WO2017042876A1 - 炉内核計装装置 - Google Patents
炉内核計装装置 Download PDFInfo
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- WO2017042876A1 WO2017042876A1 PCT/JP2015/075402 JP2015075402W WO2017042876A1 WO 2017042876 A1 WO2017042876 A1 WO 2017042876A1 JP 2015075402 W JP2015075402 W JP 2015075402W WO 2017042876 A1 WO2017042876 A1 WO 2017042876A1
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- output voltage
- detection circuit
- current detection
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- gain
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
- G21C17/108—Measuring reactor flux
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
- G01T1/16—Measuring radiation intensity
- G01T1/17—Circuit arrangements not adapted to a particular type of detector
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T3/00—Measuring neutron radiation
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/001—Computer implemented control
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- H—ELECTRICITY
- H03—ELECTRONIC CIRCUITRY
- H03G—CONTROL OF AMPLIFICATION
- H03G1/00—Details of arrangements for controlling amplification
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- H—ELECTRICITY
- H03—ELECTRONIC CIRCUITRY
- H03G—CONTROL OF AMPLIFICATION
- H03G1/00—Details of arrangements for controlling amplification
- H03G1/0005—Circuits characterised by the type of controlling devices operated by a controlling current or voltage signal
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- H—ELECTRICITY
- H03—ELECTRONIC CIRCUITRY
- H03G—CONTROL OF AMPLIFICATION
- H03G3/00—Gain control in amplifiers or frequency changers without distortion of the input signal
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- H—ELECTRICITY
- H04—ELECTRIC COMMUNICATION TECHNIQUE
- H04B—TRANSMISSION
- H04B1/00—Details of transmission systems, not covered by a single one of groups H04B3/00 - H04B13/00; Details of transmission systems not characterised by the medium used for transmission
- H04B1/02—Transmitters
- H04B1/04—Circuits
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- H—ELECTRICITY
- H04—ELECTRIC COMMUNICATION TECHNIQUE
- H04B—TRANSMISSION
- H04B14/00—Transmission systems not characterised by the medium used for transmission
- H04B14/02—Transmission systems not characterised by the medium used for transmission characterised by the use of pulse modulation
- H04B14/04—Transmission systems not characterised by the medium used for transmission characterised by the use of pulse modulation using pulse code modulation
- H04B14/042—Special circuits, e.g. comparators
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- H—ELECTRICITY
- H04—ELECTRIC COMMUNICATION TECHNIQUE
- H04B—TRANSMISSION
- H04B1/00—Details of transmission systems, not covered by a single one of groups H04B3/00 - H04B13/00; Details of transmission systems not characterised by the medium used for transmission
- H04B1/02—Transmitters
- H04B1/04—Circuits
- H04B2001/0408—Circuits with power amplifiers
- H04B2001/0416—Circuits with power amplifiers having gain or transmission power control
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Definitions
- the present invention relates to an instrumentation device, and more particularly to an in-core nuclear instrumentation device applied to a nuclear reactor.
- the in-core nuclear instrumentation apparatus includes a movable neutron detector, and is applied to a pressurized water reactor and a boiling water reactor. Dozens of thimbles are inserted into the reactor to secure the neutron detector passage. In the thimble installed in the reactor, a movable neutron detector is introduced remotely to measure the power distribution of the core.
- the power distribution of the core is obtained by measuring the neutron flux in the reactor.
- a movable neutron detector is inserted into the thimble installed in the reactor vessel to detect the neutron flux.
- the in-core nuclear instrumentation device operates the movable neutron detector remotely to run in the thimble.
- An ultra-small ionization chamber type neutron detector is applied to the neutron detector.
- the movable in-core nuclear instrumentation device measures the neutron flux distribution in the axial direction from the upper end to the lower end of the fuel assembly in the reactor. Since the in-core nuclear instrumentation apparatus uses a plurality of movable neutron detectors, variations in the measured data due to individual differences in the detectors used occur. In order to obtain more accurate data, it is necessary to correct the sensitivity difference inherent in each detector. For example, the same measurement point is sequentially measured using all the neutron detectors, and the data is separately analyzed with a dedicated device (see Patent Document 1).
- the neutron flux distribution has been made closer to the true value by correcting the sensitivity difference for each detector using a dedicated device. Since this method uses another dedicated device for correction, it takes time to process the measurement data, and it does not constantly monitor the measurement data, so it cannot grasp the signs of deterioration of the neutron detector. Since an abnormal value is detected in the measurement data, the cause identification process is started, so the response may be delayed.
- the present invention has been made to solve the above-described problems.
- an in-core nuclear instrumentation apparatus equipped with a movable neutron detector measurement errors due to deterioration of the measurement system are suppressed, and soundness is maintained. It aims to make possible.
- An in-core nuclear instrumentation apparatus includes a neutron detector installed in a nuclear reactor housed in a containment vessel, an instrumentation unit having a current detection circuit and installed outside the containment vessel, The output signal of the neutron detector is input to the current detection circuit, and the instrumentation unit stores a matrix that associates the relationship between the reactor power of the reactor, the gain of the current detection circuit, and the output voltage Vn of the current detection circuit.
