KR101230846B1 - Excore detector module in nuclear power plant and excore detecting method for the same - Google Patents

Abstract

PURPOSE: An excore detection module of a nuclear reactor and an excore detecting method of the nuclear reactor using the same are provided to measure the amount of neutrons in a wide region around the nuclear reactor by movably installing a plurality of excore detectors around the nuclear reactor. CONSTITUTION: An excore detector(110,120,130,140) is installed around a nuclear reactor and measures the amount of neutrons leaked through the nuclear reactor. A first sub detection location(A) is formed in the left side of the first excore detector. A second sub detection location(B) is formed in the right side of the first excore detector. A moving unit moves the excore detector around the nuclear reactor.

Description

Off-road measurement module for nuclear reactor and method for off-road measurement using nuclear reactor {{core detector module in nuclear power plant and excore detecting method for the same}

The present invention relates to an off-road measurement of a nuclear reactor, and more particularly, an off-road measurement module of a nuclear reactor and an out-of-counter measurement using the same, which allow the operation of a nuclear reactor more stably and efficiently by installing an outside measurement instrument so as to be movable outside the nuclear fuel assembly. It was intended to provide a way.

The designer pre-calculates the maximum allowable power that the fuel can withstand and provides information, while the operator maintains the integrity of the fuel by operating it not to exceed the maximum allowable power.

The output distribution in the core consists of a radial output distribution and an axial output distribution. The radial output distribution is determined at the design stage according to the fuel assembly loading model including the appropriate distribution of the burnable absorber, but the shaft Directional output distribution is difficult to control due to xenon transition, so Westinghouse (hereinafter referred to as WH) type power plant has set operating allowance area for axial output distribution to maintain nuclear fuel integrity.

In the past, the constant Axial Offset Control (hereinafter referred to as CAOC) operation with limited operation allowable area with narrow axial output deviation range, regardless of core output level, was performed. In recent years, the flexibility of operation has been enhanced by adopting the relaxed Axial Offset Control (RAOC) operation method which has wider axial output deviation operation allowance at low power.

The operator monitors the axial output distribution using the core output distribution measuring system at all times so as not to deviate from the defined driving allowance area.

The core output distribution measuring system includes an incore detector and an excore detector, and an in-house instrument of a domestic WH-type power plant has a fission chamber detector (235 U concentration of about 90 U) freely inserted and withdrawn from the core. It is a w / o type U3O 8) type movable detector, which is normally located outside the reactor vessel to prevent the instrument's consumption and performance degradation due to strong neutron flux and heat in the furnace. It is inserted into the core and used for core output distribution measurement.

On the other hand, the outside instrument is an important device that allows the operator to constantly monitor the core output level and the axial output distribution during the output operation by detecting the neutrons leaked outside the reactor vessel is installed outside the reactor vessel, WH type instrument is a non-compensation type It uses 10B (n, α) 7Li reaction as an uncompensated ion chamber and consists of a top detector and a bottom detector, each about 150 cm in length, and four symmetrically outside the core. Channels are arranged to indicate axial output deviations.

If the axial output deviation instructed by the external instrument is outside the preset steady-state axial output deviation range, it acts as a penalty to the trip setpoint, which affects the generation of the reactor stop signal. It is important to be able to accurately describe the output distribution at all times.

The out-of-measuring instrument changes the quantity and distribution of the leaking neutrons even at the core output level, such as the detection of the out-of-leak neutrons, so the out-of-measuring instrument needs to be calibrated regularly for accurate core power distribution prediction.

The calibration of the out-of-counter instrument is performed based on the axial output deviation measured using the in-house instrument, and is composed of two stages of acquiring the out-of-labor instrument calibration data using the in-house instrument and an actual work process of calibrating the out-of-labor instrument using the acquired data. .

At the current plant site, the performance of the off-site instruments is checked through core output distribution measurement tests once a month and calibration is performed every three months. Here, the calibration of the out-of-counter instrument means that the core output is measured by measuring the actual output distribution of the core through the core output distribution measurement test, and adjusting the resistance that converts the current generated by the out-of-meter instrument to the voltage by neutrons leaking out of the reactor vessel. This is to ensure that the distribution can be reproduced accurately.

FIG. 1 is a view schematically illustrating an off-road instrument installed in a conventional nuclear reactor, and the off-road instrument 30 applied to the conventional nuclear reactor has a state in which four nuclear fuels 1 are fixedly installed around a nuclear reactor 10. .

