JP2018151213A - Control device, measuring system, and program - Google Patents

Abstract

PROBLEM TO BE SOLVED: To provide a control device capable of preventing a time until a count of radiations radiated by a detection object nuclide reaches a target count from becoming longer.SOLUTION: A control device includes: an uncertainty calculation unit for calculating uncertainty of a count of radiations radiated by a detection object nuclide by using a spectrum of radiations calculated by a wave height analyzer on the basis of a signal indicating radiations detected by a detection unit; a determination unit for determining whether the count calculated by the uncertainty calculation unit is equal to or less than a target uncertainty; and a measuring control unit for terminating calculation of the spectrum by the wave height analyzer on the basis of a determination result of the determination unit.SELECTED DRAWING: Figure 1

Description

  The present invention relates to a control device, a measurement system, and a program.

  Research and development of a technique relating to calculation of a count in which radiation detected from a specific nuclide desired by a user among radiation emitted from a sample is detected by a detector has been performed.

  In this regard, for example, as shown in Patent Document 1, the radiation emitted from the sample is detected by a radiation detector, the energy spectrum of the radiation detected by the radiation detector is automatically analyzed, and the analyzed energy spectrum is converted into the analyzed energy spectrum. There is known a radioactivity measuring apparatus that calculates radioactivity of a detection target nuclide based on the radioactivity.

Japanese Patent Laying-Open No. 2015-99067

  Here, such a conventional radioactivity measuring apparatus detects the radiation emitted from the sample by the radiation detector within the measurement time calculated by the preliminary measurement. The measurement time depends on the uncertainty of the count (ie statistical variation of the count) in which the radiation detector detects the radiation emitted from the target nuclide out of the radiation emitted from the sample, depending on the predetermined application. This is the time estimated to be less than the target uncertainty determined. For this reason, when the measurement time elapses, the radioactivity measurement apparatus ends detection of radiation emitted from the sample by the radiation detector. However, since the uncertainty of the count of radiation emitted from the target nuclide detected by the radiation detector within the measurement time changes due to the influence of statistical fluctuations each time the radiation is detected, the target uncertainty May not be reached. In such a case, the radioactivity measurement apparatus must re-detect the radiation emitted from the sample by the radiation detector, and as a result, it takes until the count uncertainty reaches the target uncertainty. Sometimes it took a long time.

  Therefore, the present invention has been made in view of the above-described problems of the prior art, and suppresses an increase in the time until the uncertainty in counting the radiation emitted from the detection target nuclide reaches the target uncertainty. A control device, a measurement system, and a program are provided.

In order to solve the above problems and achieve the object, the present invention employs the following aspects.
(1) The control device according to one aspect of the present invention uses the spectrum of the radiation calculated by the wave height analyzer based on the signal indicating the radiation detected by the detection unit, and the radiation emitted from the detection target nuclide. An uncertainty calculation unit that calculates the uncertainty of counting, a determination unit that determines whether the uncertainty calculated by the uncertainty calculation unit is equal to or less than a target uncertainty, and a determination result of the determination unit And a measurement control unit that terminates the calculation of the spectrum by the wave height analyzer.

(2) In the control device according to (1), the uncertainty calculation unit calculates the uncertainty at a plurality of timings within a measurement period, and the measurement control unit has the uncertainty equal to or less than the target uncertainty. When the determination unit determines that the predetermined number of times continuously, the calculation of the spectrum by the wave height analyzer is terminated.

(3) In the control device according to (1) or (2), the measurement control unit further includes a measurement time based on a time estimated from the start time of the measurement period that the uncertainty is equal to or less than the target uncertainty. When elapses, calculation of the spectrum by the wave height analyzer is terminated.

(4) In the control device according to (3), the measurement control unit terminates the calculation of the spectrum by the wave height analyzer when the measurement time elapses from the start time, and the uncertainty. When the determination unit determines that the frequency is greater than the target uncertainty, the calculation of the spectrum by the wave height analyzer is resumed.

(5) In the control device according to the above (3) or (4), the measurement time is longer than the time.

(6) In the control device according to any one of (1) to (5), the uncertainty calculation unit receives a plurality of different detection target nuclides in advance and receives the plurality of detection targets received The uncertainties for each radiation emitted from each of the nuclides are calculated, and the determination unit determines, for each of the plurality of detection target nuclides, the uncertainty in counting the radiation radiated from the detection target nuclides. Whether or not the target uncertainty is less than or equal to the target uncertainty, the measurement control unit, for all the radiation of each of the plurality of detection target nuclides, uncertainty of the count of the radiation emitted from the detection target nuclides However, when the determination unit determines that the target uncertainty corresponding to the radiation is equal to or less than the target uncertainty, the calculation of the spectrum by the wave height analyzer is terminated.

(7) The measurement system which concerns on 1 aspect of this invention is provided with the control apparatus which concerns on any one among said (1) to (6), and the said detection part.

(8) The measurement system which concerns on 1 aspect of this invention is provided with the control apparatus which concerns on any one among said (1) to (6), the said detection part, and the said wave height analyzer.

(9) In the measurement system according to one aspect of the present invention, the measurement system according to (7) or (8) further includes a shield that suppresses radiation from entering the detection unit from the outside.

(10) A program according to an aspect of the present invention is emitted from a detection target nuclide using a spectrum of the radiation calculated by a pulse height analyzer based on a signal indicating radiation detected by a detection unit. An uncertainty calculation step for calculating the uncertainty of the counted radiation, a determination step for determining whether or not the uncertainty calculated by the uncertainty calculation step is equal to or less than a target uncertainty, and a determination of the determination step And a measurement control step for terminating the calculation of the spectrum by the wave height analyzer based on the result.

  The control device according to one aspect described in (1) is radiated from the detection target nuclide using the spectrum of the radiation calculated by the pulse height analyzer based on the signal indicating the radiation detected by the detection unit. The uncertainty of the radiation count is calculated, it is determined whether or not the calculated uncertainty is less than or equal to the target uncertainty, and the spectrum calculation by the wave height analyzer is terminated based on the determination result. Thereby, the said control apparatus can suppress that time until the uncertainty of the count of the radiation radiated | emitted from a detection target nuclide reaches | attains target uncertainty becomes long.

  The control device according to one aspect described in the above (2) calculates the uncertainty of counting the radiation emitted from the detection target nuclide at a plurality of timings within the measurement period, and the uncertainty is equal to or less than the target uncertainty. If the predetermined number of times is determined, the spectrum calculation by the wave height analyzer is terminated. Thereby, the said control apparatus can suppress more reliably that the time until the uncertainty of the count of the radiation radiated | emitted from a detection target nuclide reaches | attains a target uncertainty becomes long.

  The control device according to one aspect described in (3) described above is a measurement time based on a time estimated from the start time of the measurement period that the uncertainty in counting the radiation emitted from the detection target nuclide is equal to or less than the target uncertainty. When elapses, the spectrum calculation by the wave height analyzer is terminated. As a result, the control device can end the calculation of the spectrum by the pulse height analyzer even when the uncertainty in counting the radiation radiated from the detection target nuclide does not fall below the target uncertainty for some reason. .

  The control device according to one aspect of the above (4) emits from the detection target nuclide when the calculation of the spectrum by the wave height analyzer is terminated after the measurement time has elapsed from the start time of the measurement period. If it is determined that the radiation count uncertainty is greater than the target uncertainty, the spectrum calculation by the wave height analyzer is resumed. Thereby, the said control apparatus can reduce the effort which is required for the remeasurement of the radiation radiated | emitted from a sample.

  The control device according to one aspect of the above (5) includes a measurement time based on a time estimated from the start time of the measurement period that the uncertainty in counting the radiation emitted from the detection target nuclide is equal to or less than the target uncertainty. And when measurement time longer than the said time passes, calculation of the spectrum by a wave height analyzer is complete | finished. As a result, the control device can end the calculation of the spectrum by the pulse height analyzer even when the uncertainty in counting the radiation radiated from the detection target nuclide does not fall below the target uncertainty for some reason. .

