JPH05312991A - Core neutron flux measurement device - Google Patents

Abstract

PURPOSE:To obtain a neutron flux measurement device capable of measuring in synchronizim with detector position. CONSTITUTION:When a detector is moved with a drive device 5 at a determined velocity in a core, a measuring region is set in a memory 20a and based on it, a data sampling controller 20 samples data at each measuring point of the detector. Therefore, even if the drive velocity of the detector changes, power distribution measurement corresponding to the detector position is possible.

Description

Detailed Description of the Invention

[0001]

BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention controls an in-core neutron flux distribution information obtained from a detector by controlling a drive unit for driving the insertion / extraction of a detector into / from a reactor core. It is about.

[0002]

2. Description of the Related Art FIG. 5 is a conventional example shown in the article "Automatic system for nuclear power measurement control equipment" published on pages 28 to 33 of "Mitsubishi Electric Technical Report" Vol. 64, No. 3 (1990). FIG. 4 is a block diagram showing the in-core neutron flux measurement apparatus, and FIG. 4 is a configuration diagram showing a nuclear power plant in which the apparatus is used.

In FIG. 4, 1 is a nuclear reactor, 2 is a nuclear reactor 1
Core, 3 is a detector that is inserted into and removed from the core 2 in order to collect information for reactor management such as measurement of neutron flux distribution, and 4 is a guide for inserting and removing the detector 3 into and from each part of the core 2. There are multiple thimbles to do.

Reference numeral 5 designates a driving device for driving the insertion / removal of the detector 3, and 6 designates a thimble 4 into which the detector 3 is to be inserted 5
A selection device having passages and 15 passages, 7 is a withdrawal limit switch for limiting the withdrawal of the detector 3, and 8 is a safety limit switch for preventing the withdrawal of the detector 3 too much.

Reference numeral 9 denotes a storage container in which the nuclear reactor 1, drive device 5, selection device 6 and the like are stored, and 10 denotes the storage container 9
Inside the reactor, which is arranged outside the device and controls the driving device 5 and the selecting device 6 to insert the detector 3 into a predetermined portion of the core 2 of the nuclear reactor 1 to collect predetermined information such as neutron flux distribution. This is a neutron flux measurement device.

In FIG. 5 showing a conventional in-core neutron flux measuring apparatus 10, 11 is a processor for controlling the entire in-core neutron flux measuring apparatus 10, 12 is a memory of the processor 11, and 13 is a man-machine interface with an operator. Input / output unit 14 including a display such as a CRT and a keyboard, and an input / output unit 13 for the processor 11
I / O interface connected to.

Reference numeral 15 denotes a process input / output unit (hereinafter referred to as process I / O) which issues a control command to the drive unit 5 under the control of the processor 11 and receives the information collected by the detector 3, and 16 denotes this process I / O. O15 for each drive 5
Is a drive interface connected to.

Reference numeral 17 is a floppy disk for storing information from the detector 3 processed by the processor 11, and reference numeral 18 is a floppy disk interface connecting the floppy disk 17 to the processor 11.

Reference numeral 19 is a manual operation panel which is connected to the drive unit interface 16 and backs up measurement control of the nuclear reactor 1 by manual operation when a failure occurs in the processor 11.

Next, the operation will be described. When performing the measurement of the neutron flux distribution in the core 2 of the nuclear reactor 1, the operator uses the input / output unit 13 to select a menu. The selected menu is sent to the processor 11 via the input / output unit interface 14.

The processor 11 refers to the memory 12 and, in accordance with the received menu sequence, processes I / O
A control command is set to the drive unit interface 16 via O15. Based on this control command, the four drive units 5 of "A" to "D" insert the detector 3 into the core 2 via the predetermined thimble 4 selected by the selection unit 6.

At the inserted thimble position in the core 2, the detector 3 is moved axially at a constant speed by the drive unit 5 and pulled out to measure the axial power distribution within a predetermined measurement range. When it is finished, it is further withdrawn to the position of the withdrawal limit switch 7. Even if the detector 3 does not stop at the position of the pull-out limit switch 7 for some reason, it will not be caught in the motor of the drive device 5 because it is backed up by the safety limit switch 8.

Thereafter, a new thimble 4 is selected by the selection device 6.
While making the selection, the drive device 5 is used to insert the detector 3 again into the core 2 of the nuclear reactor 1 via the selected thimble 4 and measure the axial power distribution at the thimble position. go. In this way, the axial power distribution is measured at all thimble positions in the core 2.