By the way, the conventional off-road instrument 30 is fixed to a certain point outside the reactor 10, the outside of the reactor where the off-site instrument is not installed to rely on the predicted value to guess the neutron weight, the accuracy is lowered Of course, there was a problem that the reliability of the guess value itself is further degraded when the off-site instrument itself is some malfunction.
Furthermore, the Republic of Korea Patent Publication No. 10-2010-0047536 discloses a calibration method for securing the reliability of the value measured in the fixed out-of-counter instrument as described above, but in that it is a calibration of the value measured by one measuring instrument at a specific point The problem is that it is not an accurate measurement.

SUMMARY OF THE INVENTION The present invention has been made in order to solve the aforementioned problems and drawbacks of the prior art, and an object of the present invention is as follows.

First, an object of the present invention is to provide a mobile unit capable of moving an out-of-measuring instrument to an output of a neutron at a point set outside the reactor, so that the output of the neutron can be detected at various points.

Second, the present invention provides a method for detecting neutrons outside of a reactor that can compare / calculate a plurality of neutron output values for a set measurement point to secure high reliability data or reduce errors between the actual output value and the measured output value.

The objects of the present invention are not limited to the above-mentioned objects, and other objects that are not mentioned will be clearly understood by those skilled in the art from the following description.

In order to achieve the above object, the present invention is to provide a nuclear fuel assembly for the nuclear reactor, the two or more out-of-war instrument and installed at every predetermined position along the outer periphery of the reactor and the off-road instrument to move around the reactor It provides an off-road measurement module configured to include a mobile unit.

Here, the mobile unit may move the out-of-furnace instrument along the circumference of the nuclear reactor at the same angle along the circumferential direction away from the outside of the nuclear reactor by a predetermined distance.

The out-of-laboratory instrument may be reciprocated from the reference detection position positioned in the initial state to the auxiliary detection position positioned symmetrically between the reference detection positions.

In addition, the auxiliary detection position may be provided at a position where each of the external measuring instruments overlap each other by movement so that two or more of the external measuring instruments can compare the detected values.

Each of the external measuring instruments may be rotated by 45 degrees to both sides along the circumferential direction from the reference detection position.

On the other hand, out-of-measurement measurement including two or more out-of-the-road instrument installed in each position spaced along the outer periphery of the reactor, and the mobile unit for moving the out-of-warn instrument to the initial reference detection position and the auxiliary detection position along the periphery of the reactor. A module comprising: a reference position detection step of detecting neutron output at the reference detection position, a moving step of moving the out-of-measurement instrument to an auxiliary detection position, and an auxiliary position detection step of detecting neutron output at the auxiliary detection position. Provided are a neutron detection method using an out-of-measure instrument of a nuclear reactor.

Here, the movement of the out-of-laboratory instrument by the mobile unit can be alternately moved to the auxiliary detection position.

The method may further include comparing the measured values measured by the respective out-of-laboratory instruments with each other at the auxiliary detection position.

The method may further include correcting a detection value of each out-of-laboratory instrument according to the compared measured value.

In addition, the present invention is an off-site measurement module comprising a two or more out-of-war instrument and installed in each position spaced along the outer periphery of the reactor and a moving unit for moving the out-of-war instrument along the reactor periphery, reference position A reference position detecting step of detecting the neutron quantity outputted from the step; detecting the neutron weight by moving the out-of-measuring instrument measuring the neutron weight at the reference position and an adjacent out-of-measuring instrument to the reference position, and comparing the detected value It provides a method for off-vehicle measurement of the reactor comprising the step of calculating.

Referring to the effects of the present invention, the off-road measurement module configured as described above and the off-road measurement method using the same as follows.

First, the present invention is provided with a plurality of off-the-counter instruments along the outer periphery of the reactor, by allowing the off-the-counter instrument to be movable, it is possible to measure the neutron weight over a wide area around the reactor to improve the reliability of the measured value You can do it.

Secondly, the present invention enables the plurality of out-of-the-counter instruments to be rotated along the circumferential direction with respect to the circumference, so that the output values output through the respective out-of-laboratory instruments can be compared. Therefore, the reliability is further improved, and depending on the situation, the effect of identifying the abnormal detector among a plurality of detectors is brought. Further, by analyzing the correlation of a plurality of output values it is possible to correct the output value of each detector.

