JPS58151590A - Monitoring device for reactor pipeline system - 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 monitoring device for monitoring the status of various piping systems installed in multiple layers of nuclear reactor equipment.

[Invention Ω Technical background]

Generally, boiling water reactor equipment includes a reactor recirculation system and a low-pressure core spool system. High pressure core spray system.

A piping system such as a reactor isolation cooling system is provided. These piping systems are composed of pipes, bongs, pulp, etc., and are configured to supply reactor water as a coolant into the reactor pressure vessel.

Conventionally, whether or not these piping systems operate normally has been determined as follows. In other words, in the central control room of the reactor building, there is a display run that displays the status of the valves, pumps, and piping capes that are the components of each piping system! and operation switches. For worker welfare, the status of the operating switches during these display rungs was checked to determine whether each piping system was operating normally.

[Problems with background technology]

The conventional example had the following problems.

First, each piping system has many valves and pumps, so workers have to deal with many of those valves.

Pumps etc. must be monitored. Moreover, the display rungs and operation switches in the central control room are scattered in various places, and it takes a long time for workers to check these many display rungs and operation switches, and the status of each piping system mentioned above. There was a problem that required a long time to understand.

Furthermore, there is a risk that the worker may misidentify the display lamp when checking the display rungs and operation switches.

Furthermore, workers have to manually operate the operation switches of equipment that is in an abnormal state, and it takes a long time to operate the numerous operation switches distributed in various locations.4
hTo was.

[Purpose of the invention]

It is an object of the present invention to be able to monitor the status of piping systems in nuclear reactor equipment using lighting time, to prevent workers from erroneously planing, and to automatically adjust piping systems in abnormal conditions to normal conditions.
An object of the present invention is to provide a reactor piping system monitoring device that can be used to restore nuclear reactor piping systems.

[Summary of the invention]

The reactor piping system monitoring device according to the present invention is provided with a detector for detecting the states of a fluid supply source, fluid supplied equipment, and piping system equipment between these that constitute the piping system of a nuclear reactor equipment, and The status of the supply source, fluid supplied equipment, and piping system equipment is detected, and symbols are attached to multiple fluid passing points and fluid supplied equipment in the fluid supply source and piping system, and these symbols are arranged in rows and columns. A symmetric matrix is defined, and the matrix element between symbols in which fluid can flow according to the signal from the detector is 1, and the matrix element between symbols in which fluid cannot flow or the piping system machine number does not exist. A signal processing circuit is provided to create a matrix representing the state of the piping system, and a memory circuit is provided to create a matrix representing the normal state of the piping system. A comparison circuit is provided to determine the state of the piping system by comparing the matrix created by the signal processing circuit with the matrix in the storage circuit, and a display mechanism is provided to make a determination from the comparison circuit. The results are displayed.

[Embodiments of the invention]

An embodiment of the present invention will be described with reference to FIGS. 1 to 4. Figure 1 is a piping system diagram of the high-pressure core spray system of boiling water reactor equipment, and this high-pressure core spray system supplies reactor water to the reactor pressure vessel in the event of a reactor water spill accident. 1 in the figure is a condensate storage tank as a fluid supply source for the piping system, and this condensate storage tank 1 and the reactor pressure vessel as the equipment to which fluid is supplied to the piping system. 2 are communicated with each other through a main pipe 3. In this pipe 3, there is a suction valve 4. Ponda 5. Injection valve6.
A check valve 1 is inserted to inject the condensate in the condensate storage tank 1 into the reactor pressure vessel 2. The main pipe 3 is connected between the suction valve 4 and the bomb f5 as a fluid supply source in the reactor containment vessel! The sag ledge pipe 9 from the ledge vent chamber 8 is branched and connected.
The structure is such that the water stored in the sag ridge chamber 8 can also be injected into the reactor pressure vessel 2 through this sag ridge vent pipe 9. -F record fee, shi.

A suction valve 10 is inserted into the intake pipe 9.

9. In the main pipe 3, there is a pipe/pi between the bonder 5 and the injection valve 6.
The piping 11 and 12 are branch-connected, and water is transferred to the condensate storage tank 1.1 during the operation test of the bonder 5. vinegar! It is configured to provide reflux to the ledge chamber 8. A pi/nine valve 13.14 is inserted into each pi/l piping 11.12. Furthermore, a minimum flow pipe 15 for preventing the Inf5 from reaching its limit is branch-connected to the main pipe 3 on the discharge side of the pump 5.
The other end of 5 communicates with the subledge chamber 8 . A minimum flow valve 16 is inserted into the minimum flow pipe 15 .

The condensate storage tank 1 which constitutes the high pressure core streak system mentioned above. /Fugu5. Detectors 11 to 14a are provided in the reactor pressure vessel 2 and the like to detect these states. The signals from the detectors 1a, . . . are configured to be transmitted to a signal processing circuit 17 shown in FIG.

This signal processing circuit 11 performs signal processing as follows.
First, the above condensate storage tank 1. Sashi ledge connection chamber 8 Numbers 1,8゜18~21.2 as symbols indicating multiple fluid passage points 18 to JJ and W sub-reactor pressure vessels 2 for the pressure core, x, fv and system 7 above. Arrange the above condensate storage tank 1. Subledge chamber 8. Bonder for piping system 5. Valve 4-16. A matrix between numbers where fluid cannot flow or a piping route does not exist, with the matrix element between numbers in a state where water can flow being 1 based on signals from detectors 11 to 16a installed in the reactor pressure vessel 2. The state of the high-pressure core spray system is expressed by setting the element to 0, and a matrix as shown in FIG. 3, for example, is created. The output signal from the signal processing circuit 11 is configured to be transmitted to a comparison circuit 18.