The output distribution in the axial direction measured by the detector 3 as described above is sent to the sequential drive unit interface 16 via the drive unit 5 and to the processor 11 via the process I / O 15. It is captured. Processor 1
Reference numeral 1 performs a predetermined process on the collected information to obtain a three-dimensional power distribution in the core 2.

If the obtained three-dimensional output distribution is sent to the input / output unit 13 via the input / output unit interface 14, it is displayed on the display screen and can be confirmed by the operator. Also, floppy disk interface 1
It is also possible to store the three-dimensional output distribution in the floppy disk 17 by sending the data to the floppy disk 8.

When an abnormality occurs in the processor 11, the manual operation panel 19 is used to disconnect the processor 11 from the system, and the operation of the manual operation panel 19
The measurement control described above can be performed manually by an operator.

[0017]

Since the conventional in-core neutron flux measuring apparatus is configured as described above, the processor 11 controls the drive unit 5 and collects the in-core neutron flux. Therefore, when collecting information from the detector 3, if the moving speed of the detector 3, that is, the drawing speed changes, data synchronized with the position of the detector 3 depending on the processing time of the processor 11 may not be collected. Yes,
There is a problem that proper data cannot be collected unless the drawing speed of the detector 3 is kept constant.

Further, since the conventional in-core neutron flux measuring apparatus controls the drive unit 5, the connection with the drive unit 5 should be removed when carrying out operation training of the in-core neutron measuring unit. It was necessary to connect a driving device simulation device for operation training instead, and there were problems such as securing facility space and the complexity of work due to connection changes.

The invention of claim 1 has been made in order to solve the above-mentioned problems, and the neutron flux distribution information from the detector can be collected as data synchronized with the detector position, and the operation of the processor 11 can be performed. Reduce throughput,
An object of the present invention is to obtain an in-reactor neutron flux measurement device having a system configuration capable of reducing the load.

According to the second aspect of the invention, when the operation training is carried out, the operation training can be carried out by connecting a man-machine interface such as a personal computer and the operation training is carried out by changing the initial state of the drive device simulation by the personal computer. The purpose is to obtain an in-core neutron flux measurement device that can be performed.

[0021]

According to a first aspect of the present invention, there is provided an in-core neutron measuring apparatus which detects a detector position and an in-core neutron flux in a minute cycle in order to obtain in-core neutron flux information corresponding to the detector position. A data collection controller for collecting information is provided.

An in-reactor neutron flux measuring apparatus according to a second aspect of the present invention is provided with a controller for a simulator so that a simulator signal of the driving device can be exchanged with a processor via a memory.

[0023]

Since the in-reactor neutron flux measuring apparatus according to the invention of claim 1 collects the detector position and in-reactor neutron flux information in a minute cycle, the drive speed of the drive motor for inserting and removing the detector, that is, the detector A device capable of collecting information corresponding to the detector position even if the drawing speed changes.

In the in-reactor neutron flux measuring apparatus according to the second aspect of the present invention, since the drive unit can be simulated only by connecting the man-machine interface of a personal computer or the like to the simulator controller, the drive unit can be connected during training. (EN) A device capable of performing operation training without operating a drive device without needing to release a cable.

[0025]

【Example】

Example 1. Embodiment 1 of the present invention will be described below with reference to the drawings. FIG. 1 shows an embodiment of the invention of claim 1, and FIG.
The same reference numerals are given to the parts corresponding to, and the description will be omitted.
In FIG. 1, reference numeral 20 is a data collection controller for collecting information from the detectors 2 housed in the four drive devices 5 “A” to “D”, and 20 a is a memory of the data collection controller 20.

Next, the operation will be described. When measuring the distribution of neutron flux in the core 2 of the nuclear reactor 1, the operator uses the input / output unit 13 to select a menu. The processor 11 refers to the memory 12 for an instruction by this selection operation, and issues a control command to the drive unit interface 16 via the process I / O 15. At this time, data indicating the measurement ranges P _X and P _Y of the thimble 4 for collecting the in-core neutron flux information is written in the memory 20 a of the data collecting controller 20 for the data collecting controller 20. Next, the operation of the data collection controller 20 will be described based on the processing flowchart of the data collection controller 20 shown in FIG.

First, in step ST1, the measurement ranges P _X and P _Y written in the memory 20a of the data collection controller 20 are read. Next step ST
According to 2, the data collection position l _K is calculated from the number N of measurement data collection points. In step ST3, the processor 1
After the detector 3 is inserted into the thimble 4 by a command 1, this detector 3 is withdrawn from the position of the starting end P _Y measurement points, detector position l _P a predetermined period T from the position of the P _Y To collect. Then, when the sampled detector position l _P becomes smaller than the data sampling point l _{K, in-} reactor neutron flux information is acquired in step ST5. In step ST6, if the detector position l _P becomes smaller than the end P _X of the data sampling measurement range, the data sampling ends, but if not, in step ST7, data is sampled for the next measurement point. After setting K = K + 1, the process returns to step ST3.

