KR20130010290A - Digital excore nuclear instrumentation system having thermal power automatic amending function - Google Patents

Abstract

PURPOSE: A digital excore nuclear instrumentation system having thermal power automatic amending function is provided to shorten maintenance time. CONSTITUTION: An amplifier(100) is installed in the upper, the middle and the lower part of a reactor wall. The amplifier amplifies the pulse and the current generated by nuclear fission. A signal processing unit(200) changes the input value received from the amplifier to a digital value. A signal processing unit automates the operation of a nuclear instrumentation system. A thermal power automatic amending unit(300) transmits a heat power correction value to the signal processing unit. [Reference numerals] (200) Signal processing unit; (300) Inputting a heat output measuring correction value(processing by communication); (AA) Upper part; (BB) Center; (CC) Lower part; (D1,D2,D3) Pulse amplifier; (E1,E2,E3) Linear amplifier; (FF) Containment penetration hole; (GG) Analog input card; (HH) Processor board; (II) Digital output card; (JJ) Digital input card; (KK) Analog output card

Description

DIGITAL EXCORE NUCLEAR INSTRUMENTATION SYSTEM HAVING THERMAL POWER AUTOMATIC AMENDING FUNCTION}

The present invention relates to a digital out-of-core nuclear instrumentation system with a thermal output automatic correction function, and more specifically, to a digital equipment of the existing analog out-of-core nuclear instrumentation equipment signal processing device, and to precisely correct the heat output measurement results calibrated manually. It relates to a technique for real-time output calibration using the heat output value continuously calculated by the.

The off-site nuclear instrumentation system continuously monitors the reactor neutron flux levels for all operating conditions and provides alarm and emergency stop signals to protect the reactor from overpower conditions.

It also provides input signals to the relevant reactor emergency stop circuits as required by the operating technical guidelines and supplies safety class signals in the output operating range to generate local power density and nuclear boiling escaping rate protection signals.

In addition, the off-site nuclear instrumentation system measures the neutron level of the reactor core from the nuclear fission box and generates the necessary signal through the 4 Bay signal processing device.

However, in order to count neutrons using a conventional analog circuit, a pulse of a mixture of nuclide information such as neutrons and gamma rays is measured and amplified, neutron pulses are selected, and the neutron pulses are changed into square waves to obtain pulse coefficients.

As a result of this procedure, the signal processing device of the off-the-shelf nuclear instrumentation system has a complex circuit configuration, lacks linearity in a wide band, and requires various kinds of repair spare parts, and requires high skill for system operation and calibration. The test and maintenance time is excessive.

In recent years, research and development has been made in connection with the present invention, and many others have been disclosed, including Korean Patent Publication No. 2001-0076546 (Measurement Control System of a Nuclear Power Plant).

Prior literature receives output data of power plant linkage system that selectively outputs data from equipment and sensors installed in the plant site through actual wiring or network, performs safety function for single failure of nuclear power plant, and shows the result of performance. A protection system for transmitting information and soft control gateways and QIAS-dedicated data communication networks (DCN-Q); A control system that receives the output data of the power plant linkage system through a network and transmits it through a gateway and an IPS dedicated data communication network (DCN-I); And information processing system (IPS) which receives various sensor and processor related data from the protection system and control system, alarm and safety related variables provided from the RM protection system and control system, and display a plurality of flat panel displays (FPD). A monitoring system including an indication and alarm system (QIAS) for controlling the input and output of indication and alarm data by a software program, and a large display panel (LPD) for displaying information exchanged through the gateway between the IPS and the QIAS. It is configured by.

As described above, the prior art uses a method of amplifying a current pulse and preventing a pulse below a certain size from being input to a counter and making it a square wave that is good for counting through pulse shaping. The effect of this splitting alpha particle and the gamma ray on the reactor must be minimized.

In addition, the nuclear instrumentation system of the existing nuclear power plant divides the current output of the nuclear fission box into upper, middle, and lower outputs and amplifies them, and then changes the value of the semi-fixed resistance during the "average and sum calculation" process. Therefore, the heat output measurement results are manually calibrated using the heat output measurement results, and thus the heat output measurement results cannot be applied to the reactor output calibration in real time.

The first object of the present invention is to digitize an existing analog signal processing apparatus, thereby simplifying circuit configuration, automating system operation and calibration, and shortening test and maintenance time.

