineering units by the engineering unit converter 30.
The measurement signal converted by the engineering unit conversion section 30 is sent to the current value digital memory section 31a of the movable drawing information memory 31, and is digitally displayed on the screen of the CRT 9. Further, the signal from the engineering unit converter 30 is sent to the bar graph head display calculation unit 32, and the head coordinates of the bar graph display are calculated. The output from this bar graph head display calculation unit 32 is sent to the bar graph head memory unit 31b.
Displayed as a bar graph on the CRT9. Also,
This signal is sent to the current value comparison section 33, which determines whether the current value exceeds various limit values, and if it exceeds the limit values, drives the current value display color change blinking section 34, The current value display color changes/
The signal is sent to the blinking memory section 31c, and the display on the CRT 9 changes color or blinks. Next, this signal is sent to the rate of change calculating section 35, and the rate of change over time is determined. This change rate signal is then sent to the change rate memory section 31d and displayed on the CRT 9. Further, the signal from this rate of change calculation section 35 is sent to a change graphic display selection section 36, and when the rate of change is positive, an upward arrow is displayed, and when the rate of change is negative, an arrow pointing downward is displayed. When is zero, a signal for displaying a horizontal line is output, and this signal is sent to the rate of change graphic display memory section 31e to be displayed on the CRT 9. Further, this signal is sent to the rate of change comparison section 37, which is configured to display whether the rate of change exceeds various limit values. If it exceeds the limit value, it is sent from the rate of change display color change/flash unit 38 to the change rate display color change/blink memory 31f and displayed on the CRT 9. When this series of processing is completed, the process returns to signal conversion by the signal conversion section 29, and the measurement signals are continuously processed in this manner and displayed on the CRT 9. Note that displays of frames, characters, etc. other than those based on the measurement signals mentioned above are stored in the fixed drawing information memory 39 in advance.
The frames, characters, etc. are stored in the frame memory section 39a and character memory section 39b of the CRT.
Display on 9.

According to this embodiment, the minimum information necessary for the safe operation of the reactor equipment, such as reactor power, reactor water level, and reactor internal pressure, is always displayed on the same screen, so that the entire reactor equipment can be monitored. You can easily understand the condition,
This reduces the burden on the operator and prevents erroneous operations.

Each item displayed is displayed as a numerical value, a bar graph of this numerical value, and an arrow indicating the rate of change, so it can be efficiently arranged on the same screen, visibility can be improved, and the status can be accurately grasped.

If the narrow-area water level gauge that detects the reactor water level is abnormal, it will shift to the wide-area water level gauge usage mode.
Highly reliable water level display is possible.

〔Effect of the invention〕

According to the present invention, important items among the process quantities of nuclear reactor equipment are displayed on the same screen, so the status of the entire equipment can be easily grasped, the burden on operators is reduced, and inappropriate You can reduce the possibility of performing unnecessary operations.

[Brief explanation of the drawing]

The drawings show one embodiment of the present invention; FIG. 1 is an overall schematic diagram, FIG. 2 is a diagram showing an example of the display of the display mechanism, FIG. 3 is a flowchart of signal processing in the case of reactor water level measurement, and FIG. FIG. 4 is a flowchart of signal processing for the same display. 8...Display mechanism, 9...CRT, 12a...Reactor power, 12b...Reactor water level, 12c...Reactor internal pressure, 12e...Containment vessel internal pressure, 12f
...Radiation dose, 15...Bar graph, 17...Digital display, 19,20...Arrow.

Claims (1)

[Claims] 1 A detector that measures reactor power, reactor water level, reactor internal pressure, reactor containment vessel internal pressure, and radiation dose, and a signal converter that converts analog signals measured by these detectors into digital signals. , an engineering unit converter that converts the measurement signal from the signal converter into engineering units; a bar graph head display calculation unit that calculates the head of the bar graph based on the measurement signal processed by the engineering unit converter; a change rate calculation section that calculates a temporal change rate from the measurement signal processed by the engineering unit conversion section; a change rate display selection section that selects whether the change rate is positive, negative, or zero; the engineering unit conversion section; A movable drawing information memory stores the signals processed by the bar graph head display calculation section, the rate of change calculation section, and the rate of change display selection section, and the signals from the movable drawing information memory are used to calculate the reactor output, the reactor water level, and the atom. The pressure inside the reactor, the pressure inside the reactor containment vessel, and the radiation dose are expressed in the same way by numerical values, a bar graph of these values, and an arrow indicating upward when the rate of change of the numerical values is positive and downward when negative. A monitoring device for nuclear reactor equipment, comprising a display mechanism that displays information on a display screen.