  The control device according to an aspect of the above (6) receives a plurality of detection target nuclides different from each other in advance, calculates a count uncertainty for each radiation emitted from each of the received plurality of detection target nuclides, For each of the multiple detection target nuclides, determine whether or not the uncertainty in counting the radiation emitted from the detection target nuclides is less than or equal to the target uncertainty corresponding to the radiation. When it is determined that the uncertainty in counting the radiation emitted from the detection target nuclide is equal to or less than the target uncertainty corresponding to the radiation, the spectrum calculation by the wave height analyzer is terminated. Thereby, the said control apparatus can suppress that the time until the uncertainty of a radiation count reaches | attains a target uncertainty becomes long about all the radiation radiated | emitted from each of several detection object nuclide.

  The measurement system according to one aspect of the above (7) includes a detection target nuclide using a spectrum of the radiation calculated by the pulse height analyzer based on a signal indicating the radiation detected by the detection unit included in the measurement system. Uncertainty of radiation emitted from the radiation is calculated at multiple timings within the measurement period, and it is determined whether or not the calculated counting uncertainty is less than or equal to the target uncertainty. The calculation of the spectrum by the apparatus is terminated. Thereby, the said measurement system can suppress that time until the uncertainty of the count of the radiation radiated | emitted from a detection target nuclide reaches | attains a target uncertainty becomes long.

  The measurement system according to one aspect of the above (8) uses the spectrum of the radiation calculated by the pulse height analyzer included in the measurement system based on the signal indicating the radiation detected by the detection unit included in the measurement system. The calculation uncertainty of the radiation emitted from the detection target nuclide is calculated at multiple timings within the measurement period, and it is determined whether the calculated count uncertainty is less than or equal to the target uncertainty. Based on the above, the spectrum calculation by the wave height analyzer is terminated. Thereby, the said measurement system can suppress that time until the uncertainty of the count of the radiation radiated | emitted from a detection target nuclide reaches | attains a target uncertainty becomes long.

  The measurement system according to one aspect described in (9) suppresses the incidence of radiation from the outside to the detection unit. Thereby, the said measurement system can make small dispersion | variation in the statistical result by the background of the count of the radiation radiated | emitted from a detection target nuclide.

  The program according to one aspect described in the above (10) is radiated from a detection target nuclide using a spectrum of the radiation calculated by the pulse height analyzer based on a signal indicating the radiation detected by the detection unit. The uncertainty of the counted radiation is calculated, and it is determined whether or not the calculated uncertainty is equal to or less than the target uncertainty, and the calculation of the spectrum by the pulse height analyzer is terminated based on the determination result. Thereby, the program can suppress an increase in the time until the uncertainty in counting the radiation emitted from the detection target nuclide reaches the target uncertainty.

It is a figure showing an example of composition of measuring system 1 concerning this embodiment. It is a figure which shows an example of the operation screen in which the control apparatus 4 receives operation from a user among the screens which the control apparatus 4 displays on the display part 45. FIG. It is a figure which shows an example of a target uncertainty setting screen. It is a figure which shows an example of a measurement condition setting screen. It is a figure which shows an example of the flow of a process which the control apparatus 4 calculates the uncertainty of the said count with the count of the radiation radiated | emitted from a detection target nuclide. It is a figure which shows an example of the table | surface displayed on the display part 45 in step S200. It is a figure which shows an example of the flow of a process in which the control apparatus 4 performs remeasurement of the various radiation radiated | emitted from a sample.

<Embodiment>
Hereinafter, a measurement system 1 according to an embodiment of the present invention will be described with reference to the drawings. FIG. 1 is a diagram illustrating an example of a configuration of a measurement system 1 according to the present embodiment. The measurement system 1 includes a detection unit 2, a wave height analysis device 3, and a control device 4. The measurement system 1 may be configured to include other devices in addition to these. In the measurement system 1, the detection unit 2, the wave height analyzer 3, and a part or all of the controller 4 may be configured integrally. In the present embodiment, the process of converting an analog signal into a digital signal may be performed by some or all of the detection unit 2, the wave height analysis device 3, and the control device 4, or may be performed by a known method. Since it may be performed by the method developed from now on, description is abbreviate | omitted.

<Outline of measurement system>
First, an outline of the measurement system 1 will be described.
The measurement system 1 measures various types of radiation emitted from the sample. Specifically, the measurement system 1 detects the various types of radiation and calculates spectra of the various types of detected radiation. Moreover, the measurement system 1 performs an analysis based on the calculated spectrum. Specifically, the measurement system 1 calculates (measures) the uncertainty of the count together with the count of radiation emitted from the detection target nuclide based on the spectrum. In this example, the uncertainty of the count is a statistical variation of the count. The method for calculating the uncertainty of the count may be a known method or a method to be developed in the future.

  Here, the aforementioned sample is an object including one or more radionuclides. Further, in the present embodiment, various types of radiation emitted from the sample are radiation emitted from each of one or more radionuclides contained in the sample, and the types of radiation (for example, alpha rays, beta rays, It is distinguished by the combination of gamma rays and the energy of radiation. The detection target nuclide is a nuclide that the measurement system 1 receives in advance from the user, and is a nuclide that emits radiation that is a target for which the measurement system 1 calculates a count. The count of the radiation radiated from the detection target nuclide is the number of times that the radiation is detected by the detection unit 2.

  More specifically, the measurement system 1 starts detecting various types of radiation emitted from the sample based on an operation received from the user. And the measurement system 1 detects the said various radiation by the detection part 2 in the measurement period between the start time which is the time which received the said operation, and until the predetermined measurement time passes. Here, the start time may be a time before the time when the detection unit 2 starts detecting radiation, or may be substantially the same time. Hereinafter, the difference between the start time and the time will be referred to as a standby time. The measurement system 1 receives a standby time from the user, and starts detection of radiation by the detection unit 2 based on the received standby time.

  In addition, the detection unit 2 outputs a signal indicating each of various types of radiation detected by the detection unit 2 to the wave height analyzer 3. The wave height analyzer 3 acquires the signal from the detection unit 2. Moreover, the wave height analyzer 3 calculates the spectrum of the radiation detected by the detection unit 2 at a plurality of timings within the measurement period, using the plurality of acquired signals. The spectrum is the energy spectrum of the radiation. Hereinafter, a case will be described in which the plurality of timings are timings that equally divide the time between the time when the standby time has elapsed from the start time of the measurement period and the end time of the measurement period into a predetermined number. Therefore, hereinafter, for convenience of explanation, a time between a certain timing among the plurality of timings and a timing next to the timing will be referred to as a monitor interval. The monitoring interval is, for example, 60 seconds, but may be shorter than 60 seconds or longer than 60 seconds. Note that the plurality of timings may instead be a plurality of random timings within the time between the time when the standby time has elapsed from the start time of the measurement period and the end time of the measurement period. There may be a plurality of other timings based on time. Moreover, the wave height analyzer 3 may be configured to calculate the spectrum of the radiation detected by the detection unit 2 at a certain timing within the measurement period, using a plurality of the acquired signals. The pulse height analyzer 3 outputs information indicating the calculated spectrum to the controller 4. The control device 4 acquires the information from the wave height analyzer 3. Based on the acquired information, the control device 4 calculates the uncertainty of each of the counts together with each of the counts of radiation emitted from each of the one or more detection target nuclides received from the user. For each of the one or more detection target nuclides, the control device 4 performs processing based on the calculated count of radiation emitted from the detection target nuclides. This process is, for example, a process for calculating the radioactivity of the detection target nuclide. The process may be another process based on the count instead of the process of calculating the radioactivity of the detection target nuclide.