- the current detection circuit is calibrated with reference to this matrix.
- the in-core nuclear instrumentation apparatus since the detection sensitivity of the neutron detector can be calibrated, it is possible to suppress variations in measured values due to individual differences in detectors. Moreover, the accuracy as a measured value improves by suppressing the dispersion
- FIG. 1 is an overall view showing a configuration of an in-core nuclear instrumentation apparatus according to an embodiment of the present invention. It is a block diagram which shows the internal structure of the instrumentation unit concerning Embodiment 1 of this invention. It is a figure which shows the matrix showing the relationship between the gain and furnace output concerning embodiment of this invention. It is a process flow figure showing the 1st calibration procedure of the current detection circuit concerning an embodiment of this invention. It is a processing flow figure showing the 2nd calibration procedure of the current detection circuit concerning an embodiment of this invention. It is a block diagram which shows the internal structure of the instrumentation unit concerning Embodiment 2 of this invention. It is a block diagram which shows the internal structure of the instrumentation unit concerning Embodiment 3 of this invention.
- an in-core nuclear instrumentation apparatus will be described below with reference to the drawings.
- the same or similar components are denoted by the same reference numerals, and the sizes and scales of the corresponding components are independent.
- the configuration of the in-core nuclear instrumentation apparatus actually includes a plurality of members, but for the sake of simplicity, only the portions necessary for the description are shown, and the other portions are omitted. .
- Embodiment 1 FIG.
- the in-core nuclear instrumentation apparatus stores a matrix that correlates the relationship among the reactor power of the nuclear reactor, the gain of the current detection circuit, and the output voltage of the current detection circuit.
- the software (S / W) of the in-core nuclear instrumentation device automatically performs the correction calculation based on the correction function (processing flow) between the gain and the output voltage.
- the measurement data detected at a specific measurement point measured in common with all detectors is compared with a gain-output voltage matrix acquired in advance.
- FIG. 1 shows an outline of an in-core nuclear instrumentation apparatus 100 applied in a pressurized water reactor or the like.
- the in-core nuclear instrumentation device 100 includes an instrumentation unit 2, a neutron detector 3, a drive device 4, a passage selection device 5, a thimble 6 and the like.
- a nuclear reactor 7 and a containment vessel 8 are displayed as main components related to the in-core nuclear instrumentation apparatus 100.
- the nuclear reactor 7 is accommodated in a containment vessel 8 and includes a core 7a that is a measurement target.
- the neutron detector 3 is installed in a nuclear reactor 7 housed in a nuclear reactor vessel.
- primary primary equipment such as a pressurizer and a primary coolant pump is installed. Dozens of thimbles 6 are inserted into the core 7a.
- the neutron flux in the core 7a of the nuclear reactor 7 is detected by the movable neutron detector 3.
- the neutron flux distribution in the core 7a is measured by causing the neutron detector 3 to run remotely in a thimble installed in the reactor.
- An output signal (neutron flux signal) from the neutron detector 3 is input to the instrumentation unit 2 installed outside the containment vessel 8.
- the instrumentation unit 2 performs output signal detection, monitoring, data storage, and the like. Dozens of thimbles 6 are inserted into the reactor and serve as a passage for the neutron detector 3 inserted into the core 7a of the reactor 7.
- the neutron detector 3, the drive device 4, the passage selection device 5, and the thimble 6 are housed in the storage container 8. The operation (insertion and extraction) of the neutron detector 3 is performed remotely from the instrumentation unit 2.
- the driving device 4 receives an instruction or command from the instrumentation unit 2 and inserts the neutron detector 3 into the thimble 6 or pulls out the neutron detector 3 from the thimble 6.
- the passage selection device 5 selects the thimble 6 on which the neutron detector 3 travels.
- the instrumentation unit 2 is installed outside the storage container 8, but other drive devices 4 and the like are installed inside the storage container 8.
- a high DC voltage is applied to the neutron detector 3 in order to ionize the sealed gas by incident neutrons.
- the DC high voltage applied to the neutron detector 3 is set to a value (voltage) indicating a plateau characteristic so that the relationship between the detector current and the neutron flux density is not subject to fluctuations in the applied high voltage.
- the passage selection device 5 outputs a passage selection signal 11 indicating which passage (thimble) is currently selected for the neutron detector to the instrumentation unit 2.
- An output signal (neutron flux signal 9) from the neutron detector 3 inserted in the core of the nuclear reactor 7 is input to the instrumentation unit 2.
- the output signal of the neutron detector 3 is signal-processed by the instrumentation unit 2, and the neutron flux distribution in the core 7a is measured.
- an extraction operation command 10 b is output from the instrumentation unit 2 to the drive unit 4. .
- the drive device 4 extracts the neutron detector 3 from the reactor 7 to the passage selection device 5 in accordance with the extraction operation command 10b.
- the passage selection device 5 installed inside the storage container 8 is The passage (thimble) is switched, and the driving device 4 inserts the movable neutron detector 3 into another thimble 6 provided inside the nuclear reactor 7.
- the actual in-core nuclear instrumentation apparatus 100 is provided with a plurality of neutron detectors 3.
