• 专利附录
  • 专利说明
  • 权利要求
  • 类似技术
  • 同族专利
  • 引用文献
  • 法律状态
  • 优先权
    • 专利摘要:
    According to one embodiment, a neutron measuring device comprises a neutron detector (1); a preamplifier (2); a first AC amplifier (3) that extracts and amplifies an AC component; a bandwidth limiter (4) which obtains a signal from a range of a predetermined frequency domain based on the output of the first AC amplifier (3); a neutron signal gap calculating unit (11) which derives a neutron signal gap, which is a period during which a significant signal is generated from the AC component of the neutron detection signal; and a mean squared value calculation unit (6) which calculates an average quadratic output value of the bandwidth limiter (4) for a range corresponding to the neutron signal interval.
    公开号:FR3030780A1
    申请号:FR1562072
    申请日:2015-12-09
    公开日:2016-06-24
    发明作者:Daijiro Ito；Norihiro Umemura；Shigehiro Kono；Tsuyoshi Kumagai；Makoto Tomitaka
    申请人:Toshiba Corp；
    IPC主号:
    专利说明:

    [0001] NEUTRON MEASUREMENT APPARATUS AND NEUTRON MEASUREMENT METHOD The present embodiments relate to a neutron measuring device and a neutron measuring method. In the background, in many cases, neutrons produced in a nuclear reactor or experimental nuclear fusion device are less likely to be affected by radiation or circuit noise in the environment. Thus, these neutrons are measured by a fission counter tube. The fission counter tube produces a pulse signal whenever a neutron is detected. When the neutron flux is low, a pulse counting method, by which each of the pulse signals produced from the fission counter tube is counted, is used to measure the neutrons. When neutron flux is relatively high, pulse signals are frequently generated due to neutron detection. In such a case, the pulse signals are superimposed on one another (or stacked), making it impossible to count each pulse signal. Under such circumstances, it is known that Campbell's method, which uses statistical fluctuations of the superimposed pulse signals delivered from a detector to have a proportional relationship with the neutron flux, is used to measure neutrons. Recently, a method of neutron measurement using digital signal processing technology has been used in practice by digitizing the signals (detector output signals) that are output from the detector. The drawings will be briefly described below. FIG. 1 is a block diagram showing the general configuration of a neutron measuring device according to a first embodiment. Fig. 2 is a block diagram showing the general configuration of a neutron measuring device according to a variant of the first embodiment. Fig. 3 is an algorithm showing the procedure of a neutron measurement method according to the first embodiment. Fig. 4 is a graph showing an output waveform of each unit of the neutron measuring device according to the first embodiment. Fig. 5 is a block diagram showing the general configuration of a neutron measuring device according to a second embodiment. Fig. 6 is a block diagram showing the general configuration of a neutron measuring device according to a third embodiment. Fig. 7 is a graph for explaining how the delay occurs due to processing by the wave height discriminator. Fig. 8 is a block diagram showing the configuration of a conventional neutron measuring device. A detailed description will then be given below. During the neutron measurement using the Campbell method, in order to calculate statistical fluctuations of the detector output signals, the mean square value of the alternative components of the detector output signals is calculated. In general, the detector output signals are superimposed not only on neutron signals but also on environmental components derived from radiation or circuit noise, which are different from those of neutrons. If the alternating component of the neutron signal voltage is represented by Vn (t), the AC component of the environment component 30 by Vo (t), and the AC voltage component of the set of signals superimposed by Vs. (t) as a function of time t, and if the measurement instant is 0 and the measurement duration T, the mean squared value is expressed by the following equation (1): -1 ST V s2 (t) dt = -1 ST (V (t) +1/0 (t)) 2 dt TT n = -1 ST V 2 (t) dt + -2 f TV (t) V (t) dt + -1 ST V O2 (t) t) T n T n T - - - (1) On the right side of equation (1), there is no correlation between Vn (t) and Vo (t). Therefore, the internal product of function is