  Here, in a measurement system X (for example, a conventional measurement system) different from the measurement system 1, the measurement time is calculated in advance by preliminary measurement. For this reason, in the measurement system X, when the measurement time has elapsed from the time when the operation for starting the detection of radiation has been received from the user, various types of radiation radiated from the sample (that is, spectrum collection described later) are performed. finish. Specifically, the measurement system X ends the detection of the radiation by the detection unit 2 and the calculation of the spectrum by the wave height analyzer 3, and ends the detection of the various types of radiation. However, since the uncertainty of the count of radiation emitted from the target nuclide detected by the radiation detector within the measurement time changes due to the influence of statistical fluctuations every time the radiation is detected, the target uncertainty May not be reached. As a result, the measurement system X may have to remeasure various types of radiation emitted from the sample.

  In order to solve this problem, the measurement system 1 uses the spectrum of the radiation calculated by the pulse height analyzer 3 based on the signal indicating the radiation detected by the detection unit 2 to detect the radiation radiated from the detection target nuclide. Along with the count, the uncertainty of the count is calculated. The measurement system 1 determines whether or not the calculated count uncertainty is less than or equal to the target uncertainty. Then, the measurement system 1 ends the measurement of the radiation emitted from the sample based on the determination result. Thereby, the measurement system 1 can suppress that the time until the uncertainty of the count of the radiation radiated from the detection target nuclide reaches below the target uncertainty is increased. Hereinafter, a process in which the measurement system 1 calculates the uncertainty of the count together with the count of radiation emitted from the detection target nuclide will be described in detail. Moreover, below, the measurement system 1 demonstrates the case where the calculation of the spectrum by the wave height analyzer 3 is complete | finished based on the said determination result, and the said measurement is complete | finished as an example. The measurement system 1 may have a configuration in which the measurement system 1 ends detection of radiation by the detection unit 2 based on the determination result, and ends the measurement. The measurement system 1 is based on the determination result. Thus, the configuration may be such that both the detection and the calculation are terminated and the measurement is terminated.

<Configuration of measurement system>
Hereinafter, the configuration of the measurement system 1 will be described with reference to FIG.

  The detection unit 2 is, for example, a semiconductor detector such as germanium, and detects at least gamma rays and X-rays among various types of radiation emitted from the sample. The detection unit 2 may be a detector that can detect other radiation in addition to gamma rays and X-rays, and can detect other radiation in place of either or both of gamma rays and X-rays. It may be a vessel. That is, the detection unit 2 may be another radiation detector such as a GM (Geiger-Muller) counter, a scintillation counter, or the like, instead of the semiconductor detector. The detection unit 2 may be surrounded by a shield that shields the radiation (external radiation) other than the radiation radiated from the sample from entering the detector 2, and is not surrounded by the shield. Also good. The shield is a shield made of lead, for example. Note that the shield may be formed of another substance instead of lead.

  The wave height analyzer 3 is, for example, a multi-channel analyzer. The pulse height analyzer 3 acquires a signal indicating the radiation detected by the detection unit 2 from the detection unit 2. The wave height analyzer 3 calculates a wave height distribution of the acquired signal, that is, a count value for each of a plurality of channels set according to the wave height value. For example, when a signal having a peak value corresponding to the energy of the radiation emitted from the sample is acquired from the detection unit 2, the pulse height analyzer 3 generates the above-described spectrum as the pulse height distribution of the acquired signal. The process in which the wave height analyzer 3 acquires the signal from the detection unit 2 and generates the spectrum based on the acquired signal may be referred to as spectrum collection by the wave height analyzer 3. That is, the wave height analyzer 3 collects a spectrum. Note that the bin of the spectrum corresponds to each of the plurality of channels. The wave height analyzer 3 may be another analyzer that calculates a count based on a signal indicating radiation detected by the detector 2 such as a single channel analyzer.

  The control device 4 is, for example, a workstation, a desktop PC (Personal Computer), a notebook PC, a tablet PC, a multi-function mobile phone (smart phone), a PDA (Personal Digital Assistant), or the like. The control device 4 controls the entire measurement system 1. The control device 4 includes a CPU (not shown), a storage unit 42, an input receiving unit 43, a communication unit 44, a display unit 45, and a control unit 46.

  A CPU (not shown) included in the control device 4 executes various programs stored in the storage unit 42.

  The storage unit 42 includes, for example, an HDD (Hard Disk Drive), an SSD (Solid State Drive), an EEPROM (Electrically Erasable Programmable Read-Only Memory), a ROM (Read-Only Memory), a RAM (Random Access Memory), and the like. The storage unit 42 may be an external storage device connected via a digital input / output port such as a USB instead of the one built in the control device 4. The storage unit 42 stores various information processed by the control device 4, various images, various programs, and the like.

  The input receiving unit 43 is, for example, a keyboard, mouse, touch pad, or other input device. The input receiving unit 43 may be a touch panel configured integrally with the display unit 45. Further, in this example, the input receiving unit 43 is configured integrally with the control device 4, but may be configured separately from the control device 4 instead. In this case, the input reception unit 43 is communicably connected to the control device 4 by wire or wireless.

  The communication unit 44 includes, for example, a digital input / output port such as USB, an Ethernet (registered trademark) port, and the like.

  The display unit 45 is, for example, a liquid crystal display panel or an organic EL (ElectroLuminescence) display panel. In this example, the display unit 45 is configured integrally with the control device 4, but may instead be configured separately from the control device 4. In this case, the display unit 45 is communicably connected to the control device 4 by wire or wireless.

  The control unit 46 includes a display control unit 461, a setting reception unit 462, a spectrum acquisition unit 463, a count calculation unit 465, an uncertainty calculation unit 466, a determination unit 467, and a measurement control unit 469. These functional units included in the control unit 46 are realized, for example, when the above-described CPU executes various programs stored in the storage unit 42. Further, some or all of the functional units may be hardware functional units such as LSI (Large Scale Integration) and ASIC (Application Specific Integrated Circuit).

  Based on the operation received from the user, the display control unit 461 generates various screens including an operation screen in which the control device 4 receives an operation from the user. The display control unit 461 displays the generated various screens on the display unit 45.

  The setting accepting unit 462 accepts various settings set in each functional unit included in the control unit 46 from the user via at least some of the various screens displayed on the display unit 45 by the display control unit 461. .

  The spectrum acquisition unit 463 acquires information indicating the spectrum calculated by the wave height analyzer 3 from the wave height analyzer 3. The spectrum acquisition unit 463 is information stored in advance by the user and based on correspondence information indicating the correspondence between each of a plurality of channels of the pulse height analyzer 3 and energy, and a plurality of spectra indicated by the acquired information. Bins indicating each of the plurality of channels are converted into bins indicating energy. In the following, for convenience of explanation, description of such bin conversion processing by the spectrum acquisition unit 463 is omitted.

  The count calculation unit 465 calculates the count of radiation emitted from the detection target nuclide using the spectrum indicated by the information acquired by the spectrum acquisition unit 463.

  The uncertainty calculation unit 466 calculates the count uncertainty calculated by the count calculation unit.

  The determination unit 467 determines whether or not the uncertainty calculated by the uncertainty calculation unit 466 is equal to or less than the target uncertainty.

  The measurement control unit 469 terminates measurement of various types of radiation emitted from the sample based on the determination result of the determination unit 467. In this example, the measurement control unit 469 ends the spectrum calculation by the pulse height analyzer 3 based on the determination result.

<Specific examples of various screens displayed on the display unit by the control device>
Hereinafter, specific examples of various screens displayed on the display unit 45 by the control device 4 will be described with reference to FIGS. Note that the configurations of the various screens described below are merely examples, and may be configured with arbitrary changes. The control device 4 may be configured to display one or more screens different from the various screens described below on the display unit 45.