The effects of the present invention are not limited to the effects mentioned above, and other effects not mentioned can be clearly understood by those skilled in the art from the description of the claims.

1 is a schematic representation of an off-road instrument installed around a reactor in accordance with the prior art;
2 is a schematic illustration of an out-of-range instrument installed around a reactor in accordance with the present invention;
3 is a block diagram showing the relationship between the main components of the reactor system according to an embodiment of the present invention;
4 is a block diagram showing the relationship between the main components constituting the reactor system according to another embodiment of the present invention;
5 to 7 are views showing the movement and operation of the off-road instrument in the off-road measurement module of the reactor according to the present invention.

DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS Hereinafter, preferred embodiments of the present invention will be described with reference to the accompanying drawings. In describing the present embodiment, the same designations and the same reference numerals are used for the same components, and further description thereof will be omitted.

First, with reference to the accompanying drawings will be described a structure according to a preferred embodiment of the present invention.

In the accompanying drawings, FIG. 2 is a schematic view showing a state in which an out-of-measurement instrument is installed along a circumference of a nuclear reactor according to an embodiment of the present invention, and FIG. 3 is a main view of a nuclear reactor equipped with an out-of-measurement instrument according to an embodiment of the present invention. A block diagram showing the relationship between the configurations.

As shown, the outside measurement module of the nuclear reactor according to an embodiment of the present invention is provided with the outside measurement instruments 110, 120, 130, 140 in the circumferential direction of the outer circumference of the reactor 10 having a nuclear fuel assembly (1) therein.

The outside measuring instruments (110, 120, 130, 140) are installed at predetermined spaced positions along the outer periphery of the reactor 10, two or more are provided.

In the following, four out-of-the-counter instruments 110, 120, 130 and 140 are installed around the reactor, which is a model mainly applied to the Korean reactor, for example.

As shown in FIG. 2, in the off-road measurement module according to the present invention, a first out-of-counter instrument 110, a second out-of-measure instrument 120, a third out-of-measure instrument 130, and a fourth out-of-measure instrument 140 are reactor 10. They are installed every 90 degrees along the circumferential direction outside the reactor from the center of.

On the other hand, in the off-road measurement module according to the present invention is provided with a mobile unit 170 for moving the off-road instrument (110, 120, 130, 140) around the reactor (10).

In this case, the mobile unit 170 rotates the connection rail unit 173 connecting the outside measuring instruments 110, 120, 130 and 140, and the connection rail unit 173 along a circumferential direction by a predetermined angle along the circumference of the reactor 10. It comprises a drive unit 174 for moving the outside of the instrument (110, 120, 130, 140) connected to the connection rail portion 173 together.

Although not shown in detail, the driving unit 174 may be a linear motor method for moving the connection rail unit 173 itself in the circumferential direction, or the driving unit 174 along the rail in which the circumferential rail is installed and installed. By operating the outside of the instrument 110, 120, 130, 140 may be moved.

Here, in addition to the above-described structure, the moving method and configuration of the external measuring instrument may be applied to various forms of known techniques and will be apparent to those skilled in the art, and thus detailed description thereof will be omitted.

On the other hand, the off-road measurement module according to the present invention is provided with a control unit 100 that is electrically connected to the off-road instrument (110, 120, 130, 140) and the mobile unit 170.

The control unit 100 operates the mobile unit 170 to adjust the position to be moved and stopped of the out-of-scope instrument (110, 120, 130, 140), and also to measure the amount of neutron emitted to the outside of the reactor through the out-of-war instrument (110, 120, 130, 140) And adjusting the compensation of the measured value through the measuring instrument.

As shown in FIG. 4, the mobile unit 170 may be installed separately for each of the outside measuring instruments 110, 120, 130, and 140.

In this case, each of the mobile unit 170 is also electrically connected to the control unit 100 to control the movement, and each of the outside measuring instrument forms a form directly coupled to the mobile unit 170 or the respective The outside of the instrument (110, 120, 130, 140) will be in the form of each mobile unit connected to the structure is installed.

Referring to the operation method of the off-road measurement module according to an embodiment of the present invention configured as described above are as follows,

First, four out-of-furnace instruments (110, 120, 130, 140) is located at the external reference detection position of the reactor 10 to measure the neutron leakage leaking through the reactor (10).