equal to 0. Therefore, the following equation (2) can be established: f 0 Vn (t) - V (t) dt = 0 - - (2) Consequently, the second term on the right side of equation (1) is equal to 0, and the following equation (3) is therefore established. Equation (3) shows that the sum of the mean squared voltage of the neutron-associated signals and the mean squared voltage of the signals associated with environmental radiation and circuit noise is equal to the mean squared voltage of the ensemble. signals. -1 Jr vs2 (t) dt = -1 f yn2 (t) dt + ST V ,, (t) dt (3) TTT ° From equation (3), it is obvious that the mean squared value of the environmental component on the right side of equation (3) is a difference between the mean squared value of a measured value and the mean squared value of a true value. When the neutron flux is relatively high, the mean square voltage of the signals associated with the neutrons is sufficiently greater than the difference between the measured and actual values. Consequently, the difference can be neglected and the relationship of proportionality between the statistical fluctuations and the neutron flux is preserved. When the neutron flux is relatively small, the difference between the measured and actual values is slightly greater than the mean square voltage of the neutron associated signals. As a result, statistical fluctuations and neutron flux no longer respect the relationship of proportionality. In this case, it is difficult to measure the neutron flux. Fig. 8 is a block diagram showing the configuration of a conventional neutron measuring device. As shown in FIG. 8, a signal processing circuit which processes a detector output signal (analog signal), a preamplifier 2, a first AC (AC) amplifier 3, a bandwidth limiter 4, and a RMS calculator 6 are arranged to measure neutrons. At this stage, conventional noise measurements, such as inserting a ferrite core on a signal line, are taken to reduce the environmental component. However, in the conventional neutron measuring device, the effect of the environmental component reduction obtained by the conventional anti-noise measurements is limited. Therefore, the influence of the environmental component can not be sufficiently eliminated and it is difficult to accurately measure the neutron flux when the neutron flux is relatively low. The objective of the embodiments of the present invention is to measure the neutron flux even when the neutron flux level is relatively low by suppressing the influence of the environment component.
    [0002] According to one embodiment, there is created a neutron measuring device comprising: a neutron detector for producing an output signal corresponding to an incoming neutron; a preamplifier for amplifying the output signal of the neutron detector and for outputting a neutron detection signal; a first AC amplifier for extracting and amplifying an AC component from the output of the preamplifier; a bandwidth limiter for obtaining a signal of a range of a predetermined frequency domain based on the output of the first AC amplifier; a neutron signal interval calculating unit for deriving a neutron signal gap, which is a period of time during which a large signal is generated, from the AC component of the neutron detection signal; and a mean squared value calculation unit for calculating an average quadratic value of the bandwidth limiter outputs for a range corresponding to the neutron signal interval. Preferably, the neutron signal gap calculating unit comprises: a second AC amplifier for extracting and amplifying an AC component from the output of the preamplifier; a wavelength discriminator for classifying wavelengths in the predetermined ranges on the basis of an output of the second AC amplifier; and a pulse length converter for deriving the neutron signal interval based on an output of the wave height discriminator and outputting a pulse signal corresponding to the neutron signal interval. Preferably, the neutron measuring device further comprises a subtraction element for subtracting from a value calculated by the mean squared value calculating unit by integrating mean squared values over all periods of time. periods of time based on signals filtered by the bandwidth limiter, a value that the RMS calculation unit has calculated in a section in which any signal filtered by the bandwidth limiter is not produced by integration of mean square values based on the signals filtered by the bandwidth limiter.