  FIG. 2 is a diagram illustrating an example of an operation screen on which the control device 4 receives an operation from the user among the screens displayed on the display unit 45 by the control device 4. A screen 31 illustrated in FIG. 2 is an example of an operation screen. In this example, the screen 31 includes a switching tab 32 including a button 32a and a button 32b. The button 32a is a button for displaying a target uncertainty setting screen, which is a screen for setting the target uncertainty, instead of the screen 31. The button 32b is a button for displaying a measurement condition setting screen for setting measurement conditions, which are various conditions related to the measurement of radiation by the measurement system 1, instead of the screen 31. The screen 31 may be configured to include other GUIs in addition to these GUIs (Graphical User Interfaces), or may be configured to include other GUIs instead of these GUIs. Good.

  When receiving an operation (for example, click, tap, etc.) for selecting the button 32a from the user, the display control unit 461 displays a target uncertainty setting screen instead of the screen 31 (switches from the screen 31 to the screen). . Further, when receiving an operation (for example, click, tap, etc.) for selecting the button 32b from the user, the display control unit 461 displays a measurement condition setting screen instead of the screen 31 (switches from the screen 31 to the screen). ).

  FIG. 3 is a diagram illustrating an example of a target uncertainty setting screen. That is, the screen 33 shown in FIG. 3 is an example of a target uncertainty setting screen. In this example, the screen 33 includes a switching tab 34 including a button 34 a and a button 34 b, a screen 36, and a screen 37. Note that the screen 33 may be configured to include other GUIs in addition to these GUIs, or may be configured to include other GUIs instead of these GUIs.

  The button 34a is a button for receiving (registering) a detection target nuclide. When the display control unit 461 receives an operation (for example, click, tap, etc.) for selecting the button 34 a from the user, for example, the display control unit 461 reads out information indicating a list of nuclides stored in the storage unit 42 from the storage unit 42 in advance. The nuclide is a radionuclide. Then, the display control unit 461 displays a screen for displaying a list of nuclides on the screen 33 based on the read information. On the screen, the user can select one or more desired nuclides as one or more detection target nuclides from the list displayed on the screen. When the user selects one or more nuclides on the screen, the setting reception unit 462 receives each of the one or more nuclides selected by the user as a detection target nuclide. In this case, the display control unit 461 deletes the screen and displays on the screen 36 detection target radiation information that is information indicating radiation emitted by one or more detection target nuclides received by the setting reception unit 462. Let The detection target radiation information indicating the radiation emitted by a certain detection target nuclide is information including detection target nuclide information indicating the detection target nuclide and energy information indicating the energy of the radiation. The detection target nuclide information is, for example, a symbol, a numerical value, a character string, or the like indicating the detection target nuclide. The energy information is a numerical value, a symbol, a character string, or the like indicating the energy. When some of the one or more nuclides selected by the user are nuclides that emit a plurality of radiations having different energies, such as cobalt 57 and cobalt 60, the display control unit 461 includes: As shown in FIG. 3, for each nuclide, detection target radiation information indicating each of the plurality of radiations emitted by the nuclide is displayed on the screen 36. Further, the detection target radiation information may be information including channel information indicating a channel in which the radiation is detected instead of the energy information. Further, the detection target radiation information may be information including a partial combination of the detection target nuclide information, the energy information, and the channel information.

  The button 34b is a button that removes (cancels) some or all of one or more nuclides received as detection target nuclides by the setting reception unit 462 from the detection target nuclides. When the display control unit 461 receives an operation (for example, click, tap, etc.) for selecting the button 34b from the user, the display control unit 461 displays, for example, a list of one or more nuclides received as detection target nuclides by the setting reception unit 462. The screen is displayed over the screen 33. On the screen, the user can select one or more nuclides from the list displayed on the screen. When the user selects one or more nuclides on the screen, the setting reception unit 462 removes the one or more nuclides selected by the user from the detection target nuclides. In this case, the display control unit 461 deletes the screen, and deletes the detection target radiation information indicating the radiation emitted by the nuclide removed from the detection target nuclide by the setting reception unit 462 from the screen 36.

  As described above, the screen 36 is a screen that accepts (sets) target uncertainty for each radiation indicated by each of the one or more detection target radiation information displayed on the screen 36. The target uncertainty for a given radiation is the target uncertainty for that radiation count uncertainty. As shown in FIG. 3, the screen 36 displays input fields corresponding to each of the one or more detection target radiation information displayed on the screen 36. Each of the input fields displayed on the screen 36 is a field for inputting the radiation target uncertainty indicated by the detection target radiation information corresponding to each input field. That is, the user can input the target uncertainty of radiation indicated by the detection target radiation information in an input field corresponding to certain detection target radiation information. When a value in a certain input field displayed on the screen 36 is input, the setting reception unit 462 displays the target value of radiation indicated by the detection target radiation information corresponding to the input field as the value input in the input field. Accept as uncertainty.

  FIG. 3 shows an example of the screen 36 when each of the cobalt 57 and the cobalt 60 is selected as a detection target nuclide. Here, the cobalt 57 emits 122.05 keV radiation and 136.47 keV radiation. Further, the cobalt 60 emits 1173.21 keV radiation and 13332.47 keV radiation. Therefore, on the screen 36, detection target radiation information “Co-57 (122.05 keV)”, detection target radiation information “Co-57 (136.47 keV)”, and “Co-60 (1173.21 keV)” are displayed. ) ”And four pieces of detection target radiation information of“ Co-60 (13332.47 keV) ”. Here, “Co-57” is detection target nuclide information indicating cobalt 57. “Co-60” is detection target nuclide information indicating cobalt 60. Further, “(122.05 keV)”, “(136.47 keV)”, “(1173.21 keV)”, and “(133.47 keV)” are energy information.

  In the screen 36 shown in FIG. 3, the value “1.0” is input from the user in the input field corresponding to the detection target radiation information “Co-57 (122.05 keV)”. That is, the user inputs a value of “1.0” in the input field when the target uncertainty with respect to the uncertainty of the count of 122.05 keV radiation emitted from the cobalt 57 is set to 1.0%. When a value is input in the input field, the setting receiving unit 462 receives the value as the target uncertainty of radiation indicated by the detection target radiation information corresponding to the input field. That is, in the example illustrated in FIG. 3, the setting reception unit 462 receives 1.0% as the target uncertainty of 122.05 keV radiation radiated from the cobalt 57.

  In addition, on the screen 36, the value “1.0” is input from the user in the input field corresponding to the detection target radiation information “Co-57 (136.47 keV)”. That is, when the user sets the target uncertainty to the uncertainty of counting 136.47 keV radiation emitted from the cobalt 57, the user inputs a value of “1.0” in the input field. When a value is input in the input field, the setting receiving unit 462 receives the value as the target uncertainty of radiation indicated by the detection target radiation information corresponding to the input field. That is, in the example illustrated in FIG. 3, the setting reception unit 462 receives 1.0% as the target uncertainty of the 136.47 keV radiation radiated from the cobalt 57.

  On the screen 36, the value “1.0” is input from the user in the input field corresponding to the detection target radiation information “Co-60 (1173.21 keV)”. That is, the user inputs a value of “1.0” in the input field when setting the target uncertainty with respect to the uncertainty of the count of 1173.21 keV radiation radiated from the cobalt 60 to 1.0%. When a value is input in the input field, the setting receiving unit 462 receives the value as the target uncertainty of radiation indicated by the detection target radiation information corresponding to the input field. That is, in the example illustrated in FIG. 3, the setting reception unit 462 receives 1.0% as the target uncertainty of the 1173.21 keV radiation radiated from the cobalt 60.

  Further, on the screen 36, the value “1.0” is input from the user in the input column corresponding to the detection target radiation information “Co-60 (13332.47 keV)”. That is, the user inputs a value of “1.0” in the input field when setting the target count for the uncertainty of the count of 13332.47 keV radiation emitted from cobalt 60 to 1.0%. When a value is input in the input field, the setting receiving unit 462 receives the value as the target uncertainty of radiation indicated by the detection target radiation information corresponding to the input field. That is, in the example illustrated in FIG. 3, the setting reception unit 462 receives 1.0% as the target uncertainty of the radiation of 13232.47 keV emitted from the cobalt 60.