Comparison circuit 18 is configured to receive a signal from storage circuit 1#. The memory circuit 19 has previously stored in the memory circuit 19 a matrix shown in Figure 4, which is created in the same way as the above matrix and represents the normal state of the high-pressure reactor core stripe.

The comparison circuit 18 is configured to compare each matrix element of the memory circuit 19 with each matrix element of the signal processing circuit 17 to determine whether the high pressure core grayscale system is in a normal state. For example, the matrix of FIG. 3 has (xz, 2o) matrix elements compared to the matrix of FIG. 4 showing a normal state.

It can be seen that the matrix elements (20, 21) are different and the injection valve 6, which should be open between numbers 20 and 2, is closed. However, since both of the above matrices are symmetrical matrices, the comparison circuit 18 performs the above comparison for the upper triangular matrix or the lower triangular matrix. The comparison circuit 18 is configured to output a determination signal to the display mechanism 20.

The display mechanism 20 is configured to display the state of the high-pressure core grayscale system based on the determination signal.

(9) A plurality of operating mechanisms 4b~ in parallel with the display mechanism 20.
16k is connected to the comparison circuit IJ.

The above operating mechanism 4m-16b is the above-mentioned PON! It is provided corresponding to the 5° pulps 4 to 16, and the bonder 5. It is configured such that when the pulps 4 to 16 are in an abnormal state, a control section that controls them is operated to restore the pulps to a normal state.

The above structure has the following effects.

An operator can grasp the state of, for example, a high-pressure core streak system by simply looking at the display mechanism 20, and can judge the state of the high-pressure core streak system in a short time. In addition, the worker does not have to check the indicator lamps for each component of the piping system as in the past. 4ili! It is possible to eliminate the possibility that "i" will occur.

Further, the comparator circuit 18 only needs to compare whether the same matrix elements of both matrices are equal or not, and the structure of the comparator circuit IJ can be simplified and the comparison can be made evenly. Furthermore, since only the upper triangular or lower triangular matrices are compared, the time required for comparison can be further reduced.

Furthermore, the operating mechanisms 4b to 16b are operated by a pump 6° pulp 4 to
16 control parts are automatically returned to normal state,
The high-pressure core streak system can be returned to a normal state more quickly than when an operator manually operates a large number of operation switches.

Note that the present invention is not limited to the above embodiment. For example, the operating mechanisms 4b to 16b are provided with manual operation switches so that they can be used selectively, so that in the unlikely event that the operating mechanisms 4b to 16b malfunction, the pump 5. Valve 4-1
When 6 malfunctions, it is possible to manually operate it using the manual operation switch to improve the shaft reliability.

〔Effect of the invention〕

The reactor piping system monitoring device according to the present invention determines whether the nine piping systems are in a normal state by comparing a matrix representing the current state of the piping system with a matrix representing the normal state of the piping system. The system automatically returns the piping system to its normal state. Therefore, workers can easily and quickly determine the condition of the piping system without having to perform the difficult work of checking the condition of each element that makes up the piping system and determining the condition of the entire piping system. The effects are great, such as being able to automatically return the piping system to its normal state.

[Brief explanation of drawings]

Fig. 1 is a piping system diagram showing a high-pressure core streak base of nuclear reactor equipment, Fig. 2 is a configuration diagram showing an embodiment of the present invention, and Figs. 3 and 4 are included in an embodiment of the present invention. FIG. 3 is an explanatory diagram illustrating matrices that are compared by a comparison circuit. 6... Pump (piping equipment), 6... Injection valve (piping equipment), 1... Condensate storage tank (fluid supply source) 2.
・Reactor pressure vessel (fluid supplied equipment), 11-21・
...Fluid distribution point, 11-161...Detector, 17...
- Signal processing circuit, 18... Comparison circuit, 1#... Memory circuit, 20... Display circuit, 4b to 16b... Operation mechanism. Figure 3 1 8 18 19 20 21 2. 4th meal

Claims (3)

[Claims] (1) A fluid supply source and a fluid supplied device constituting the piping system of the atom-equipment, a detector installed in the piping system equipment between them to detect the state of these, and the fluid supply source and piping system A nine-symmetric matrix is defined by assigning symbols to a plurality of fluid passing points and devices to which fluid is supplied, and arranging these symbols in rows and columns. A signal section l1lI that creates a matrix of binary signals expressing the state of the piping system by setting matrix elements between symbols to 1 and matrix elements between symbols in which fluid cannot flow or the piping system equipment does not exist to 0; A circuit, a memory circuit that stores in advance a matrix that is created in the same way as the above matrix and represents the normal state of the piping system, and a nine matrix created by the signal processing circuit that is compared with the matrix of the memory circuit. a comparison circuit that determines the state of the piping system, a display mechanism that displays the determination result from the comparison circuit, and an operation mechanism that operates the control section of the piping system equipment based on the determination result from the comparison circuit. A nuclear reactor piping system monitoring device characterized by being equipped with the following. (2) The patented reactor piping system monitoring device is characterized in that the comparison circuit compares and determines the upper triangular matrix and the lower triangular matrix of both the matrices. (3) the operating mechanism operates the control unit (by remote control);
The reactor piping system monitoring device according to claim 1, characterized in that the device returns the piping system equipment to a normal state when it is in an abnormal state.