    [0003] Preferably, the neutron measuring device further comprises a delay unit which corrects start time differences between calculation processes in the neutron signal interval calculating unit and the units leading to the limiter. bandwidth. In another embodiment, a neutron measurement method is provided comprising: a pulse length converting step of: extracting, in a second AC amplifier, an AC component based on a signal amplified by a preamplifier; implement wave height discrimination; and deriving a neutron signal gap based on a result of the wave height discrimination; an extraction step of: amplifying, in a preamplifier, an output signal of a neutron detector; extracting and amplifying, in a first AC amplifier, an AC component; and then obtaining an AC component of a range of a predetermined fi-equequential domain using a bandwidth limiter; and a mean squared value calculation step for calculating a mean squared value of the AC components, by a mean squared value calculation unit, for a range corresponding to a time section that is derived as a signal range of neutron. Preferably, the neutron signal interval is calculated as a duration of a signal filtered by the bandwidth limiter from the production of an input of the wavelength discrimination. Preferably, at the mean squared value calculation step, the mean squared value is calculated by integrating, on the neutron signal gap, signals filtered by the bandwidth limiter. Preferably, at the mean squared value calculation step, the mean squared value is computed by subtraction from a computed value by integrating signals filtered by the bandwidth limiter over all periods of time. a value calculated in a section in which any signal filtered by the bandwidth limiter is not generated by integrating signals filtered by the bandwidth limiter. Hereinafter, with reference to the accompanying drawings, embodiments of a neutron measuring device and a neutron measuring method of the present invention will be described. The same parts or similar parts are represented by the same reference numerals and a duplicate description will be omitted. A first embodiment will now be described. Fig. 1 is a block diagram showing the general configuration of a neutron measuring device according to a first embodiment. A neutron measuring device 100 of the present embodiment is designed to measure the neutron intensity of a reactor core in a range that is less than a range (power range) in which an output power. of a nuclear reactor is close to a nominal power, or in what is called a starting range in which the level of a neutron flux is relatively low. The neutron measuring device 100 comprises a neutron detector 1, a preamplifier 2, a Campbell measurement circuit 10, and a neutron signal interval calculating unit 11. The neutron detector 1 is a detector which detects neutrons. The neutron detector 1 delivers a pulse-shaped electrical signal (hereinafter referred to as a neutron pulse) when a neutron is introduced. The preamplifier 2 amplifies signals from the neutron detector 1 to transmit the output of the neutron detector 1 to a control panel or the like, which is not shown in the diagram.
    [0004] The Campbell 10 measurement circuit includes a first AC amplifier 3, a bandwidth limiter 4, an analog digital (A / D) converter 5, and a mean square value (MSV) calculation unit (MSV value calculator). 6. The Campbell 10 measurement circuit is a circuit that measures, based on Campbell's method, the level of a neutron flux.
    [0005] The first AC amplifier 3 receives, as input, a signal from the preamplifier 2, extracts an AC component and amplifies it. The bandwidth limiter 4 receives, as input, an output of the first amplifier CA 3, and filters the waves only in an alternating current of a predetermined frequency band while allowing the attenuation of an alternating current in other frequency ranges. The A / D converter 5 delivers, when a bandwidth limiter output signal 4 is input, a value obtained by converting the input signal into a digital value, according to certain intervals. The MSV value calculator 6 is designed to obtain a root mean square value. The value calculator MSV 6 receives, as input, an output signal of the A / D converter 5 and an output signal of a pulse length converter 9, which will be described later, and delivers a value mean quadratic. In this case, the mean squared value is a sliding average over a predetermined time. Fig. 2 is a block diagram showing the general configuration of a neutron measuring device according to a variant of the first embodiment. In the variant, the A / D converter 5 is followed by the bandwidth limiter 4. That is to say that, in a Campbell 10a measurement circuit, an output of the first amplifier CA 3 passes through an analog conversion -Numeric in the A / D converter 5 before entering the