  The screen 37 is a screen for receiving, for example, the above-described standby time, the above-described monitoring interval, and the continuous determination number target value (indicated as the number of times of arrival in FIG. 3). The screen 37 includes a standby time input field that is an input field for inputting a standby time, a monitor interval input field that is an input field for inputting a monitor interval, and a continuous determination frequency target value input field for inputting a continuous determination frequency target value. It is included. The continuous determination frequency target value is a value related to determination by the determination unit 467. Details of the target number of continuous determination times will be described later. The screen 37 may be configured to receive other information in addition to these pieces of information. When the user inputs a value in the standby time input field, the setting reception unit 462 receives the value input by the user as the standby time. When the user inputs a value in the monitor interval input field, the setting reception unit 462 receives the value input by the user as the monitor interval. When the user inputs a value in the continuous determination number target value input field, the setting reception unit 462 receives the value input by the user as the continuous determination number target value.

  FIG. 4 is a diagram illustrating an example of a measurement condition setting screen. That is, the screen 38 shown in FIG. 4 is an example of a measurement condition setting screen. In this example, the screen 38 includes a screen 40. The screen 38 may be configured to include other GUIs in addition to the screen 40, or may be configured to include other GUIs instead of the screen 40. The screen 40 is a screen that receives information indicating the presence / absence of determination by the determination unit 467. In the example shown in FIG. 4, a check box associated with the character string “set target uncertainty” is displayed on the screen 40. When an operation (for example, click, tap, etc.) for selecting the check box is received from the user, the setting reception unit 462 validates the determination by the determination unit 467. On the other hand, when the operation for selecting the check box from the user (for example, click, tap, etc.) is not received, the setting reception unit 462 invalidates the determination by the determination unit 467.

<Process in which the control device calculates the uncertainty of the count together with the count of radiation emitted from the detection target nuclide>
Hereinafter, with reference to FIG. 5, a description will be given of a process in which the control device 4 calculates the uncertainty of the count together with the count of the radiation emitted from the detection target nuclide. FIG. 5 is a diagram illustrating an example of a flow of processing in which the control device 4 calculates the uncertainty of the count together with the count of radiation emitted from the detection target nuclide. In the following description, the setting reception unit 462 receives in advance the target uncertainty for each radiation emitted by each of the one or more detection target nuclides and each of the one or more detection target nuclides from the user on the target uncertainty setting screen. The case where it has been described will be described. Hereinafter, a case in which the determination by the determination unit 467 is validated in advance by the setting reception unit 462 will be described.

  The setting receiving unit 462 repeatedly performs the process of step S120 for each of one or more detection target nuclides received in advance from the user (step S110).

  The setting receiving unit 462 determines whether or not the target uncertainty of the radiation emitted from the detection target nuclide selected in step S110 has been received in advance (step S120). Here, in step S120, when a plurality of radiations having different energies are emitted from the detection target nuclide selected in step S110, the setting reception unit 462 determines in advance all target uncertainties for each of the plurality of radiations. By accepting, it is determined that the target uncertainty of the radiation emitted from the detection target nuclide is accepted in advance. When the setting reception unit 462 determines that the target uncertainty of the radiation emitted from the detection target nuclide selected in step S110 has not been received in advance (step S120—NO), the control unit 46 ends the process. On the other hand, when it is determined that the target uncertainty of the radiation radiated from the detection target nuclide selected in step S110 has been received in advance (step S120-YES), the setting reception unit 462 transitions to step S110, and the next Select unselected detection target nuclides. If there is no unselected detection target nuclide in step S110, the setting reception unit 462 proceeds to step S130.

  In step S130, the setting reception unit 462 determines whether or not the continuous determination frequency target value has been received in advance (step S130). Here, the continuous determination number target value will be described. For example, when the number of detection target nuclides selected by the user is one, the measurement control unit 469 continuously determines that the uncertainty calculated by the uncertainty calculation unit 466 is equal to or less than the target uncertainty by the predetermined number of times determination unit 467. If so, the spectrum calculation by the wave height analyzer 3 is terminated. This predetermined number of times is the continuous determination number of times target value. Hereinafter, as an example, a case where the target number of times of continuous determination is 5 will be described. In addition, the continuous determination frequency target value may be less than 5 times or more than 5 times. On the other hand, when there are a plurality of detection target nuclides selected by the user, the measurement control unit 469 has a radiation count uncertainty less than the target uncertainty of the radiation for all of the radiation emitted from each of the plurality of detection target nuclides. If the predetermined number of times (that is, the continuous determination number target value) determination unit 467 determines that it is continuously, the spectrum calculation by the wave height analyzer 3 is terminated. For example, the determination result by the determination unit 467 for each of the uncertainty in counting the radiation emitted from the detection target nuclide A, which is a certain two detection target nuclides, and the uncertainty in counting the radiation emitted from the detection target nuclide B, In the case of the determination result shown in Table 1 below, the measurement control unit 469 ends the spectrum calculation by the wave height analyzer 3 when the determination by the determination unit 467 for the ninth time is completed. This is because the determination result of the ninth determination unit 467 shows that the count uncertainty of the radiation radiated from the detection target nuclide A has reached the target uncertainty five times in succession, and the radiation from the detection target nuclide B This is because the uncertainties in the counting of the emitted radiation have reached the target uncertainty five times in succession.

  When the setting reception unit 462 determines that the continuous determination number of times target value has not been received in advance in step S130 (step S130-NO), the control unit 46 ends the process. On the other hand, when the setting reception unit 462 determines that the continuous determination frequency target value has been received in advance (step S130—YES), the determination unit 467 sets the variable indicating the number of continuous determinations stored in the storage unit 42 to 0. Initialization is performed (step S140). Next, the measurement control unit 469 determines whether or not an operation for starting the measurement of radiation by the measurement system 1 has been received in advance (step S150). When the measurement control unit 469 determines that the operation has not been received in advance (step S150—NO), the control unit 46 ends the process. On the other hand, when it is determined that the operation has been received in advance (step S150-YES), the measurement control unit 469 determines the time from which the operation is received, that is, the start time of the measurement period described above, via the target uncertainty setting screen. The setting reception unit 462 waits until the standby time received from the user has elapsed (step S160). When the standby time has elapsed from the start time (step S160—YES), the measurement control unit 469 starts the spectrum calculation by the wave height analyzer 3 (step S170). Specifically, in step S170, the measurement control unit 469 is a signal of radiation detected by the detection unit 2 at the time when the standby time has elapsed from the start time, and each of various types of radiation emitted from the sample. Is started by the wave height analyzer 3. Here, the detection unit 2 outputs a signal indicating the detected radiation to the wave height analyzer 3 every time the radiation is detected. For this reason, acquisition of the signal by the wave height analyzer 3 is continuously performed until the measurement control unit 469 finishes the calculation of the spectrum by the wave height analyzer 3 in step S240. Then, when the monitoring interval elapses from the time when the standby time has elapsed from the start time, the measurement control unit 469 transmits the spectrum to the pulse height analyzer 3 based on the plurality of signals acquired from the detection unit 2 up to the current time. Calculation is performed (step S170). The pulse height analyzer 3 outputs information indicating the calculated spectrum to the controller 4. The spectrum acquisition unit 463 acquires the information from the wave height analyzer 3.

  Next, the uncertainty calculation unit 465 repeatedly performs the process of step S190 for each of one or more detection target nuclides received in advance from the user (step S180).

  The count calculation unit 465 calculates the count of radiation emitted from the detection target nuclide selected in step S180 based on the spectrum indicated by the information acquired by the spectrum acquisition unit 463 in step S170 (step S190). Here, in step S190, when a plurality of radiations having different energies are emitted from the detection target nuclide selected in step S180, the count calculation unit 465 calculates a count for each of the plurality of radiations.