- the driving device 4 and the passage selecting device 5 can simultaneously run three to four neutron detectors 3 on a thimble 6 installed in the reactor.
- Fig. 2 shows the main configuration of the neutron flux measurement unit.
- the instrumentation unit 2 includes a high voltage generation card 21, a current detection circuit 22, an operation PC (Personal Computer) 23, a CPU card (Central Processing Unit card) 24, a communication card 25, a digital output card (Digital Output Card; DO card). ) 26, a digital input card (DI card) 27, a gain-output comparison unit 28, and the like.
- the operator outputs a command to the CPU card 24 through the operation PC 23.
- the high voltage generation card 21 applies a DC high voltage set by the operator to the neutron detector 3.
- the neutron detector 3 transmits a current signal (output signal) because the sealed gas is ionized by incident neutrons.
- the current detection circuit 22 converts the current signal (neutron flux signal 9) from the neutron detector 3 into a voltage signal.
- the operation PC 23 monitors the neutron flux distribution in the core based on the neutron flux signal 9 from the neutron detector 3.
- the operation PC 23 outputs an insertion operation command 10a into the core of the neutron detector 3 and an extraction operation command 10b from the neutron detector 3 to the outside of the core.
- An insertion operation command and an extraction operation command for the neutron detector 3 from the operation PC 23 are transmitted to the CPU card 24 via the communication card 25.
- the CPU card 24 executes an insertion operation instruction and an extraction operation instruction from the operation PC 23 in accordance with a programmed predetermined processing procedure.
- the digital output card (DO card) 26 transmits a high voltage setting signal 41 to the high voltage generation card 21 and transmits a gain control signal 42 to the current detection circuit 22.
- the digital input card (DI card) 27 receives the path selection signal 11 and the neutron detector current value corresponding signal 43. Since the current detection circuit 22 has a function as a programmable gain amplifier, the gain can be continuously changed.
- the gain-output comparison unit 28 stores a matrix that associates the relationship between the reactor output of the nuclear reactor 7, the gain of the current detection circuit 22, and the output voltage of the current detection circuit 22.
- the neutron detector current value corresponding signal 43 is a digital signal transmitted from the analog-digital conversion circuit 35 of the current detection circuit 22.
- FIG. 3 shows an example of a matrix that is stored in the gain-output comparison unit 28 and associates the relationship between the furnace output, the gain, and the output voltage. This data is acquired in advance at a specific measurement point that is commonly measured by all detectors.
- the matrix shown in the figure shows the relationship between the gain ( ⁇ n) and the output voltage Vn when the furnace power is increased by 1%.
- the output voltage Vn represents the output value ( ⁇ n) of the current detection circuit 22 (and the amplification circuit 32) obtained when the nuclear reactor is operated at n% of the maximum output before calibration.
- the gain ( ⁇ n) represents the amplification factor of the current detection circuit 22 (and the amplification circuit 32) under the condition that the output voltage Vn is obtained. Since there are a plurality of current detection circuits 22 (and amplification circuits 32), there are also a plurality of this matrix corresponding to each current detection circuit.
- the gain-output comparison unit 28 compares the reactor output with the matrix based on the neutron flux signal output (output voltage Vout) from the current detection circuit 22, determines the gain correction value, and corrects the output voltage. Calculate automatically.
- the instrumentation unit 2 is provided with a high voltage generation card 21, a current detection circuit 22, an operation PC 23, a CPU card 24, a communication card 25, a digital output card 26, a digital input card 27, and a gain-output comparison unit 28. Yes.
- the operation PC 23 is provided outside the instrumentation unit 2 panel, for example, in the central control panel, and the operator monitors the neutron flux distribution in the core and inserts and pulls out the neutron detector 3 with the central control panel. You can also.
- the current detection circuit 22 includes a current detection resistor 31, an amplifier circuit 32, a digital-analog converter (DAC) 33, a digital-analog converter control circuit (DAC control circuit) 34, and an analog-digital conversion circuit (AD conversion). Circuit) 35 and the like.
- DAC digital-analog converter
- AD conversion analog-digital conversion circuit
- Circuit 35 a voltage signal obtained by converting the current signal (neutron flux signal 9) from the neutron detector 3 by the current detection resistor 31 is referred to as an input voltage Vin.
- the output voltage Vout (A) indicates the output signal of the amplifier circuit 32.
- the output voltage Vout (D) indicates the output signal of the analog-digital conversion circuit 35.
- the current detection resistor 31 is installed on the input side of the amplifier circuit 32, and converts the current signal (neutron flux signal 9) from the neutron detector 3 into a voltage signal (input voltage Vin).
- the amplifier circuit 32 amplifies the voltage signal (input voltage Vin) converted by the current detection resistor 31 with a gain (G) specified by the gain control signal 42.
- the digital-analog converter 33 functions as an equivalent resistance of the feedback circuit of the amplifier circuit 32.
- the digital-analog converter control circuit 34 functions as an equivalent resistance control circuit that controls the digital-analog converter 33 based on the gain control signal 42 from the digital output card 26 and changes the equivalent resistance of the feedback circuit of the amplifier circuit 32. .