bandwidth limiter 4. In this variant, the bandwidth limiter 4 can use a digital filter. Therefore, it is possible to sufficiently block the passage of waves other than those of a frequency range that is supposed to pass. Then, the operation of the first embodiment will be described. The neutron signal gap calculating unit 11 shown in FIG. 1 comprises a second AC amplifier 7, a wave height discriminator 8, and a pulse length converter 9. The second AC amplifier 7 receives, as input, a signal from the preamplifier 2, extracts an AC component, and amplifies it. The wave height discriminator 8 is designed to detect the production of a neutron pulse. The wavelength discriminator 8 receives, as input, an output signal of the second amplifier CA 7, compares the wavelength of the input signal with a wavelength that has been determined in advance. on the basis of a neutron pulse, and delivers a logic pulse signal. For example, when the wavelength of the input signal is greater than the predetermined wavelength, the logic pulse signal is in the ACTIVE state. When the wavelength of the input signal is less than the predetermined wavelength, the logic pulse signal is in the OFF state. The pulse length converter 9 is designed to adjust the length of the logic pulse. When an output signal (logic pulse) of the wave height discriminator 8 is inputted, the pulse length converter 9 outputs a logic pulse which remains active for a certain duration. In this case, as will be described later, the neutron signal interval does not refer to a period of time only during noise generation, but to a period of time during which significant signals are received by the receiver. Neutron detector 1. That is, the neutron signal interval may also be a period of time during which the MSV calculator 6 is to calculate the RMS value of signals. Fig. 3 is an algorithm showing the procedure of a neutron measurement method according to the first embodiment. Fig. 4 is a graph showing an output waveform of each unit of the neutron measuring device according to the first embodiment. The horizontal axis represents time. The vertical axis on the upper curve represents the output of the second AC amplifier 7. The vertical axis on the second curve from the top represents the output n) of the wave height discriminator 8. The vertical axis on the third curve from the top represents the output of the pulse length converter 9. The vertical axis on the fourth curve from the top represents the output of the bandwidth limiter 4. The operation of the present embodiment will be described in FIG. Referring to Figs. 3 and 4. First, based on the signal amplified by the preamplifier 2, the second AC amplifier 7 extracts the AC component. The wave height discriminator 8 implements a wavelength discrimination by comparing the AC component with a predetermined specified value. The pulse length converter 9 implements a pulse length conversion on a result of the wave height discrimination (step S01). A weak neutron pulse that is produced by the neutron detector 1 is amplified by the preamplifier 2. An output signal that is produced by superimposed neutron pulses from the preamplifier 2 contains an unstable continuous component. The unstable DC component can be a factor of unnecessary power generation across the circuit. The second AC amplifier 7 eliminates the unnecessary DC component from the input signal and extracts only the AC component. The profile of the neutron pulse that emerges after the AC component has been extracted is shown in the section "AC amplifier output signal" in FIG. 4. FIG. 4 shows a case in which a pulse of - The neutron A1 is produced at time Ti, and another neutron pulse A2 is produced at time T4. In this case, a frequency component contained in the neutron pulses is represented by fn. In parallel with step S01, on the Campbell 10 measurement circuit, an output of the preamplifier 2 is received and an AC component is extracted and amplified by the first amplifier CA 3, and a signal of a range of a domain predetermined frequency is obtained by the bandwidth limiter 4 (step S02). Fig. 4 shows the case in which the frequency band which is allowed to pass after filtering of the bandwidth limiter 4 has been set for a band which is less than fn. That is, the time interval AT during which the neutron pulse that passes through the bandwidth limiter 4 continues is greater than the time interval during which the pulse of neutron which is the output signal of the second amplifier CA 7 continues.
    [0006] The time interval AT is a constant value given that the time interval AT is determined on the basis of the frequency characteristics of the bandwidth limiter 4. The neutron signal interval calculating unit 11 is used to detect a time interval during which the neutron pulse is produced on the bandwidth limiter output signal 4.