Thereafter, as in the conventional case, while sequentially inserting the detector 3 into the core 2 of the reactor 1 by driving the driving device 5 through the thimble 4 selected by the selecting device 6,
The output distribution in the axial direction at each thimble position is measured, and the output distribution in the axial direction at all the thimble positions in the core 2 is measured. The output distribution information in the axial direction in each thimble 4 measured in this way is stored in the memory 20a of the data collection controller 20 to the memory 12
Are transferred and stored by the processor 11.

Example 2. Next, an embodiment of the invention of claim 2 will be described with reference to FIG. In FIG. 3, reference numeral 21 is a controller for a simulation device that simulates the operation of the drive device 5,
a is its memory. An input / output unit 22 is provided with a CRT and a keyboard for setting an initial value of the drive device simulation and displaying the simulation state. Other configurations are the same as those in FIG.

Next, the operation will be described. The operation of measuring the axial power distribution of the nuclear reactor 1 of the in-core neutron flux measurement device 10 is performed in the same manner as in the conventional case.

Next, the operation in the case of conducting the operation training of the in-core neutron flux measuring apparatus 10 will be described. When carrying out operation training, the operator first uses the CRT and keyboard of the input / output unit 22 to perform initial settings for the simulation of the drive unit 5, for example, the stop position of the detector 3, the passage selection position of the passage selection device 6, and the core. The upper and lower limit positions for the thimble 4 of 2 are set. The simulation device controller 21 takes this setting and sets it as an initial value of the drive device simulation.

Next, if the instruction for starting the training execution is set by the processor 11 periodically referring to the memory 21a of the controller 21 for the simulation device, the memory address of the process I / O 15 is set to the simulation device. The processing for moving to the memory 21a of the controller 21 is performed. By this processing, the command from the processor 11 to the driving device 5 is not input / output from the process I / O 15 but
It is executed for this memory 21a.

This command information is sent to the simulation device controller 2
1 refers to and sets the memory 21a by simulating a signal input from the driving device 5 in response to the command. As a result, the processor 11 determines that the signal is from the process I / O 15 and performs the same operation as a normal measurement operation.

It is also possible to increase the types of training by variously changing the simulated initial value of the driving device 5 using the CRT of the input / output unit 22 and the keyboard. The simulation device controller 21 can be configured by changing the software of the data collection controller 20 of FIG.

[0035]

As described above, according to the first aspect of the invention, the data sampling controller is provided to collect data in synchronization with the position of the detector. Therefore, the output distribution measurement in the axial direction is performed. Even if the driving speed of the detector changes, the in-reactor neutron flux distribution corresponding to the detector position can be sampled regardless of the load amount of the processor, so that there is an effect that more accurate output distribution measurement can be obtained.

Further, according to the invention of claim 2, since the controller for the simulation device for simulating the operation of the drive device is provided, the connection to the drive device is disconnected or a new drive is performed at the time of training. There is an effect that the operator can perform operation training using the control panel without installing a partial simulator.

[Brief description of drawings]

FIG. 1 is a block diagram showing a first embodiment of the present invention.

FIG. 2 is a flowchart showing the operation of the first embodiment of the present invention.

FIG. 3 is a block diagram showing a second embodiment of the present invention.

FIG. 4 is a configuration diagram showing a nuclear power plant in which the present invention and a conventional in-core neutron flux measurement apparatus are used.

FIG. 5 is a block diagram showing a conventional in-core neutron flux measurement apparatus.

[Explanation of symbols]

 1 Reactor 2 Core 3 Detector 5 Driving Device 10 In-Reactor Neutron Flux Measurement Device 20 Data Collection Controller 21 Simulated Device Controller

Claims (2)

[Claims] 1. A driving device for driving insertion and extraction of a detector for measuring a neutron flux distribution in a reactor core into and from the reactor core, and processing measurement information obtained by the detector. An in-reactor neutron flux measurement device, comprising: a data collection controller for collecting the measurement information from the driven detector in synchronization with the detector position. 2. A drive device for driving insertion and extraction of a detector for measuring a neutron flux distribution in a reactor core into and from the reactor core, and processing measurement information obtained by the detector. An in-reactor neutron flux measurement device, comprising: a controller for an in-reactor neutron flux measurement device that executes a simulated operation of the drive device based on initial settings.