- the analog-digital conversion circuit 35 is a digital output circuit that outputs the output voltage signal of the amplifier circuit 32.
- the output signal of the analog-digital conversion circuit 35 is a digital voltage signal obtained by converting the detection current (neutron flux signal 9) in the neutron detector 3 into a voltage signal (input voltage Vin) and amplifying by the amplification circuit 32. . Therefore, the output signal of the analog-digital conversion circuit 35 is called a neutron detector current value corresponding signal 43 in addition to the output voltage Vout (D).
- the input voltage Vin of the amplifier circuit 32 is a detector current equivalent value detected by the current detection resistor 31.
- the digital-analog converter 33 functions as an equivalent resistance of the feedback circuit of the amplifier circuit 32.
- the digital-analog converter control circuit 34 functions as an equivalent resistance control circuit for the amplifier circuit 32.
- the gain control signal 42 is output from the operation PC 23 via the digital output card 26.
- the digital-analog converter control circuit 34 controls the value of the equivalent resistance of the feedback circuit installed in the feedback circuit of the amplifier circuit 32 according to the gain control signal 42.
- the gain of the current detection circuit 22 (or the amplification circuit 32) can be variably changed.
- the input voltage Vin detected by the current detection resistor 31 is amplified to the output voltage Vout (A) by the amplifier circuit 32 with a gain G corresponding to the gain control signal 42.
- This output voltage Vout (A) is AD converted into an output voltage Vout (D) by an analog-digital conversion circuit 35.
- the output voltage Vout (D) is also called a neutron detector current value corresponding signal 43, read into the digital input card 27, and processed by the CPU card 24.
- the input voltage Vin of the amplifier circuit 32 is a detector current equivalent value detected by the current detection resistor 31.
- the CPU card 24 outputs the set value of the DC high voltage input from the operation PC 23 to the high voltage generation card 21 as the high voltage setting signal 41 via the digital output card 26, and the DC voltage generated by the high voltage generation card 21. Set the high voltage.
- the high voltage generation card 21 generates a DC high voltage set by the operation PC 23 and applies this DC high voltage to the neutron detector 3.
- a pair of high voltage generation card 21 and current detection circuit 22 are shown.
- a card 21 and a current detection circuit 22 are installed in the instrumentation unit 2. For this reason, the current detection circuit 22 is called a neutron flux current detection circuit.
- the gain-output comparison unit 28 takes in the data of the neutron detector current value corresponding signal 43 measured at a specific measurement point that is common to all detectors that have arrived at the CPU card 24, and represents the relationship between the gain and the output voltage. To get. Compare that information with the gain-output voltage matrix acquired in advance, and whether the value of the neutron detector current value corresponding signal 43 is deviated from the matrix data acquired in advance due to neutron detector degradation, etc. Judge whether. When it is determined that the deviation is larger than the specified value, the gain-output comparison unit 28 automatically adjusts the gain by quoting the matrix and outputs the correct neutron detector current value corresponding signal. Alternatively, the current detection circuit 22) is calibrated.
- the instrumentation unit 2 extracts the output voltage Vn corresponding to the current furnace output from the matrix, and obtains the difference between the output voltage Vn corresponding to the current furnace output and the current output voltage Vout of the current detection circuit, When the obtained difference is larger than a specified value, calibration of the current detection circuit is started.
- FIG. 4 shows a first calibration procedure executed when the gain-output comparison unit 28 of the instrumentation unit 2 adjusts the gain of the amplifier circuit 32 (or the current detection circuit 22).
- This processing flow automatically adjusts the gain of the amplifier circuit 32 (or the current detection circuit 22) with reference to a gain-output voltage matrix acquired in advance.
- the gain-output comparison unit 28 first acquires information on the neutron detector current value correspondence signal, the reactor output, and the gain (S100, S101). Further, the gain-output comparison unit 28 extracts the current furnace output and the output voltage Vn of the current detection circuit 22 corresponding to the current gain from the matrix (S102).
- the value of the neutron detector current value corresponding to the current gain ( ⁇ n) is extracted from the matrix. Thereafter, this value (output voltage Vn) is compared with the current measured value of the current neutron detector current value corresponding signal (output voltage Vout). For this purpose, it is determined whether or not the acquired output voltage Vn is smaller than the current output voltage Vout of the current detection circuit. Next, when it is determined that the output voltage Vn is smaller than the output voltage Vout, a value smaller than the current gain (G) by a specified value is set as a new gain (G) of the current detection circuit. The current detection circuit operates with a new gain (G) and outputs a new output voltage Vout.
- the neutron detector current value corresponding signal 43 and the output voltage Vout (A) are essentially equal.
- the gain (G) is decreased by a specified value (for example, 0.1), and the process returns to step S103 (S104). As long as the result of the determination is yes (when output voltage V100 ⁇ output voltage Vout), S103 and S104 are repeated.