    [0007] The wavelength discriminator 8 of the neutron signal gap calculating unit 11 outputs a logic pulse as shown in the section "Wave height discriminator output signal" in FIG. 4, at a time when the output signal of the second AC amplifier 7 has reached a predetermined threshold value due to the generation of the neutron pulse. Therefore, the generation of the logic pulse indicates the instant at which the neutron pulse is produced. When the logic pulse is input to the pulse length converter 9, the logic signal output of the pulse length converter 9 is inverted from the low to high level. The logic signal that has been inverted at the high level returns to the original logic signal after an AT time has elapsed. As a result, the logic state (up / down) of the output signal of the pulse length converter 9 represents whether or not the neutron pulse is produced on the bandwidth limiter output signal 4, such as this is shown in FIG. 4. The time interval AT is determined on the basis of the frequency characteristics of the bandwidth limiter 4. It is possible to calculate the time interval AT beforehand, in order to define the required duration to ensure the low return of the logic signal after it has been inverted at the high level, such as AT on the pulse length converter 9. Then, only for a time domain obtained by the conversion of pulse length, the root mean square value of the signals of a range of a predetermined frequency domain is calculated (step S03). The MSV value calculator 6 of Campbell's measurement circuit 10 uses only the numerical value Vs [t], which is obtained during a period during which the neutron pulse is produced, i.e. a period during which the logic state of the output signal of the pulse length converter 9 is high, and for calculating the mean square value MSVO of measurement time signals T with the following equation (4): MSVO = The calculated mean squared value MSVO is converted to neutron flux after being multiplied by a conversion coefficient and is then outputted. According to the present embodiment described above, only a signal value (e.g., a voltage value) that is measured during a period of time during which the neutron pulse is produced is used for the calculation of mean square value. Therefore, even if the neutron flux is small, the effects of the voltage value measured during a period during which there is no neutron pulse can be eliminated. As a result, it is possible to measure a value closer to a real value. In conventional neutron measurement devices that simultaneously use both the pulse counting method and the Campbell method to maintain an extended measurement range, such as a start range control device. of a nuclear reactor, an additional circuit must be installed in order to use both processes simultaneously. At the same time, the application of the present embodiment makes it possible to measure only with the Campbell method and the pulse counting method is not required. Therefore, it is not necessary to mount a circuit for the pulse counting method and a circuit for simultaneously using both methods. Thus, the mounting possibility can be improved.
    [0008] When the pulse counting method and Campbell's method are used simultaneously, an integrated circuit, such as an FPGA (Field Programmable Gate System), is frequently used as a means to realize the MSV value calculator 6. All circuits which must be added in order to implement the present invention may be mounted on such an integrated circuit. Therefore, without increasing the size of the printed circuit, the present embodiment can be applied to extend the measurement range of the Campbell method. A second embodiment will next be described. Fig. 5 is a block diagram showing the general configuration of a neutron measuring device according to a second embodiment. The present embodiment is a variant of the first embodiment. According to the second embodiment, a Campbell 10b measurement circuit comprises a first MSV value calculator 6a, a second MSV value calculator 6b, and a subtraction element 12.
    [0009] The first MSV value calculator 6a is designed to calculate a mean square value of signals. Regardless of whether a neutron pulse is produced or not, all the numerical values that are obtained during the measurement period T are used to calculate the mean square value MSV1, which is then delivered.
    [0010] The second MSV value calculator 6b is for calculating a mean square value of signals. The second MSV value calculator 6b receives, as inputs, an output signal of the A / D converter 5 and a pulse length converter output signal 9, and then delivers a mean square value. The second MSV value calculator 6b uses a digital value which is an output signal of the A / D converter 5 during a period of time during which no neutron pulse is produced or when the logic state of the output signal of the Impulse length converter 9 is low, for the purpose of calculating and delivering a mean squared value MSV2. The subtraction element 12 is designed to calculate a difference between the mean squared values. After the mean square value MSV1 which is output from the first MSV calculator 6a and a mean squared value MSV2 which is output from the second MSV calculator 6b has been outputted, the subtraction element 12 calculates and delivers the difference between the mean squared values (MSV1-MSV2). According to the present embodiment, the mean squared value MSV2 of signals for a period during which no neutron signal is produced is deduced from the mean squared value MSV1 of signals for all time periods. Therefore, even if the neutron flux is small, the effects of the voltage value measured during a period during which there is no neutron pulse can be eliminated. As a result, it is possible to measure a value closer to a true