Here, the reference detection position refers to the position where the off-surface measuring instrument is installed in the previous nuclear reactor, that is, the position where the respective off-surface measuring instruments 110, 120, 130 and 140 are installed before the movement in the present invention.

Referring to FIG. 5, an initial reference detection position exists where four out-of-road instruments 110, 120, 130, and 140 are located at right angles to each other.

That is, the first outside instrument 110, the second outside instrument 120, the third outside instrument 130, and the fourth outside instrument 140 are respectively located at four positions around the reactor 10 in the stopped state. The position forms the reference detection position.

In addition, each of the outside measuring instruments (110, 120, 130, 140) from the reference detection position is moved to the auxiliary detection position in accordance with the operation of the control unit 100 and the mobile unit 170.

Each of the outside measuring instruments can be moved to both sides with respect to the reference detection position, and for convenience of description, the auxiliary detecting position provided on the left side with respect to the first outside measuring instrument 110 positioned at the reference detecting position will be described below. The first subsidiary detection position A is referred to as the second subsidiary detection position B as the right side subsidiary detection position.

For convenience of description, the first detector 110 is described as a reference, but since all four out-of-the-counter instruments 110, 120, 130, and 140 are moved, the first auxiliary detection position A and the second auxiliary detection position B may also be described. Of course, there will be four based on the detector.

On the other hand, after detecting the neutron weight through the respective outside measuring instruments at the reference detection position, the outside measuring instruments 110, 120, 130 and 140 are moved to the first auxiliary detection position (A) by the operation of the mobile unit 170. Let's do it.

The neutron weight is again detected using the respective out-of-furniture instruments at each of the first auxiliary detection positions A. FIG.

That is, the first outside instrument 110 detects the neutron amount at the first auxiliary detection position A, and the second outside instrument 120, the third outside instrument 130, and the fourth outside instrument 140 also reference. The neutron weight is measured by being positioned at the first auxiliary detection position by the angle of rotation of the first outside measuring instrument 110 from the detection position.

The measured neutron quantities are all measured and digitized by the controller 100.

Next, the first outlier measuring instrument 110 is moved back to the initial reference detection position to measure the neutron weight.

Then, the first outside instrument 110 is moved to the second auxiliary detection position (B), and the neutron weight at the second auxiliary detection position is measured.

In this case, the neutron mass at each auxiliary detection position located at the same rotational angle as that of the second outside instrument 120, the third outside instrument 130 and the fourth outside instrument 140, and the first outside instrument 110, respectively. Will be measured.

On the other hand, when the neutron weight values are detected at both the first and second auxiliary detection positions A and B, the adjacent out-of-measure instruments overlap each other to detect the neutron weight values. Done.

In more detail, as shown in FIGS. 6 and 7, the first exposing instrument 110 and the second exposing instrument 120 are located at the first auxiliary detection position A, and the first exposing instrument 110. And the fourth outside measuring instrument 140 measures the neutron mass at the second auxiliary detection position.

Similarly, the second outside instrument 120, the third outside instrument 130, the third outside instrument 130 and the fourth outside instrument 140 are also moved to undergo the process of detecting the neutron mass at the same detection position. .

As a result, according to the present invention, since the neutron weight is measured through the two out-of-the-measuring instruments at the same detection position, it becomes possible to compare the detected values according to the movement of the out-of-instrument instruments within a predetermined time.

In this case, since there is a time difference for the respective out-of-laboratory instruments to move to the same position, the predetermined error range is determined in advance, and when the measured value of each out-of-the-measurement instrument is within a certain level error range, the reliability of the measured value is possible.

On the other hand, if the error range is too large, as described above, the out-of-measuring instrument is rotated for a plurality of times, and the out-of-measuring instrument is measured alternately at the auxiliary detection position. If such a process continues to deviate from the error range, it may be identified as a malfunction of one of the off-site instruments.

In this case, the value measured at the reference detection position of the out-of-counter instrument causing one side malfunction is also less reliable. In this case, by moving the adjacent outside measuring instrument to the reference detection position to measure the neutron weight, for example, when the reliability of the first outside measuring instrument 110 is low, By moving the second exposing instrument 120 or the third exposing instrument 130 to measure the neutron weight, it is possible to grasp the exposing instrument and the malfunction value that cause the malfunction.