In addition, a second object of the present invention is to increase the detection efficiency and improve the accuracy of neutron measurement by using an energy discrimination algorithm using a multinuclide analysis technique.

A third object of the present invention is to automatically calibrate a nuclear measurement system using heat output, and to continuously perform calibration using heat output measurement results using a precision measuring instrument such as an ultrasonic flowmeter.

The present invention for achieving the technical problem relates to a digital nuclear nuclear instrument system with a heat output automatic correction function, which is installed on the upper, middle and lower portions of the outer wall of the reactor to amplify the pulse and current generated in the nuclear fission box An amplifier; A signal processing device for converting an input value provided from an amplifier into a digital signal and receiving a heat output measurement correction value from a heat output automatic calibrator in real time to automate the entire operation of the nuclear measurement system; And a heat output automatic compensator for calculating a heat output measurement correction value using an algorithm in real time and transmitting the same to a signal processing apparatus. It includes.

The amplifier may further include: a pulse amplifier configured to amplify a pulse generated in a nuclear fission box and to amplify a pulse proportional to a neutron flux to provide an input value for calculating a total count rate and a start rate proportional to the number of neutron incidents to an analog input card of the signal processing apparatus; And a linear amplifier providing an input value for calculating an output level of the nuclear power plant by linearly amplifying a current generated in the nuclear fission box and proportional to the neutron flux to an analog input card of the signal processing apparatus. It includes.

In addition, the signal processing apparatus, which receives the analog signal from the amplifier consisting of three pulse amplifiers and three linear amplifiers installed on the upper, middle and lower portions of the outer wall of the reactor, and performs the function of converting into a digital signal through a signal verification step Input card; Compute the input values of pulse amplifiers and linear amplifiers converted from analog input cards to digital signals and the thermal output measurement correction values transmitted from the thermostat automatic calibrator to obtain the calculation values necessary for power plant start-up, operation control, protection and monitoring. Process board; A digital input card, which is an input terminal for receiving the manual operation signal of an operator and a contact signal transmitted from another system and confirming the soundness of the output from the outside; A digital output card for outputting a contact signal to receive information on the status of the off-grid output system, the output status of the power plant, and the output alarm from another system; And an analog output card for providing various protection and control signals for various linkage systems related to the off-site nuclear measurement system, and for providing a signal for the core protection calculation system to calculate local power density and nuclear boiling escape rate. It includes.

In addition, the automatic heat output corrector, characterized in that the continuous calibration of the nuclear measurement system using the heat output measurement results using a measuring instrument including an ultrasonic flowmeter.

In addition, the total counting rate is a neutron pulse calculation method using different energy levels of gamma rays, neutrons, and alpha rays. And a net nucleus, a gamma ray, and an alpha ray, each of which has a net coefficient, and is derived from a multinuclide analysis technique using the result of the count.

으로 도출할 수 있는 것을 특징으로 하는 것을 포함한다.
In addition, the starting rate has a large range of neutron counts measured at the start-up and output rise of the reactor.

It includes that which can be derived as.

According to the present invention as described above, by digitizing the existing analog signal processing device, using the energy discrimination algorithm using the multinuclide analysis technique, and automatically calibrating the nuclear measurement system using the heat output, the circuit configuration is simple and system operation Automated and over-calibration reduces test and maintenance time, improves detection efficiency, improves neutron measurement accuracy, and continuously calibrates using heat output measurement results using precision instruments such as sonic flow meters.

1 is an overall configuration diagram of a digital out-of-core nuclear instrumentation system with a heat output automatic correction function according to the present invention.
Figure 2 is a block diagram of the amplifier of the digital external nuclear measurement system with a heat output automatic correction function according to the present invention.
Figure 3 is an algorithm implemented to calculate the activation rate of the digital off-shore nuclear instrumentation system with a heat output automatic correction function according to the present invention.
4 is a block diagram of a signal processing apparatus of a digital out-of-core nuclear instrumentation system with a heat output automatic correction function according to the present invention.
5 is a conventional column output manual correction circuit.
6 is a schematic diagram of an automatic heat output corrector of a digital off-shore nuclear instrumentation system with a heat output automatic correction function according to the present invention.

