JPH06123793A - Reactor neutron flux measurement device - Google Patents

Abstract

PURPOSE:To grasp the neutron flux distribution in the whole reactor in a short time by indicating the neutron flux distribution in the whole reactor roughly in a graph. CONSTITUTION:A data processing part 4 outputs moving command through an output part 5 to a neutron detector 2 to make it detect neutron fluxes at each measuring point set in advance in a reactor 1 and stores the results in a memory part 7. An indication processor 11 adds every detection result of measuring points at the same core elevation. For example, if 60 measuring points are provided in the horizontal direction in the core, then the measuring points at the same core elevation is 60. Thus, 60 detection results are added. Also, if 325 measuring points are provided in the vertical direction in the core, then the data points added are 325. The processing part 11 indicates the added results in a graph on a display 9. This graph indicates that if the width is wide, the neutron flux is large.

Description

Detailed Description of the Invention

[0001]

BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a reactor neutron flux measuring device for measuring the output distribution of neutron flux in a nuclear reactor.

[0002]

2. Description of the Related Art FIG. 3 is a block diagram showing a conventional nuclear reactor neutron flux measuring apparatus, in which 1 is a nuclear reactor and 2 is a neutron flux for detecting a neutron flux at an arbitrary measurement point in the nuclear reactor 1. The detectors 3 are the neutron flux detectors 2 evenly in the reactor 1
By moving the inside of the reactor 1, the neutron flux detector 2 detects the neutron flux at each preset measurement point in the reactor 1, and the data collection unit 4 collects the detection result. The processing unit 5 is an output unit for outputting the movement command output from the data processing unit 4 to the neutron flux detector 2, 6
Is an input unit for inputting the detection result of the neutron flux detector 2 to the data processing unit 4, and 7 is a storage unit for storing the detection result collected by the data processing unit 4. Reference numeral 8 denotes a display processing unit that reads the detection results collected by the data collection unit 3 and causes the display unit 9 to display a graph for each detection result in which the horizontal direction of the measurement point (core x, y direction) is at the same position. is there.

Next, the operation will be described. First, the data processing unit 4 outputs a movement command to the neutron flux detector 2 via the output unit 5 to detect the neutron flux at each preset measurement point in the nuclear reactor 1. Here, as the measurement points in the nuclear reactor 1, for example, as shown in FIG. 4, points are equally divided into 325 in the core height direction and 60 in the horizontal direction (total 325 * 60 = 19500).
Measurement points).

Then, the data processing unit 4 inputs the detection result of the neutron flux detector 2 via the input unit 6, and stores the detection result in the storage unit 7.

Then, the display processing unit 8 selects the detection results stored in the storage unit 7 in the horizontal direction of the measurement point (core x,
Reading is performed for each detection result (data that differs only in the core height direction) in which the y direction) is at the same position. Then, select any one of the 60 measurement points in the horizontal direction, and at the selected location, the x-axis of the graph is the core height direction,
A graph as shown in FIG. 5 is displayed on the display unit 9 with the y-axis as the neutron flux detection result.

[0006]

Since the conventional reactor neutron flux measuring device is constructed as described above, it is impossible to recognize the distribution of the neutron flux in the entire reactor at a glance, and therefore, There was a problem that it took much time to understand the distribution of neutron flux in the entire reactor.

The present invention has been made in order to solve the above problems, and by displaying the distribution of neutron flux in the entire reactor in a schematic manner, the distribution of neutron flux in the entire reactor in a short time can be obtained. The purpose is to obtain a reactor neutron flux measurement device that can grasp

[0008]

A reactor neutron flux measurement apparatus according to the present invention reads detection results collected by a data collection unit and displays a graph for each detection result in which the horizontal direction of the core of a measurement point is at the same position. At the same time, the total of the detection results in which the core height direction of the measurement point is at the same position is integrated and the integrated result is displayed in a graph.

[0009]

The reactor neutron flux measuring device according to the present invention is
The detection results collected by the data collection unit are read, and a graph is displayed for each detection result in which the horizontal direction of the measurement point is at the same position in the core, and the results are integrated for each detection result in which the core height direction of the measurement point is at the same position. The distribution of neutron flux in the entire reactor is schematically displayed by providing the display processing unit that graphically displays the integration result.

[0010]

【Example】

Example 1. An embodiment of the present invention will be described below with reference to the drawings. FIG. 1 is a configuration diagram showing a reactor neutron flux measurement apparatus according to an embodiment of the present invention. In the figure, the same reference numerals as those of the conventional one indicate the same or corresponding portions, and therefore the description thereof will be omitted.

Reference numeral 11 reads the detection results collected by the data collecting unit 3 and measures the measurement points in the horizontal direction of the core (core x, y).
(Direction) is displayed in a graph for each detection result at the same position, and is integrated for each detection result in which the core height direction of the measurement point is at the same position, and the integrated result is displayed in a graph.

Next, the operation will be described. The data processing unit 4 collects the detection result of the neutron flux detector 2 and stores it in the storage unit 7.
Since it is stored in the same manner as the conventional example, the description thereof will be omitted.

When the data collection of the data processing unit 4 is completed, the display processing unit 11 displays the graph of FIG. 5 on the display unit 9 as in the conventional case. Further, the display processing unit 11
Integration is performed for each detection result where the core height direction of the measurement point is at the same position. Here, as shown in FIG. 4, since 60 measurement points are provided in the horizontal direction of the core, the number of measurement points at the same position in the core height direction is 60, and therefore,
The 60 detection results will be integrated. Further, since 325 measurement points are provided in the core height direction, the total number of data is 325.

Then, the display processing unit 11 displays the integrated result on the display unit 9 as a graph as shown in FIG. Note that the graph of FIG. 2 indicates that the wider the width direction is, the more the neutron flux is.

Example 2. In the above embodiment, the integration result is represented as shown in FIG. 2, but the integration result may be represented by a line graph or the like, and the same effect as that of the above embodiment can be obtained.

[0016]

As described above, according to the present invention, the detection results collected by the data collection unit are read, and a graph is displayed for each detection result in which the horizontal direction of the core of the measurement point is at the same position. Since the core height direction is integrated for each detection result at the same position and the integrated result is displayed as a graph, the distribution of the neutron flux in the entire reactor is displayed in a short time. It has the effect of being able to understand the distribution of neutron flux in the entire reactor.

[Brief description of drawings]

FIG. 1 is a configuration diagram showing a reactor neutron flux measurement apparatus according to an embodiment of the present invention.

FIG. 2 is a graph showing the distribution of neutron flux in the entire nuclear reactor.

FIG. 3 is a configuration diagram showing a conventional reactor neutron flux measurement apparatus.

FIG. 4 is an explanatory diagram illustrating measurement points of a nuclear reactor.

FIG. 5 is a graph showing a distribution of neutron flux.

[Explanation of symbols]

 1 Reactor 2 Neutron Flux Detector 3 Data Collection Section 11 Display Processing Section

Claims (1)

[Claims] 1. A neutron flux detector that detects a neutron flux at an arbitrary measurement point in the reactor, and a neutron flux detector that is moved in the reactor evenly to preset the inside of the reactor. The neutron flux at each measurement point is detected by the neutron flux detector, and the data collection unit that collects the detection result and the detection results collected by the data collection unit are read, and the horizontal direction of the core of the measurement point is the same position. A nuclear reactor neutron flux measuring device having a display processing unit for displaying a graph for each detection result and integrating for each detection result in which the core height direction of the measurement point is at the same position and displaying the integrated result in a graph .