- step S105 If the result of the determination is no (if output voltage V100 ⁇ output voltage Vout), the process proceeds to the next step (S105). If the comparison result shows that the output voltage V100> the output voltage Vout, the gain (G) is increased by a specified value (for example, 0.1), and the process returns to step S105 (S106). As long as the result of the determination is yes (when output voltage V100> output voltage Vout), S105 and S106 are repeated. If the result of determination is no (if output voltage V100 ⁇ output voltage Vout), the process ends (S107).
- FIG. 5 shows a second calibration procedure executed when the gain-output comparison unit 28 of the instrumentation unit 2 adjusts the gain of the amplifier circuit 32 (or the current detection circuit 22).
- This processing flow automatically adjusts the gain of the amplifier circuit 32 (or the current detection circuit 22) with reference to a gain-output voltage matrix acquired in advance.
- the gain-output comparison unit 28 first acquires information on the neutron detector current value correspondence signal, the reactor output, and the gain (S110, S111). Further, the gain-output comparison unit 28 extracts the current furnace output and the output voltage Vn of the current detection circuit 22 corresponding to the current gain from the matrix (S112).
- the value of the neutron detector current value corresponding to the current gain ( ⁇ n) is extracted from the matrix. Thereafter, this value (output voltage Vn) is compared with the current measured value of the current neutron detector current value corresponding signal (output voltage Vout). For this purpose, it is determined whether or not the acquired output voltage Vn is larger than the current output voltage Vout of the current detection circuit. Next, when it is determined that the output voltage Vn is larger than the output voltage Vout, a value larger than the current gain (G) by a specified value is set as a new gain (G) of the current detection circuit. The current detection circuit operates with a new gain (G) and outputs a new output voltage Vout.
- the neutron detector current value corresponding signal 43 and the output voltage Vout (A) are essentially equal.
- the gain (G) is increased by a specified value (for example, 0.1), the current detection circuit is operated, and the process returns to step S113 (S114). As long as the result of the determination is yes (when output voltage V100> output voltage Vout), S113 and S114 are repeated.
- step S115 the process proceeds to the next step (S115).
- the gain (G) is decreased by a specified value (for example, 0.1)
- the current detection circuit is operated, and the process returns to step S115 (S116).
- S115 and S116 are repeated. If the result of the determination is no (if output voltage V100 ⁇ output voltage Vout), the process ends (S117).
- the in-core nuclear instrumentation apparatus performs the above processing for all neutron detectors.
- the calibration process flow of the neutron detector is completed, the correction of the difference for each detector is completed, and the variation in the measured value due to the individual difference in detector sensitivity can be suppressed.
- the variation of the measured value is suppressed, the accuracy as the measured value is improved. Since the in-core nuclear instrumentation apparatus according to the present embodiment performs this processing by itself, correction work with another dedicated apparatus is not required, and labor saving and shortening of work time are possible.
- a first object of the present invention is to eliminate the need for a dedicated device for correcting individual differences of neutron detectors, and to save labor for correction work and shorten work time.
- the in-core nuclear instrumentation device converts the neutron flux signal current from the neutron detector into a voltage signal, and obtains in advance a neutron flux current detection circuit capable of continuously varying the gain to be amplified. And a gain-output comparison section for comparing the measured gain-output voltage matrix and measurement data, and measuring the reactor core power distribution based on the output voltage signal of the neutron flux current detection circuit.
- the neutron flux current detection circuit controls the value of the equivalent resistance of the current detection resistor that converts the neutron flux signal current from the neutron detector into a voltage signal and the feedback circuit that amplifies the voltage signal converted by the current detection resistor. It is characterized by comprising a possible amplifier circuit, an equivalent resistance control circuit for changing the resistance value of the equivalent resistance of the feedback circuit, and an output circuit for outputting the output voltage signal of the current detection circuit.
- a second object of the present invention is to provide an in-core nuclear instrumentation apparatus that can suppress measurement errors due to deterioration of measurement system hardware and maintain soundness.
- the gain-output comparison unit takes in the data of the neutron detector current value corresponding signal 43 measured at a specific measurement point that is common to all detectors arriving at the CPU card 24, and calculates the gain and Acquire information on the furnace output voltage.
- the information is compared with the matrix of gain-output voltage acquired in advance, and the value of the neutron detector current value corresponding signal 43 deviates from the data of the matrix acquired in advance due to the deterioration of the detector, etc.
- the gain is automatically adjusted in accordance with the detector calibration process flow, and the correct signal value corresponding to the neutron detector current value is corrected.
- the in-core nuclear instrumentation apparatus 100 includes a gain adjustment width determination unit 29 in the instrumentation unit 2.
- the gain adjustment width determination unit 29 has a function of storing a gain adjustment width threshold value, receiving data from the gain-output comparison unit 28, and confirming an adjustment value of the gain (G) in the detector calibration processing flow. .
- the gain adjustment width determination unit 29 determines that the neutron detector or the measurement system hardware has deteriorated when gain adjustment is necessary beyond the threshold value of the gain adjustment width in the processing flow.
- the instrumentation unit obtains the difference between the gain after calibration and the gain before calibration, and determines that the apparatus has deteriorated when the obtained difference is larger than the threshold value.
