• 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:
    System and method for the volumetric and isotopic identification of radioactive scene distributions. The present invention is a system (10) and method for the volumetric and isotopic identification of the spatial distribution of ionizing radiation from radioactive (3) point sources, or extensive, in radioactive scenes. More specifically, this system (10) comprises: a gamma radiation detector (2) and an optical transducer (1) integral with each other and linked to a control unit for detecting the absolute position, with respect to a visual reference that is found in the radioactive scene, from the radioactive sources (3) and determines its radioactive activity, that is, it detects the isotope composition of the radioactive sources (3). (Machine-translation by Google Translate, not legally binding)
    公开号:ES2681094A1
    申请号:ES201730164
    申请日:2017-02-10
    公开日:2018-09-11
    发明作者:Jorge AGRAMUNT ROS；Francisco ALBIOL COLOMER；Alberto CORBI BELLOT；Luis Caballero Ontanaya；Cesar DOMINGO PARDO；Alberto ALBIOL COLOMER
    申请人:Empresa Nacional De Residuos Radioactivos SA (enresa)；Empresa Nac De Residuos Radioactivos S A Enresa；Consejo Superior de Investigaciones Cientificas CSIC；Universitat de Valencia；
    IPC主号:
    专利说明:

    SYSTEM AND METHOD FOR VOLUMETRIC AND ISOTOPIC IDENTIFICATION OF DISTRIBUTIONS OF RADIOACTIVE SCENES
    D E S C R I P C I Ó N
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    OBJECT OF THE INVENTION
    The object of the present invention is a system and method for the volumetric and isotopic identification of the spatial distribution of an ionizing radiation from specific or extensive radioactive sources 10 in radioactive scenes.
    More specifically, this system and method detects the absolute position, with respect to a visual in the radioactive scene, of radioactive sources. It also determines its radioactive activity and the composition of the isotopes of the aforementioned sources.
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    BACKGROUND OF THE INVENTION
    Currently, due to certain industrial activities of energy production or material management and monitoring, there are environments that are potentially contaminated by radioactive material. Such contamination is usually due to uncontrolled leaks of radioactive material from radioactive sources.
    On the other hand, in relation to safety in nuclear facilities, it is necessary to carry out active and preventive surveillance tasks, such as during the transport of 25 materials found in them or at the time of the implementation of control measures.
    In all these scenarios, information on which radioisotopes are present in these materials, in what abundance and what their spatial distribution should be obtained.
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    Typically, gamma radiation detectors are used to detect such radiations, which comprise transducers that produce an electrical signal when they are stimulated by ionizing radiation. This electrical signal is proportional to the energy of the
    radiation and is unique for each isotope, since it is a function of wavelengths
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    present in it. The wavelength for which the greatest deposit of energy is produced in the detector (absence of Compton radiation) is the so-called photopic.
    By determining these photopics it is possible to characterize the polluting elements of an environment and to know the composition of isotopes that are in one or several radiation sources.
    To inspect an area contaminated with radiation it is necessary to have gamma radiation detectors. An operator must routinely move these detectors manually to locate the risk regions, inevitably being exposed to the ionizing radiation present. This type of sampling helps to map contaminated spaces. In order to avoid these negative effects, there are different solutions that are summarized below and that are also capable of performing a 2-dimensional mapping of radioactive sources.
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    An example of this solution appears in WO2005022197A2, where different methods and apparatus for the determination in two dimensions of the intensity and location of a radioactive source are described. This location is carried out by means of a device comprising a matrix of at least 3 gamma radiation detectors positioned in places 20 different from those whose coordinates are known. The operating zone, or field of vision, of the gamma radiation detectors must be partially superimposed. When this device detects a dangerous source, it generates signals according to its intensity and location. The device makes use of an algorithm that correlates the coordinates of the gamma radiation detectors with the signals generated by them. Despite these advantages, the aforementioned document does not describe how to locate and orient the detectors. In addition, detection and location capabilities are optimized for the position in which the detectors were originally established. Finally, if you want to relocate the system, it is necessary to make great efforts since it is not designed to be displaced.