In addition, when the value of the out-of-measurement instrument causing a malfunction shows only a difference in a predetermined numerical value compared to a normally-operated out-of-measured instrument, and a change value of the changed neutron weight is normally indicated, measurement of the out-of-measurement instrument that caused the malfunction without a separate replacement. Only the values can be corrected for continuous use, thus increasing storage and stability.

On the other hand, the above-described method can be applied even when there is no out-of-furnace instrument causing a malfunction. That is, by measuring three out-of-the-counter instruments at one point and calculating an average value, the neutron weight value with higher reliability becomes possible at the point measured.

In particular, it is also possible to derive an average value over a certain time period, since it takes into account the time required for each of the off-the-shelf instruments to move to a point.

As described above, according to the present invention, a plurality of outside measuring instruments are provided along the outer circumference of the nuclear reactor, and the outside measuring instruments are installed to be movable, so that the neutron weight can be measured over a wide area around the nuclear reactor, and thus the reliability of the measured values. It will be possible to improve.

In addition, it is possible to compare the output value output through each of the external measuring instruments by allowing the plurality of external measuring instruments to rotate in the circumferential direction with respect to the circumference. Therefore, the reliability is further improved, and depending on the situation, the effect of identifying the abnormal detector among a plurality of detectors is brought.

Further, by analyzing the correlation of a plurality of output values it is possible to correct the output value of each detector.

It will be apparent to those skilled in the art that the present invention can be embodied in other specific forms without departing from the spirit or scope of the invention as defined in the appended claims. It is obvious to them. Therefore, the above-described embodiments should be regarded as illustrative rather than restrictive, and thus, the present invention is not limited to the above description and may be modified within the scope of the appended claims and their equivalents.

10: reactor 100: control unit
110, 120, 130, 140: off-site instrument 170: mobile unit

Claims (10)

In the off-road measurement module of a nuclear reactor equipped with a fuel assembly,
Two or more out-of-band instruments installed at predetermined spaced positions along the outer circumference of the reactor; And
A mobile unit which moves the out-of-furnace instrument along the reactor periphery;
The off-road measurement module of the reactor comprising a. The method of claim 1,
The mobile unit includes:
An off-road measurement module for a nuclear reactor according to the circumference of the nuclear reactor, characterized in that for moving the furnace at a predetermined rotational angle in the circumferential direction away from the reactor by a predetermined distance. The method of claim 1,
The external measuring instrument,
From the reference detection position located in the initial state,
An off-road measurement module of a nuclear reactor, characterized in that the reference detection position to be reciprocated to the secondary detection position located on both sides. The method of claim 3,
So that two or more of the out-of-labor instruments can compare the respective detected values,
The auxiliary detection position is an off-road measurement module of a nuclear reactor, characterized in that provided in the position where each of the outside measurement instruments overlap each other by movement. The method of claim 3,
Each outside measuring instrument,
An off-road measurement module for a nuclear reactor characterized in that it is rotated by 45 degrees on both sides in the circumferential direction from the reference detection position. An out-of-measurement module including two or more out-of-furnace instruments installed at predetermined spaced positions along the outer periphery of the reactor, and a mobile unit for moving the out-of-furnace instruments to the initial reference detection position and the auxiliary detection position along the periphery of the reactor. In the off-road measurement method of the used reactor,
A reference position detection step of detecting neutron output at the reference detection position;
A moving step of moving the out-of-laboratory instrument to an auxiliary detection position; And
An auxiliary position detecting step of detecting a neutron output at the auxiliary detecting position;
Method for measuring the outside of the reactor comprising a. The method according to claim 6,
The off-road measurement method of the nuclear reactor, characterized in that for the movement of the out-of-warn instrument by the mobile unit to be moved to each other to the auxiliary detection position. The method of claim 7, wherein
And comparing the measured values measured by the respective out-of-measuring instruments with each other at the auxiliary detection position. 9. The method of claim 8,
And correcting the detected value of each out-of-laboratory instrument according to the compared measured value. In the off-road measurement method of a nuclear reactor using an out-of-war measurement module comprising two or more out-of-warfare instruments installed at predetermined spaced positions along the outer periphery of the reactor and a mobile unit for moving the out-of-warn instruments around the reactor.
A reference position detecting step of detecting a neutron quantity output at the reference position;
Detecting the neutron weight by moving the out-of-measuring instrument measuring the neutron weight at the reference position to an reference position; And
Comparing / calculating the detected values;
Method for measuring the outside of the reactor comprising a.

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