- the in-core nuclear instrumentation apparatus can determine whether or not the neutron detector or measurement system hardware has deteriorated from the threshold value of the gain adjustment width, so that the neutron detector or measurement system hardware It is possible to determine when to replace the wear. That is, the in-core nuclear instrumentation apparatus according to the present embodiment includes a gain adjustment width determining unit having a function of confirming the gain adjustment width in addition to the configuration of the first embodiment.
- the in-core nuclear instrumentation apparatus 100 includes a signal switching unit 50 and a reference signal input unit 51 in the current detection circuit 22.
- the signal switching unit 50 is installed on the input side of the amplifier circuit 32, and executes an input signal switching operation for the amplifier circuit 32 according to an instruction from the reference signal input unit 51.
- an output signal (neutron flux signal 9) is input from the neutron detector 3 to the amplifier circuit 32.
- the signal switching unit 50 changes the input signal destination of the amplification circuit 32 from the neutron detector 3 to the reference signal input unit. Switch to 51.
- the input mode of the current detection circuit 22 is the determination mode, a simulation signal of the output current of the neutron detector 3 assumed from the current reactor output is input from the reference signal input unit 51 to the current detection circuit 22.
- the determination mode is executed using the method of the third embodiment, information on how the measurement system hardware behaves can be obtained when the signal from the neutron detector is correct.
- the method of the third embodiment is used to determine whether the detector has deteriorated or the measurement system hardware has failed. I can do it.
- the instrumentation unit according to the present embodiment is characterized in that a simulation signal is input to the current detection circuit, and the degradation point of the apparatus is determined based on the output voltage Vout of the current detection circuit corresponding to the simulation signal. . Therefore, it is possible to automatically cope with degradation of the neutron detector, degradation of the measurement system hardware, etc., and labor saving of the entire apparatus can be achieved. That is, the in-core nuclear instrumentation apparatus according to the present embodiment has a reference signal input unit for inputting a designated output current, a neutron detector signal, and a signal from the reference signal input unit in addition to the configuration of the second embodiment. And a signal switching unit for switching.
Abstract
Description
本発明の実施の形態に係わる炉内核計装装置は、原子炉の炉出力、電流検出回路のゲインおよび電流検出回路の出力電圧との関係を対応付けているマトリクスを記憶している。炉内核計装装置のソフトウエア(S/W)が、ゲインと出力電圧との補正関数(処理フロー)を基に補正演算を自動的に行う。中性子検出器の個体差を感度補正するには、全検出器共通で測定する特定の測定点で検出した測定データを、事前に取得している、ゲイン‐出力電圧のマトリクスと比較する。以下、実施の形態に係わる炉内核計装装置の動作および機能について、図に基づいて説明する。
実施の形態2に係わる炉内核計装装置を図6に基づいて説明する。図に示すように、本実施の形態に係わる炉内核計装装置100は、計装ユニット2にゲイン調整幅判定部29を備えている。ゲイン調整幅判定部29は、ゲイン調整幅の閾値を記憶し、ゲイン‐出力比較部28からデータを受け取り、検出器校正の処理フローにおけるゲイン(G)の調整値を確認する機能を備えている。ゲイン調整幅判定部29は、処理フローにおいてゲイン調整幅の閾値以上にゲイン調整が必要となった場合、中性子検出器あるいは測定系ハードウエアが劣化していると判断する。