  In step S190, the count calculation unit 465 responds to the energy of the radiation radiated from the detection target nuclide selected in step S180 out of the parts included in the spectrum indicated by the information acquired by the spectrum acquisition unit 463 in step S170. A peak region which is a part (in other words, a region including a part where a peak appears), a first base region for obtaining a net count on the energy side lower than the peak, and a net count on the energy side higher than the peak A region including the second base region is specified as an ROI (Region Of Interest) region. The part corresponding to the energy is, for example, a part included in a predetermined range with the energy as a central value. The predetermined range is, for example, a range of ± 10% of the energy, but may be another range instead. In addition, when a plurality of radiations having different energies are emitted from the detection target nuclide, the count calculation unit 465 specifies a portion corresponding to each energy of the plurality of radiations as an ROI region. The method by which the count calculation unit 465 calculates the radiation count corresponding to each of the specified one or more ROI regions may be a known method or a method to be developed in the future. For example, the count calculation unit 465 counts the radiation corresponding to the ROI region for each of the specified one or more ROI regions, for each of the peak region, the first base region, and the second base region. And is calculated by the Kobel method. Specifically, for each of the specified one or more ROI regions, the count calculation unit 465 subtracts the area of the portion representing the background in the ROI region from the area of the spectrum included in the ROI region (that is, the net count). (Net count)) is calculated as the count of radiation corresponding to the ROI region. Note that the count calculation unit 465 is a function obtained by fitting a certain function (for example, a normal distribution function) to the shape of the spectrum included in the ROI region instead of the configuration in which the count is calculated by the Kobel method. The net area of the function in the ROI region may be calculated as the count.

  After the process of step S190 is performed, the uncertainty calculation unit 466 calculates the count uncertainty calculated by the count calculation unit 465 in step S190 (step S195). In step S195, the calculation unit 466 calculates the uncertainty by, for example, “Radioactivity Measurement Method Series 7 Gamma-Ray Spectrometry Using Germanium Semiconductor Detector” issued by the Japan Analysis Center (revised in 1992, Ministry of Education, Culture, Sports, Science and Technology) This is the method described on pages 137-140 of the Science and Technology / Academic Policy Bureau. In this case, the uncertainty is the standard deviation of the count. The uncertainty may be another value representing the statistical variation of the count instead of the standard deviation.

  After the repetitive processing of step S170 to step S195 is performed, the display control unit 461 is a count calculated by the count calculation unit 465, and the radiation emitted by each of one or more detection target nuclides received in advance from the user. And the uncertainty of the count calculated by the uncertainty calculation unit 466 is displayed on the display unit 45 (step S200). For example, the display control unit 461 displays the table shown in FIG. 6 on the aforementioned operation screen. FIG. 6 is a diagram illustrating an example of a table displayed on the display unit 45 in step S200. In the table shown in FIG. 6, the detection target nuclide information, the count of radiation emitted by the detection target nuclide indicated by the detection target nuclide information, which is a count calculated in the repetitive processing of step S170 to step S195, The target uncertainty of radiation, the uncertainty of the radiation count calculated in the repetitive processing of steps S170 to S195, and the scheduled measurement end date and time of the radiation count are associated with each other. The scheduled measurement end date and time of the radiation count is the date and time when the uncertainty of the radiation count is estimated to reach the target uncertainty. In addition, when displaying the said table | surface on the operation screen, the display control part 461 calculates the measurement end date and time of the measurement uncertainty of the said radiation based on the half life of the said detection target nuclide. In the example shown in FIG. 6, the target uncertainty count of the radiation emitted by the detection target nuclide A is 1.0%, and the uncertainty of the radiation count calculated in the iterative process is 2.6%. Yes, the scheduled measurement end date and time of the radiation count is November 16, 2016 at 10:00. In this example, the target uncertainty of the radiation emitted by the detection target nuclide B is 1.0%, and the uncertainty of the radiation count calculated in the iterative process is 4.5%. The scheduled measurement end date and time of the radiation count is 11:20 on November 16, 2016.

  After the process of step S200 is performed, the determination unit 467 calculates the radiation calculated in the repetition process of steps S170 to S190 for all of the radiation emitted by each of the one or more detection target nuclides received in advance from the user. It is determined whether or not the counting uncertainty is less than or equal to the target uncertainty (step S210). When it is determined that at least one of the radiations emitted by each of the one or more detection target nuclides is not less than the target uncertainty, the uncertainty of the radiation count calculated in the repetitive processing (step S210-NO) The determination unit 467 initializes a variable indicating the number of continuous determinations stored in advance in the storage unit 42 to 0 (step S280). Then, the measurement control unit 469 transitions to step S170 and waits until the monitoring interval elapses from the time when the wave height analyzer 3 calculates the previous spectrum. When the monitoring interval elapses from the time, the measurement control unit 469 causes the wave height analyzer 3 to calculate a spectrum based on a plurality of signals acquired from the detection unit 2 up to the current time. The pulse height analyzer 3 outputs information indicating the calculated spectrum to the controller 4. The spectrum acquisition unit 463 acquires the information from the wave height analyzer 3. On the other hand, for all of the radiation emitted by each of the one or more detection target nuclides, when it is determined that the uncertainty of the radiation count calculated in the repetitive processing is equal to or less than the target uncertainty (step S210—YES). The determination unit 467 adds 1 to a variable indicating the number of continuous determinations stored in advance in the storage unit 42 (step S220).

  Next, the measurement control unit 469 determines whether or not the variable indicating the number of continuous determinations stored in advance in the storage unit 42 is 5 or more (step S230). When it determines with the variable which shows the said continuous determination frequency | count not being 5 or more (step S230-NO), the measurement control part 469 transfers to step S170, and monitoring interval is from the time when the wave height analyzer 3 calculated the last spectrum. Wait until it has passed. When the monitoring interval elapses from the time, the measurement control unit 469 causes the wave height analyzer 3 to calculate a spectrum based on a plurality of signals acquired from the detection unit 2 up to the current time. The pulse height analyzer 3 outputs information indicating the calculated spectrum to the controller 4. The spectrum acquisition unit 463 acquires the information from the wave height analyzer 3. On the other hand, when it is determined that the variable indicating the number of continuous determinations is 5 or more (step S230—YES), the measurement control unit 469 causes the wave height analyzer 3 to finish acquiring signals from the detection unit 2 (step S240). ).

  Next, the measurement control unit 469 causes the wave height analyzer 3 to calculate a spectrum based on a plurality of signals acquired from the detection unit 2 from the start time of the measurement period to the current time (step S250). Next, the measurement control unit 469 ends the spectrum calculation by the wave height analyzer 3 (step S255).

  Next, the count calculation unit 465 repeats the process of step S270 for each of one or more detection target nuclides received in advance from the user (step S260).

  The count calculation unit 465 calculates the count of radiation emitted from the detection target nuclide selected in step S260 based on the spectrum indicated by the information acquired by the spectrum acquisition unit 463 in step S250 (step S270). Here, since the process of step S270 is the same process as the process of step S190, detailed description is abbreviate | omitted. And after the repetition process of step S260-step S270 is performed, the control part 46 complete | finishes a process.

  The setting reception unit 462 may be configured to receive a measurement time from the user via a screen such as the above-described target uncertainty setting screen. In this case, in the case of the process of step S230 (step S230-NO), the measurement control unit 469 determines whether the measurement time has elapsed from the start time of the measurement period before transitioning to step S170. . If it is determined that the measurement time has not elapsed since the start time, the measurement control unit 469 proceeds to step S170. On the other hand, when it is determined that the measurement time has elapsed from the start time, the measurement control unit 469 proceeds to step S240. In this case, since it is in the process of step S230 (step S230-NO), the measurement system 1 counts a part of the counts of radiation emitted by each of the one or more detection target nuclides received in advance from the user. Therefore, it is necessary to remeasure various types of radiation emitted from the sample. In the measurement system X described above, such remeasurement is started by receiving an operation for starting the remeasurement from the user.