value. A third embodiment will now be described. Fig. 6 is a block diagram showing the general configuration of a neutron measuring device according to a third embodiment. The present embodiment is a variation of the first embodiment. A Campbell measurement circuit 10c of the present embodiment has a delay unit 13. A neutron signal gap calculating unit 1a has a sequence corrector 14. In addition to these units, a measurement device of Neutron 100 comprises a counter 15, a neutron rate calculator 16, a dead time corrector 17, and an external control unit 18. The delay unit 13 of the Campbell measurement circuit 10c is designed to to delay signals for a certain time. When a bandwidth limiter output signal 4 is input, the delay unit 13 outputs the bandwidth limiter output signal 4 after a certain time. That is, the delay unit 13 compensates for a delay in processing by the neutron signal gap calculating unit 1a relative to the processing by the Campbell 10e measuring circuit. For example, the delay on processing can be attributed to the processing by the wave height discriminator 8 of the neutron signal gap calculating unit 11a. Fig. 7 is a graph for explaining how the delay occurs due to processing by the wave height discriminator. As shown in Fig. 7, the output signal of the second AC amplifier 7 begins to rise at time Ti. In this case, in the neutron signal gap calculating unit 11a, the wave height discriminator 8 is set to the ON state at time T 1a when the output signal of the second AC amplifier 7 exceeds a predetermined threshold value. As a result, the logic signal of the pulse length converter 9 is also set to the ACTIVE state at time T1a. Meanwhile, in the Campbell measurement circuit 10e, at the same time, Ti, when the output signal of the first amplifier CA 3 rises, an output signal is produced from the bandwidth limiter 4. In this way, while the pulse signal is delivered at time T1, the neutron signal interval calculating unit 11 has started to produce at time T1a. Thus, a delay of (T1-T1) is produced. In order to correct a time shift, including this delay, the delay unit 13 is arranged on the Campbell 10e measurement circuit. Counter 15 is designed to count the neutron pulses. When the logic pulse that is delivered from the wavelength discriminator 8 is input, the counter 15 adds one to a cumulative value, and outputs the incremented accumulated value. The neutron flow calculator 16 is designed to calculate a neutron flow. When the accumulated value that is delivered from the counter 15 is input, the neutron flow calculator 16 delivers the neutron flow. The dead time corrector 17 is designed to correct an error on the neutron flow. When the neutron flow that is delivered from the neutron flow computer 16 is inputted, the dead time corrector 17 delivers the corrected neutron flow. The counter 15, the neutron flow calculator 16 and the dead time corrector 17 provide a function of obtaining the neutron flow rate using the pulse counting method and performing a dead time correction method. Counter 15 counts the number of neutron pulses; the neutron flow calculator 16 calculates the neutron flow rate by dividing the number by the counting time of the counted value. However, no correction is made on the neutron flow rate obtained such as for a period during which the sensitivity of the counter is lost. Therefore, the dead time counter 17 performs a correction. The dead time correction is expressed by the following equation (5) if the neutron rate after correction is represented by Rc, the neutron rate before correction by R, and the dead time by r. R c = N I (T - N - 1) = R 1 (1 - R - z -) - - - (5) wherein N represents a value counted over a duration T; R = N / T. The external adjustment unit 18 allows the adjustment of the length of the logic pulse delivered from the pulse length converter 9 and the delay time during which each signal is delayed by the delay unit 13 since the delay. 'outside. When setting the values of the logic pulse, the length and the delay time are input from the outside, the external adjustment unit 18 delivers each of the adjustment values to the delay unit 13 and the length converter. 9. When the setting values are input to the external adjustment unit 18, the delay time during which the signal is delayed by the delay unit 13 and the length of the logic pulse delivered from of the pulse length converter 9 are modified for the setting values. The sequence corrector 14 of the neutron signal gap calculating unit 11a uses a sequence correction method, such as a zero offset method or a constant coefficient method, to correct the gap. detection time of the neutron pulse. According to the present embodiment described above, the dead time correction method has been applied. Therefore, by using both the Campbell method and the pulse counting method, an area in which each of the two measuring ranges overlap each other may be larger than before. However, the sequence corrector 14 and the delay unit 13 can eliminate the deviation on pulse generation time detection, which is caused by fluctuations in the pitch of the pulse waves.
    [0011] In addition, the external adjustment unit 18 allows fine adjustment of the adjustment values at the time of calibration or adjustment of the device. Other embodiments are possible. While several embodiments of the present invention have been described, these embodiments have been presented by way of example and are not intended to limit the scope of the invention. For example, what has been described in the embodiments is the case in which the neutron flux level is measured in the start range. However, the application is not limited thereto as long as the principles of the invention are used. In addition, features of the invention may be used in an associated manner.