実施の形態3に係わる炉内核計装装置を図7に基づいて説明する。図に示すように、本実施の形態に係わる炉内核計装装置100は、電流検出回路22に、信号切替部50と基準信号入力部51を備えている。信号切替部50は、増幅回路32の入力側に設置されていて、基準信号入力部51からの指示により、増幅回路32に対する入力信号の切替動作を実行する。電流検出回路22の入力モードが測定モードの場合、増幅回路32には、中性子検出器3から出力信号(中性子束信号9)が入力されている。操作用PC23からの指示により、電流検出回路22の入力モードが測定モードから判定モードに変更されると、信号切替部50は、増幅回路32の入力信号先を中性子検出器3から基準信号入力部51に切り替える。その結果、電流検出回路22の入力モードが判定モードの場合、現在の炉出力より想定される中性子検出器3の出力電流の模擬信号が基準信号入力部51より電流検出回路22に入力される。
Claims (8)
- 格納容器に収容された原子炉に設置される中性子検出器と、
電流検出回路を有し、前記格納容器の外側に設置される計装ユニット、とを備え、
前記中性子検出器の出力信号は前記電流検出回路に入力され、
前記計装ユニットは、前記原子炉の炉出力、前記電流検出回路のゲインおよび前記電流検出回路の出力電圧Vnの関係を対応付けているマトリクスを記憶しており、
このマトリクスを参照して前記電流検出回路を校正することを特徴とする炉内核計装装置。 - 前記計装ユニットは、前記電流検出回路を校正する際に、
前記マトリクスから、現在の炉出力および現在のゲインに対応した出力電圧Vnを抽出する第1のステップと、
前記第1のステップで抽出した出力電圧Vnが、現在の電流検出回路の出力電圧Voutよりも小さいか否かを判断する第2のステップと、
前記第2のステップで出力電圧Vnが出力電圧Voutよりも小さいと判断した場合、現在のゲインよりも規定値だけ小さい値を前記電流検出回路のゲインに設定する第3のステップと、
を実行することを特徴とする請求項1に記載の炉内核計装装置。 - 前記計装ユニットは、前記第2のステップのあとに、
前記第1のステップで抽出した出力電圧Vnが、現在の電流検出回路の出力電圧Voutよりも大きいか否かを判断する第4のステップと、
前記第4のステップで出力電圧Vnが出力電圧Voutよりも大きいと判断した場合、現在のゲインよりも規定値だけ大きい値を前記電流検出回路のゲインに設定する第5のステップと、
を実行することを特徴とする請求項2に記載の炉内核計装装置。 - 前記計装ユニットは、前記電流検出回路を校正する際に、
前記マトリクスから、現在の炉出力および現在のゲインに対応した出力電圧Vnを抽出する第1のステップと、
前記第1のステップで抽出した出力電圧Vnが、現在の電流検出回路の出力電圧Voutよりも大きいか否かを判断する第2のステップと、
前記第2のステップで出力電圧Vnが出力電圧Voutよりも大きいと判断した場合、現在のゲインよりも規定値だけ大きい値を前記電流検出回路のゲインに設定する第3のステップと、
を実行することを特徴とする請求項1に記載の炉内核計装装置。 - 前記計装ユニットは、前記第2のステップのあとに、
前記第1のステップで抽出した出力電圧Vnが、現在の電流検出回路の出力電圧Voutよりも小さいか否かを判断する第4のステップと、
前記第4のステップで出力電圧Vnが出力電圧Voutよりも小さいと判断した場合、現在のゲインよりも規定値だけ小さい値を前記電流検出回路のゲインに設定する第5のステップと、
を実行することを特徴とする請求項4に記載の炉内核計装装置。 - 前記計装ユニットは、校正後のゲインと校正前のゲインの差を求め、
この求められた差が閾値よりも大きい場合に装置に劣化が生じていると判断することを特徴とする請求項2または4に記載の炉内核計装装置。 - 前記計装ユニットは、前記電流検出回路に模擬信号を入力し、
この模擬信号に対する電流検出回路の出力電圧Voutをもとにして、装置の劣化箇所を判断することを特徴とする請求項6に記載の炉内核計装装置。 - 前記計装ユニットは、現在の炉出力に対応する出力電圧Vnと現在の電流検出回路の出力電圧Voutの差を求め、この求められた差が規定値よりも大きい場合に前記電流検出回路の校正を開始することを特徴とする請求項1に記載の炉内核計装装置。
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CN113436766A (zh) * | 2021-06-07 | 2021-09-24 | 中国核动力研究设计院 | 一种用于核电厂的堆外核仪表系统设备 |
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Citations (8)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS6256898A (ja) * | 1985-09-06 | 1987-03-12 | 株式会社日立製作所 | 中性子束較正装置 |
JPH07294688A (ja) * | 1994-04-21 | 1995-11-10 | Toshiba Corp | 原子炉出力監視装置 |
JPH1026668A (ja) * | 1996-07-10 | 1998-01-27 | Hitachi Ltd | 校正装置および中性子束測定装置 |
JP2000009877A (ja) * | 1998-06-24 | 2000-01-14 | Toshiba Corp | 原子炉出力監視装置 |
JP2000266884A (ja) * | 1999-03-16 | 2000-09-29 | Mitsubishi Electric Corp | 核計測装置 |
JP2002116283A (ja) * | 2000-10-05 | 2002-04-19 | Toshiba Corp | 原子炉のディジタル式出力領域モニタシステム |
JP2007040718A (ja) * | 2005-07-29 | 2007-02-15 | Toshiba Corp | 制御棒引抜監視装置 |
JP2013120057A (ja) * | 2011-12-06 | 2013-06-17 | Mitsubishi Electric Corp | 炉内核計装装置 |
Family Cites Families (26)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4053355A (en) * | 1975-10-14 | 1977-10-11 | The United States Of America As Represented By The United States Energy Research And Development Administration | Nuclear reactor remote disconnect control rod coupling indicator |
US4655994A (en) * | 1983-12-30 | 1987-04-07 | Westinghouse Electric Corp. | Method for determining the operability of a source range detector |
CA1266707A (en) * | 1985-12-16 | 1990-03-13 | Steve S. Yang | Method of calibrating and equalizing a multi-channel automatic gain control amplifier |
FR2649240B1 (fr) * | 1989-06-29 | 1991-09-13 | Framatome Sa | Procede de determination de la repartition de la puissance dans le coeur d'un reacteur nucleaire et procede de calibrage des detecteurs neutroniques autour du coeur d'un reacteur nucleaire |