  Here, the control device 4 may be configured to automatically start such re-measurement. For example, in the first measurement of various types of radiation radiated from the sample, the control device 4 has a target uncertainty that is the uncertainty of some of the counts of radiation emitted by each of the one or more detection target nuclides. If not, the second measurement of various types of radiation emitted from the sample is started without accepting an operation from the user (automatically). Then, the control device 4 counts the radiation calculated by the first measurement and the radiation calculated by the second measurement for each of the radiation emitted by each of the one or more detection target nuclides. Add the count.

  Specifically, the control device 4 automatically starts remeasurement of various types of radiation emitted from the sample by performing the processing of the flowchart shown in FIG. FIG. 7 is a diagram illustrating an example of a flow of processing in which the control device 4 performs remeasurement of various types of radiation emitted from the sample. Here, the measurement time received from the user by the setting reception unit 462 described above is calculated based on, for example, the time estimated from the start time of the measurement period that the uncertainty of the detection target radiation count is equal to or less than the target uncertainty, The time is longer than the time. Note that the measurement time may be a time that is less than or equal to the time that the uncertainty in counting the detection target radiation is less than or equal to the target uncertainty from the start time of the measurement period.

  Each of the functional units included in the control unit 46 executes the process of the flowchart shown in FIG. 5 as the first count calculation process (step S310). Next, the determination unit 467 determines whether or not the number of continuous determinations is determined to be 5 or more in step S230 in the first count calculation process (step S320). In the process of step S320, the uncertainty of the radiation count calculated in the repetition process of steps S170 to S190 is the target uncertainty for all of the radiation emitted by each of the one or more detection target nuclides received in advance from the user. This is a process for determining whether or not: Hereinafter, for convenience of explanation, each count calculated in steps S260 to S270 in the first count calculation process will be referred to as a first count. When the determination unit 467 determines that the number of continuous determinations is 5 or more in step S230 (step S320—YES), the control unit 46 ends the process. On the other hand, when the determination unit 467 determines that the number of continuous determinations is not determined to be 5 or more in step S230 (step S320—NO), each of the functional units included in the control unit 46 is illustrated in FIG. The process of the flowchart is executed as the second count calculation process (step S330). Here, in step S330, the control device 4 executes the second count calculation process while holding various conditions (that is, measurement conditions) set in the control device 4 when the first count calculation process is executed. To do. In the second count calculation process, the control device 4 may be configured to use a time shorter than the measurement time in the first count calculation process as the measurement time in the second count calculation process. Hereinafter, for convenience of explanation, each count calculated in step S260 to step S270 in the second count calculation process will be referred to as a second count.

  Next, the count calculation unit 465 adds the first count of radiation and the second count of radiation for each of the radiation emitted by each of the one or more detection target nuclides received in advance from the user, A summation process is performed in which the calculated value is a new first count (step S340). Then, the determination unit 467 proceeds to step S320, and determines again whether or not it is determined in step S340 that the number of continuous determinations is 5 or more.

  As described above, the control device 4 can perform re-measurement of various kinds of radiation emitted from the sample by performing the processing of the flowchart shown in FIG. As a result, the control device 4 can reduce the labor required for remeasurement of radiation. Note that the control device 4 performs the process of step S320 after the process of step S340 is performed in order to prevent the process of step S320 to step S340 from being repeated for a predetermined time or longer due to some cause. It may be configured to determine whether or not the repeated end condition is satisfied before being performed. The predetermined time is, for example, five times the above-described measurement time. Alternatively, the predetermined time may be a time shorter than five times the measurement time or a time longer than five times the measurement time. The repetition end condition is, for example, that the real-time elapsed time that is the elapsed time from the start time of the measurement period in the first count calculation process to the current time exceeds a predetermined first upper limit value, The live time elapsed time, which is the total time of the time required and the time required for the second count calculation process, exceeds a predetermined second upper limit value, and the number of times the second count calculation process is performed is determined in advance. It is a condition including at least one of exceeding the third upper limit value. In this case, when the repeated end condition includes a plurality of conditions, the control device 4 determines whether or not the repeated end including one or more conditions selected by the user is satisfied. In this case, the control device 4 may be configured to accept in advance from the user whether to enable or disable the determination of whether or not the repeated end condition is satisfied.

  Note that the determination unit 467 described above determines whether the calculated radiation count uncertainty is less than or equal to the target uncertainty for all of the radiation emitted by each of the one or more detection target nuclides received in advance from the user. However, instead of this, all of some of the radiation received from the user out of the radiation emitted from each of the one or more detection target nuclides received from the user is calculated. It may be configured to determine whether or not the uncertainty of counting the radiation is equal to or less than the target uncertainty.

  In addition, when calculating the radiation count corresponding to a certain ROI region based on the Kobel method, the count calculation unit 465 described above, when a radiation peak different from the radiation appears in the ROI region, the ROI The structure which changes the range of an area | region may be sufficient.

  In addition, the detection target nuclide described above may include an unknown nuclide. In this case, the control device 4 detects the appearance of an unknown radiation peak in the spectrum indicated by the information acquired from the pulse height analysis device 3. And the control apparatus 4 specifies the ROI area | region corresponding to the said detected peak, and calculates the uncertainty of the said count with the count of the said radiation in the specified said ROI area | region. When the calculated count exceeds the predetermined fourth upper limit, the control device 4 is likely to have contaminated the sample with an unknown radionuclide, and therefore the sample is contaminated with an unknown radionuclide. The display unit 45 displays information indicating that there is a high possibility of being present. Moreover, the control apparatus 4 complete | finishes calculation of the spectrum by the wave height analyzer 3 in this case. The unknown nuclide corresponds to the nuclide that is not included in the list indicated by the information indicating the list of nuclides stored in the storage unit 42 in advance and the correspondence information described above among the channels of the wave height analyzer 3. It includes at least one of a nuclide that emits radiation corresponding to a count value of a channel in which no energy is present, and a nuclide whose correspondence with the energy of the emitted radiation is unknown (unknown). The control device 4 may have a configuration in which the user can select whether or not to include an unknown nuclide in the detection target nuclide, and cannot select whether or not to include an unknown nuclide in the detection target nuclide. May be. When the configuration is such that it is impossible to select whether or not to include an unknown nuclide in the detection target nuclide, the control device 4 always includes the unknown nuclide in the detection target nuclide.

  Further, the control device 4 may be configured such that the measurement time described above can be changed at any timing in steps S110 to S280 described above.

  As described above, the control device 4 in the present embodiment radiates from the detection target nuclide using the radiation spectrum calculated by the pulse height analysis device 3 based on the signal indicating the radiation detected by the detection unit 2. The uncertainty of the counted radiation is calculated, it is determined whether or not the calculated uncertainty is equal to or less than the target uncertainty, and the spectrum calculation by the pulse height analyzer 3 is terminated based on the determination result. Thereby, the control apparatus 4 can suppress that time until the uncertainty of the count of the radiation radiated | emitted from a detection target nuclide reaches | attains a target uncertainty becomes long.

  Further, the control device 4 calculates the uncertainty of the count of the radiation emitted from the detection target nuclide at a plurality of timings within the measurement period, and continuously counts a predetermined number of times if the count uncertainty is equal to or less than the target uncertainty. When it determines, the calculation of the spectrum by the wave height analyzer 3 is terminated. Thereby, it can suppress more reliably that time until the uncertainty of the count of the radiation radiated | emitted from a detection target nuclide reaches | attains target uncertainty becomes long.