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    EP2966478A1 describes a three-dimensional radiation detection system connected to a visualization system. This system comprises a radiation sensor and an image sensor coupled to a vertical and a horizontal rotation mechanism. Additionally, it describes a three-dimensional method of radiation detection and
    display. Finally, the image, the detected radiation and the 3D position are related. However, the described method is based on the visual inspection of the images that both detectors provide continuously. No precise identification of the actual position of the radioactive source is established and therefore requires 5 additional elements (such as a laser) to measure the actual distance between the source and the detectors.
    Another example that relates video to radiation detectors is found in US6782123B1. This describes a method and apparatus for accurately locating 10 radioactive sources. This apparatus comprises a pair of visible light cameras that are oriented in both directions so that the field of view of both is totally or partially common. The apparatus also comprises a gamma radiation detector. The multiplicity of visible cameras makes three-dimensional identification possible by initial triangulation. After moving the apparatus and using a second triangulation, the location of the radiation sources is identified. Additionally, this solution uses photogrammetry software to perform the calculations.
    The drawback of this solution is that it requires the correct centering of the visible light chambers and the gamma radiation detector. On the other hand, this method is not effective since it does not take into account the real differences in measurement between light, whose angular resolution is excellent, and gamma radiation, which inherently has a much lower angular resolution. Another important disadvantage is that to ensure a good detection it is necessary to keep the focus constantly on a source that, in general, may have a low intensity. Finally, it does not allow sweeping in motion, but each scene acquired with the gamma detector is independent of the previous one, resulting in false negatives for certain locations.
    Finally, EP2796898A1 describes a mobile vehicle equipped with radiation sensors 30 and which is capable of measuring the distribution of the radioactive intensity of the environment. Once this spatial distribution of intensities is obtained, the position of the radioactive source is derived. However, this system cannot be used in enclosed spaces since it does not have means for locating the radioactive source and is totally focused on the general inspection of open spaces, such as disaster areas or large deposits
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    of materials.
    As a summary, the aforementioned solutions involve devices and methods that fuse visible image and gamma detection in the same framework. However, they do not allow to obtain results fully consistent with reality. This is mainly due to the poor geometric interrelation between the gamma radiation detecting devices and the visible light cameras coupled or related to the former.
    DESCRIPTION OF THE INVENTION
    A first object of the invention is a system for the volumetric and isotopic identification of the spatial distribution of at least one ionizing radiation from one or a few radioactive sources, or extensive, in radioactive scenes where the system comprises:
    - a gamma radiation detector, to generate an electrical signal proportional to the energy of the ionizing radiation, and comprising collimation mechanisms intended to obtain directional information of the radioactive scene, and
    - an optical transducer in solidarity with the gamma radiation detector to capture images of the radioactive scene.
    More specifically, the system comprises:
    - a control unit that links the gamma radiation detector with the optical transducer,
    wherein the control unit comprises:
    - a microprocessor, and
    - a memory, linked to the microprocessor, and comprising:
    or positioning instructions for:
    ■ define an initial image of the radioactive scene captured by the optical transducer,
    ■ detect at least one visual reference in the initial image,
    ■ determine the initial orientation of the gamma radiation detector with respect to that visual reference,
    ■ detect the absolute position of the system with respect to the reference
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    visual of the initial image in a succession of locations, from successive images to the initial image, and
    ■ to determine the orientation of the gamma radiation detector for each location within the radioactive scene, and
    or measurement instructions for:
    ■ perform measurements of ionizing radiation, using the gamma radiation detector, at each system location within the radioactive scene,
    ■ relate these measurements of ionizing radiation to the absolute position obtained by positioning instructions,
    ■ establish the spatial distribution of the measures of ionizing radiation in the radioactive scene forming a three-dimensional matrix in the form of sub-volumes where each subvolume region comprises a value proportional to the intensity of its radiation, and
    ■ characterize ionizing radiation according to the value of the electrical signal produced by the transducer according to the photopic to determine its isotope composition.