Specific features and advantages of the present invention will become more apparent from the following detailed description based on the accompanying drawings. Prior to this, terms and words used in the present specification and claims are to be interpreted in accordance with the technical idea of the present invention based on the principle that the inventor can properly define the concept of the term in order to explain his invention in the best way. It should be interpreted in terms of meaning and concept. In addition, when it is determined that the detailed description of the known function and its configuration related to the present invention may unnecessarily obscure the subject matter of the present invention, it should be noted that the detailed description is omitted.

Hereinafter, a detailed description will be given on the basis of the accompanying drawings for the digital out-of-core nuclear instrumentation system with a heat output automatic correction function according to the present invention. 1 is an overall configuration diagram of a digital out-of-core nuclear instrumentation system with a heat output automatic correction function according to the present invention.

As shown in FIG. 1, the digital off-shore nuclear measurement system S equipped with the automatic thermal output correction function according to the present invention includes an amplifier 100, a signal processing device 200, and a thermal output automatic corrector 300. It is configured by.

First, as shown in Figure 2, the amplifier 100 is installed on the upper, middle and lower portions of the reactor outer wall, respectively, to amplify the pulse and current generated in the nuclear fission chamber, the pulse amplifier 110 and the linear amplifier 120 It is configured to include.

Specifically, the pulse amplifier 110 amplifies a pulse generated in the nuclear fission box and is proportional to the neutron flux, and provides an input value for calculating a total count rate and a start rate proportional to the number of neutron incidents.

The total counting rate can be obtained based on neutron counts, gamma ray counts and alpha ray counts by multinuclide analysis. The energy level of the alpha particles is 4.7 Mev, the energy of fission products by neutrons is 165 Mev, which can be distinguished from the energy level, and the gamma energy is lower than that of the alpha particles.

Multinuclide analysis is a method of calculating neutron pulses using different energy levels of gamma, neutron, and alpha rays. ), The net coefficients of the neutron, gamma and alpha lines can be net coefficients.

FIG. 3 is a diagram illustrating an algorithm in which neutron pulse coefficient accuracy confirmation start rate calculation is implemented. As shown in FIG. 3, the neutron count value measured at the start-up and output rise of the reactor has a large range, and the result of the counting is expressed as a logarithmic count rate using a logarithmic function so that the operator can directly read it. Changes in reactor output are expressed in DPM (Decade Per Minute) to help operators understand.

이때 SUR은 기동률, T는 원자로의 주기이다.
Mobility rate is SUR =

SUR is the activation rate and T is the cycle of the reactor.

In addition, the linear amplifier 120 provides an input value for calculating the output level of the nuclear power plant by linearly amplifying a current generated in the nuclear fission box and proportional to the neutron flux.

In addition, as shown in FIG. 4, the signal processing apparatus 200 converts the input value provided from the amplifier 100 to digital and receives the heat output measurement correction value from the heat output automatic calibrator 300 in real time. The entire operation of the measurement system is automated, but includes an analog input card 210, a process board 220, a digital output card 230, a digital input card 240, and an analog output card 250.

Specifically, the analog input card 210 receives an analog signal from the amplifier 100 consisting of three pulse amplifiers 110 and three linear amplifiers 120 installed on the upper, middle, and lower portions of the outer wall of the reactor and verifying the signal. It converts to digital signal through.

In addition, the process board 220 is an input of the pulse amplifier 110 and the linear amplifier 120 converted into a digital signal from the analog input card 210 to obtain the operation value required for power plant startup, operation control, protection and monitoring Value and a heat output measurement correction value transmitted from the heat output automatic calibrator 300 to be communicated.

In addition, the digital input card 230 is an input terminal for receiving the manual operation signal of the operator and the contact signal transmitted from the other system to check the soundness of the outside output.

In addition, the digital output card 240 performs a function of outputting a contact signal to receive information on the status of the off-site output system and the power plant output status and output alarm from other systems.

In addition, the analog output card 250 provides various protection and control signals for various linkage systems related to the off-core nuclear instrumentation system, and provides a signal for the core protection operation machine to calculate the local power density and the nuclear boiling departure rate. .

In addition, as shown in FIG. 5, the nuclear measurement system of the conventional nuclear power plant divides the current output of the nuclear fission box into upper, middle, and lower outputs, amplifies the circuit, and then adds the semi-fixed resistance in the process of "average sum and sum". By changing the value of, calibrate manually by using the heat output measurement result in a fixed period.

However, as shown in FIG. 6, the automatic thermal output corrector 300 of the present invention calculates a thermal output measurement correction value using a new algorithm in real time and transmits it to the processor board 220 of the signal processing apparatus 200. .