  In addition, when the measurement time based on the time when the uncertainty of the count of the radiation emitted from the detection target nuclide is estimated to be equal to or less than the target uncertainty has elapsed from the start time of the measurement period, the control device 4 3 finishes the spectrum calculation. Thereby, the control device 4 can end the calculation of the spectrum by the wave height analyzer 3 even when the uncertainty of the count of radiation emitted from the detection target nuclide does not fall below the target uncertainty for some reason. it can.

  In addition, when the measurement time elapses from the start time of the measurement period, the control device 4 ends the calculation of the spectrum by the wave height analyzer 3, and the uncertainty in counting the radiation emitted from the detection target nuclide When it is determined that it is larger than the target uncertainty, the spectrum calculation by the wave height analyzer 3 is restarted. Thereby, the control apparatus 4 can reduce the effort which is required for the remeasurement of the radiation radiated from the sample.

  In addition, the control device 4 is a measurement time based on the time estimated from the start time of the measurement period to the time when the uncertainty of the radiation emitted from the detection target nuclide is less than or equal to the target uncertainty, and is longer than the time. When the measurement time has elapsed, the calculation of the spectrum by the wave height analyzer 3 is terminated. Thereby, the control device 4 can end the calculation of the spectrum by the wave height analyzer 3 even when the uncertainty of the count of radiation emitted from the detection target nuclide does not fall below the target uncertainty for some reason. it can.

  Further, the control device 4 previously receives a plurality of detection target nuclides different from each other, calculates the uncertainty of the count for each radiation emitted from each of the received plurality of detection target nuclides, and for each of the plurality of detection target nuclides, Judgment is made on whether or not the uncertainty in counting the radiation emitted from the detection target nuclide is less than or equal to the target uncertainty corresponding to the radiation, and all of the radiation of each of the multiple detection target nuclides is emitted from the detection target nuclide. When it is determined that the uncertainty in counting radiation is equal to or less than the target uncertainty corresponding to the radiation, the spectrum calculation by the wave height analyzer 3 is terminated. Thereby, the control apparatus 4 suppresses that the uncertainty of the count of the radiation detected by the detection unit 2 is larger than the target uncertainty within the measurement period for all of the radiation emitted from each of the plurality of detection target nuclides. be able to.

  In addition, the measurement system 1 uses the spectrum of the radiation calculated by the wave height analyzer 3 based on the signal indicating the radiation detected by the detection unit 2 included in the measurement system 1, and the radiation emitted from the detection target nuclide. Is calculated at a plurality of timings within the measurement period, it is determined whether or not the calculated uncertainty is equal to or less than the target uncertainty, and a spectrum is calculated by the pulse height analyzer 3 based on the determination result. End. Thereby, the measurement system 1 can suppress that the time until the uncertainty of the count of the radiation radiated from the detection target nuclide reaches the target uncertainty is increased.

  Further, the measurement system 1 uses the spectrum of the radiation calculated by the wave height analyzer 3 included in the measurement system 1 based on a signal indicating the radiation detected by the detection unit included in the measurement system 1 to detect the detection target nuclide. And calculating whether or not the calculated uncertainty is less than or equal to the target uncertainty, and based on this determination result, the calculation of the spectrum by the wave height analyzer 3 is terminated. . Thereby, the measurement system 1 can suppress that the time until the uncertainty of the count of the radiation radiated from the detection target nuclide reaches the target uncertainty is increased.

  The embodiment of the present invention has been described in detail with reference to the drawings. However, the specific configuration is not limited to this embodiment, and changes, substitutions, deletions, and the like are possible without departing from the gist of the present invention. May be.

  Further, a program for realizing the function of an arbitrary component in the device described above (for example, the control device 4) is recorded on a computer-readable recording medium, and the program is read by a computer system and executed. You may do it. Here, the “computer system” includes hardware such as an OS (Operating System) and peripheral devices. The “computer-readable recording medium” refers to a portable medium such as a flexible disk, a magneto-optical disk, a ROM, a CD (Compact Disk) -ROM, or a storage device such as a hard disk built in the computer system. . Furthermore, “computer-readable recording medium” means a volatile memory (RAM) inside a computer system that becomes a server or client when a program is transmitted via a network such as the Internet or a communication line such as a telephone line. In addition, those holding programs for a certain period of time are also included.

In addition, the above program may be transmitted from a computer system storing the program in a storage device or the like to another computer system via a transmission medium or by a transmission wave in the transmission medium. Here, the “transmission medium” for transmitting the program refers to a medium having a function of transmitting information, such as a network (communication network) such as the Internet or a communication line (communication line) such as a telephone line.
Further, the above program may be for realizing a part of the functions described above. Further, the program may be a so-called difference file (difference program) that can realize the above-described functions in combination with a program already recorded in the computer system.

DESCRIPTION OF SYMBOLS 1 ... Measurement system, 2 ... Detection part, 3 ... Wave height analyzer, 4 ... Control apparatus, 42 ... Memory | storage part, 43 ... Input reception part, 44 ... Communication part, 45 ... Display part, 46 ... Control part, 461 ... Display Control unit, 462 ... Setting reception unit, 463 ... Spectrum acquisition unit, 465 ... Count calculation unit, 466 ... Uncertainty calculation unit, 467 ... Determination unit, 469 ... Measurement control unit

Claims (10)

An uncertainty calculator that calculates the uncertainty of the count of radiation emitted from the detection target nuclide using the spectrum of the radiation calculated by the pulse height analyzer based on the signal indicating the radiation detected by the detector;
A determination unit for determining whether the uncertainty calculated by the uncertainty calculation unit is equal to or less than a target uncertainty;
A measurement control unit for terminating calculation of the spectrum by the wave height analyzer based on a determination result of the determination unit;
A control device comprising: The uncertainty calculation unit calculates the uncertainty at a plurality of timings within a measurement period,
The measurement control unit terminates the calculation of the spectrum by the wave height analyzer when the determination unit continuously determines that the uncertainty is equal to or less than the target uncertainty a predetermined number of times.
The control device according to claim 1. The measurement control unit further terminates the calculation of the spectrum by the wave height analyzer when the measurement time based on the time when the uncertainty is estimated to be equal to or less than the target uncertainty has elapsed from the start time of the measurement period. ,
The control device according to claim 2. The measurement control unit determines that the measurement by the wave height analyzer is terminated when the measurement time has elapsed from the start time, and the determination unit determines that the uncertainty is greater than the target uncertainty. If so, restart the calculation of the spectrum by the wave height analyzer,
The control device according to claim 3. The measurement time is longer than the time,
The control device according to claim 3 or 4. The count calculation unit previously receives a plurality of different detection target nuclides, calculates the uncertainty for each radiation emitted from each of the received plurality of detection target nuclides,
The determination unit determines, for each of the plurality of detection target nuclides, whether the uncertainty of radiation emitted from the detection target nuclide is equal to or less than the target uncertainty corresponding to the radiation,
In the measurement control unit, the determination unit determines that the uncertainty of the radiation emitted from the detection target nuclide is equal to or less than the target uncertainty corresponding to the radiation for each of the radiations of the plurality of detection target nuclides. If so, the calculation of the spectrum by the wave height analyzer is terminated,
The control device according to any one of claims 1 to 5. A control device according to any one of claims 1 to 6;
The detection unit;
Measuring system. A control device according to any one of claims 1 to 6;
The detection unit;
The wave height analyzer;
Measuring system. Further comprising a shield for suppressing the incidence of radiation from the outside to the detection unit,
The measurement system according to claim 7 or 8. On the computer,
An uncertainty calculation step for calculating the uncertainty of the count of the radiation emitted from the detection target nuclide using the spectrum of the radiation calculated by the pulse height analyzer based on the signal indicating the radiation detected by the detection unit;
A determination step of determining whether or not the uncertainty calculated by the uncertainty calculation step is equal to or less than a target uncertainty;
A measurement control step for terminating the calculation of the spectrum by the wave height analyzer based on the determination result of the determination step;
A program that executes

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