    [0012] Embodiments may be implemented in other varied forms. Various omissions, replacements and changes can be made without departing from the main subject of the invention. The previous embodiments and their variants are within the scope and main subject of the invention, and are similarly within the scope of the invention defined in the description and its equivalence range.
    权利要求:
    Claims (8)
    [0001]
    REVENDICATIONS1. A neutron measuring device (100) comprising: a neutron detector (1) for producing an output signal corresponding to an incoming neutron; a preamplifier (2) for amplifying the output signal of the neutron detector (1) and outputting a neutron detection signal; a first AC amplifier (3) for extracting and amplifying an AC component from the output of the preamplifier (2); a bandwidth limiter (4) for obtaining a signal of a range of a predetermined frequency domain based on the output of the first AC amplifier (3); a neutron signal interval calculating unit (11) for deriving a neutron signal gap, which is a period of time during which a large signal is generated, from the AC component of the signal of neutron detection; and a mean squared value calculating unit (6) for calculating an average quadratic output value of the bandwidth limiter (4) for a range corresponding to the neutron signal interval.
    [0002]
    The neutron measuring device (100) according to claim 1, wherein the neutron signal gap calculating unit (11) comprises: a second AC amplifier (7) for extracting and amplifying a component alternative of the output of the preamplifier (2); a wavelength discriminator (8) for classifying wavelengths in the predetermined ranges on the basis of an output of the second AC amplifier (7); and a pulse length converter for deriving the neutron signal interval based on an output of the wave height discriminator (8) and outputting a pulse signal corresponding to the signal range of - 18 - neutron.
    [0003]
    The neutron measuring device (100) according to claim 1 or 2, further comprising a subtraction element (12) for subtracting from a value calculated by the mean squared value calculation unit ( 6) by integrating mean square values over all time periods on the basis of signals filtered by the bandwidth limiter (4), a value that the mean squared value calculation unit (6) has calculated in a section in which any signal filtered by the bandwidth limiter (4) is not produced by integrating mean square values on the basis of the signals filtered by the bandwidth limiter (4).
    [0004]
    The neutron measuring device (100) according to any one of claims 1 to 3, further comprising a delay unit (13) which corrects start time differences between computational processes in the control unit. Neutron signal interval calculation (11a) and the units leading to the bandwidth limiter (4).
    [0005]
    A method of neutron measurement comprising: a step of converting pulse length comprising: extracting, in a second AC amplifier (7), an AC component based on a signal amplified by a preamplifier (2); implement wave height discrimination; and deriving a neutron signal gap based on a result of the wave height discrimination; an extraction step of: amplifying, in a preamplifier (2), an output signal of a neutron detector (1); extracting and amplifying, in a first AC amplifier (3), an AC component; and then obtaining an AC component of a range of a predetermined frequency domain using a bandwidth limiter (4); and a mean squared value calculating step for calculating an average squared value of the AC components, by a mean squared value calculating unit (6), for a range corresponding to a time section that is derived as an interval. of neutron signal.- 19 -
    [0006]
    The method of measuring the neutron according to claim 5, wherein the neutron signal interval is calculated as a duration of a signal filtered by the bandwidth limiter (4) from the production of a signal input. wave height discrimination.
    [0007]
    The method of measuring the neutron according to claim 5 or 6, wherein at the mean square value calculation step, the mean squared value is calculated by integrating, on the neutron signal gap, signals filtered by the bandwidth limiter (4).
    [0008]
    A neutron measuring method according to claim 5 or 6, wherein at the mean square value calculation step, the mean squared value is computed by subtraction from a value calculated by integrating signals filtered by the bandwidth limiter (4) during all the periods, a value calculated in a section in which any signal filtered by the bandwidth limiter (4) is not generated by integration of signals filtered by the limiter of bandwidth (4).
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    优先权:
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    JP2014255178|2014-12-17|
    JP2014255178A|JP6441062B2|2014-12-17|2014-12-17|Neutron measuring apparatus and neutron measuring method|
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