값으로 계산된다.The heat output measurement correction value is

It is calculated by value.

Since the change value of the heat output constant is easily processed as a constant change in software, it can be utilized to continuously correct a precise output measurement result in the operation of a nuclear power plant through communication with an ultrasonic flowmeter.

While the present invention has been particularly shown and described with reference to preferred embodiments thereof, it will be understood by those skilled in the art that various changes in form and details may be made therein without departing from the spirit and scope of the invention as defined by the appended claims. It will be appreciated by those skilled in the art that numerous changes and modifications may be made without departing from the invention. And all such modifications and changes as fall within the scope of the present invention are therefore to be regarded as being within the scope of the present invention.

S: Digital out-of-core nuclear instrumentation system (S) with automatic thermal output correction
100: amplifier 110: pulse amplifier
120: linear amplifier 200: signal processing device
210: analog input card 220: process board
230: digital input card 240: digital output card
250: analog output card 300: thermal output automatic compensator

Claims (6)

In the digital out-of-core nuclear instrumentation system equipped with automatic thermal output correction,
An amplifier 100 installed on upper, middle, and lower portions of the outer wall of the reactor to amplify pulses and currents generated in the nuclear fission box;
A signal processing device (200) for converting the input value provided from the amplifier (100) to digital and receiving the heat output measurement correction value from the heat output automatic calibrator 300 in real time to automate the entire operation of the nuclear measurement system; And
A heat output automatic calibrator (300) for calculating a heat output measurement correction value in real time and transmitting it to the signal processing apparatus (200); Digital out-of-core nuclear instrumentation system with a heat output automatic correction function comprising a.
The method of claim 1,
The amplifier 100,
A pulse amplifier for amplifying a pulse generated in the nuclear fission box and proportional to the neutron flux and providing an input value for calculating the total count rate and the activation rate proportional to the number of neutron incidents to the analog input card 210 of the signal processing apparatus 200. 110; And
Linear amplifier 120 for providing an input value for calculating the output level of the nuclear power plant by linearly amplifying a current generated in the nuclear fission box and proportional to the neutron flux to the analog input card 210 of the signal processing device 200 ; Digital out-of-core nuclear instrumentation system with a heat output automatic correction function comprising a.
The method of claim 1,
The signal processing device 200,
Performs a function of receiving an analog signal from the amplifier 100 consisting of three pulse amplifiers 110 and three linear amplifiers 120 installed on the upper, middle, and lower portions of the reactor outer wall, and converting the signal into a digital signal through a signal verification step. An analog input card 210;
Input values and thermal output automatic compensators 300 of pulse amplifiers 110 and linear amplifiers 120 converted to digital signals from the analog input card 210 to obtain the operation values required for power plant startup, operation control, protection and monitoring. A process board 220 for calculating a heat output measurement correction value transmitted from the communication to the communication;
A digital input card 230 which is an input terminal for receiving a manual operation signal of an operator and a contact signal transmitted from another system and confirming the soundness of the outside output;
A digital output card 240 for outputting a contact signal to receive information on the status of the off-grid output system and the power output status and the output alarm in another system; And
An analog output card 250 for providing various protection and control signals for various linkage systems related to the off-core nuclear instrumentation system, and for providing a signal for the core protection calculation system to calculate local power density and nuclear boiling escape rate; Digital out-of-core nuclear instrumentation system with a heat output automatic correction function comprising a.
The method of claim 1,
The heat output automatic calibrator 300,
Digital out-of-core nuclear instrumentation system with a heat output automatic correction function characterized in that the calibration of the nuclear instrumentation continuously using the heat output measurement results using a measuring instrument including an ultrasonic flowmeter.
The method of claim 2,
The comprehensive counting rate,
A neutron pulse calculation method using different gamma, neutron, and alpha ray energy levels, using the peak area of the spectrum and the half-value width to net coefficients of the neutron, gamma, and alpha rays, respectively. Digital out-of-core nuclear instrumentation system with a heat output automatic correction function, characterized in that.
The method of claim 2,
The activation rate is,
The neutron counts measured during reactor start-up and output increase have a large range so that the operator can read them directly.

, But
'SUR' is the start-up rate, 'T' is a digital off-shore nuclear instrument system with a heat output automatic correction function, characterized in that the cycle of the reactor.

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