JPH06194452A (ja) | 1992-12-24 | 1994-07-15 | Hitachi Ltd | 中性子束監視システム |
JP3579024B2 (ja) | 2001-12-11 | 2004-10-20 | 株式会社グローバル・ニュークリア・フュエル・ジャパン | 原子炉出力監視装置 |
US7079436B2 (en) * | 2003-09-30 | 2006-07-18 | Hewlett-Packard Development Company, L.P. | Resistive cross point memory |
JP4679862B2 (ja) * | 2004-09-16 | 2011-05-11 | 三菱電機株式会社 | 放射線モニタ |
US20070105516A1 (en) * | 2005-11-10 | 2007-05-10 | Hickman Barton T | Automatic compensation of gain versus temperature |
JP4795014B2 (ja) | 2005-12-15 | 2011-10-19 | 株式会社グローバル・ニュークリア・フュエル・ジャパン | 原子炉出力監視装置 |
JP4881033B2 (ja) | 2006-02-21 | 2012-02-22 | 株式会社東芝 | 中性子検出器の寿命判定装置およびその寿命判定方法ならびに原子炉炉心監視装置 |
TWI336164B (en) * | 2007-01-03 | 2011-01-11 | Realtek Semiconductor Corp | Dc offset calibration apparatus and method for differential signal |
JP2010164338A (ja) * | 2009-01-13 | 2010-07-29 | Toshiba Corp | 移動式炉心内計装装置の検出感度校正システム及び方法 |
US20100283773A1 (en) * | 2009-05-08 | 2010-11-11 | Yong-Hun Kim | Driving integrated circuit and image display device including the same |
JP4883151B2 (ja) * | 2009-08-05 | 2012-02-22 | 株式会社デンソー | 回転機の制御装置 |
TWI402652B (zh) * | 2010-07-07 | 2013-07-21 | Richtek Technology Corp | 校正一次側回授馳返式電源模組的輸出電壓的裝置及方法 |
JP5535100B2 (ja) * | 2011-02-03 | 2014-07-02 | 三菱電機株式会社 | 炉外核計装装置 |
KR101272367B1 (ko) * | 2011-11-25 | 2013-06-07 | 박재열 | 전달 함수를 이용한 영상표시장치의 보정 시스템 및 그의 보정 방법 |
JP5787799B2 (ja) * | 2012-03-13 | 2015-09-30 | 三菱電機株式会社 | 炉外核計装装置 |
US9157963B2 (en) * | 2012-08-10 | 2015-10-13 | O2Micro Inc. | Method and system for calibrating battery pack voltage based on common-mode calibration parameter and differential-mode calibration parameter |
JP6124663B2 (ja) * | 2013-04-19 | 2017-05-10 | 三菱電機株式会社 | 線量率測定装置 |
CN103927968B (zh) * | 2013-06-18 | 2016-12-28 | 上海天马微电子有限公司 | 一种oled显示装置 |
JP2015079187A (ja) * | 2013-10-18 | 2015-04-23 | シナプティクス・ディスプレイ・デバイス株式会社 | 表示装置および表示ドライバ |
US20170047132A1 (en) * | 2014-08-29 | 2017-02-16 | Mitsubishi Electric Corporation | Ex-core nuclear instrumentation device |
CN107251155B (zh) * | 2015-03-05 | 2019-04-23 | 三菱电机株式会社 | 堆外核检测仪表装置 |
TWI580984B (zh) * | 2015-10-27 | 2017-05-01 | 力晶科技股份有限公司 | 電壓校正電路及電壓校正系統 |
-
2015
- 2015-09-08 CN CN201580082706.XA patent/CN107924726B/zh active Active
- 2015-09-08 US US15/736,040 patent/US11081244B2/en active Active
- 2015-09-08 JP JP2017538500A patent/JP6425824B2/ja active Active
- 2015-09-08 TR TR2017/22213T patent/TR201722213T1/tr unknown
- 2015-09-08 WO PCT/JP2015/075402 patent/WO2017042876A1/ja active Application Filing
Patent Citations (8)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS6256898A (ja) * | 1985-09-06 | 1987-03-12 | 株式会社日立製作所 | 中性子束較正装置 |
JPH07294688A (ja) * | 1994-04-21 | 1995-11-10 | Toshiba Corp | 原子炉出力監視装置 |
JPH1026668A (ja) * | 1996-07-10 | 1998-01-27 | Hitachi Ltd | 校正装置および中性子束測定装置 |
JP2000009877A (ja) * | 1998-06-24 | 2000-01-14 | Toshiba Corp | 原子炉出力監視装置 |
JP2000266884A (ja) * | 1999-03-16 | 2000-09-29 | Mitsubishi Electric Corp | 核計測装置 |
JP2002116283A (ja) * | 2000-10-05 | 2002-04-19 | Toshiba Corp | 原子炉のディジタル式出力領域モニタシステム |
JP2007040718A (ja) * | 2005-07-29 | 2007-02-15 | Toshiba Corp | 制御棒引抜監視装置 |
JP2013120057A (ja) * | 2011-12-06 | 2013-06-17 | Mitsubishi Electric Corp | 炉内核計装装置 |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN113436766A (zh) * | 2021-06-07 | 2021-09-24 | 中国核动力研究设计院 | 一种用于核电厂的堆外核仪表系统设备 |
CN113436766B (zh) * | 2021-06-07 | 2023-05-26 | 中国核动力研究设计院 | 一种用于核电厂的堆外核仪表系统设备 |
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