    Collimation mechanisms comprise a structure with segmenters to detect the direction of ionizing radiation from the radioactive source at each system location. In addition, to detect the direction of ionizing radiation, the control unit incorporates instructions for calculating incident radiation trajectories, such as collimation techniques or Compton techniques.
    More specifically, the structure with segmenters and / or collimation techniques, allow the control unit to obtain a three-dimensional, cone-shaped measurement field of ionizing radiation from information from the gamma radiation detector. Since the gamma radiation detector is integral with the optical transducer, the control unit can relate the measurement range of the gamma radiation detector to a field of view of the optical transducer by solving one. In this way several of the prior art problems mentioned above and related to the
    disparity between gamma radiation detecting devices and optical transducers
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    in terms of resolution and calibration methods between them.
    From the measurements made by the gamma radiation detector in the different positions, the spatial distribution of the radioactive activity is obtained.
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    This radioactive activity is considered as the intensity factor of the gamma radiation detector, and is determined by the ability of the gamma radiation detector to associate each photopic of each known energy with an acceptance value. Additionally, the relationship between the distance and the intensity of the radioactive source (which decreases with the square of the distance) allows the intensity of it to be evaluated and its absolute position with respect to the system or a visual reference.
    The optical transducer is a visible light camera, or a depth or contour camera.
    15 The control unit comprises the projective characteristics of the optical transducer, that is to say its equation and associated parameters, which allows its calibration to be performed. The usual way to obtain this equation is by means of two matrices. The first matrix corresponds to the internal characteristics of the lens aperture and the size of the optical sensor and, unless the lens or focal lens is changed, is fixed. The second matrix corresponds to the 20 internal translations. This calibration includes obtaining the equation of the optical transducer which in turn allows connecting lines in space with points in the image. This vision technique is also known as projective image.
    Said control unit, through the images of the visual reference in the radioactive scene 25 of the optical transducer, allows to obtain in each measurement made by the gamma radiation detector the relative position of the system with respect to its previous positions and identify the location (not known) of the radiation source by successive measurements or displacements of the system.
    Preferably, the visual reference is a fiducial mark of dimensions, or size, preset and positioned by a user in the radioactive scene within the field of view of the optical transducer, so that when it makes the initial image the fiducial mark is comprised in That initial image. It should be noted that throughout the succession of locations, and therefore measurements, this fiducial mark can be placed in another
    position, or overlap with other fiducial marks. In this way, more than one fiducial mark can be used in the same radioactive scene, allowing the control unit to detect the absolute position of the system, or of the radioactive source, with respect to any of these fiducial marks or even with respect to several of them.
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    Thus, when the optical transducer is a visible light chamber, it is necessary to enter the value of the dimensions, or size, of the fiducial mark, in the control unit so that it can determine the distances between the system and the fiducial mark by means of positioning instructions included in the memory and executed by the microcontroller.
    In this case, to modify the position of the fiducial mark, the control unit registers in its memory the image where the fiducial mark is in one of the limits of the field of vision of the optical transducer and relates it to all previous images where the fiducial mark 15 was visible. Subsequently, and maintaining the position of the system, the fiducial mark is moved, for example, by the user, to the opposite limit of the field of vision of the optical transducer. The control unit considers this position as a position in solidarity with the previous position, that is to say, it continues with the location of the system and therefore allows measurements to be taken continuously.
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    However, when the optical transducer is the contour chamber, it provides the projected distances, and therefore it is not necessary for the fiducial mark dimensions to be known. The movement of successive three-dimensional contour translations between shot and shot can be obtained.
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    In this case, when the optical transducer is the contour camera, the visual reference is a recognizable object within the radioactive scene. In this way, the control unit establishes a first recognizable object that, when due to the movement of the system, is at the limit of the field of vision of the optical transducer, is replaced by a second recognizable object that is at the opposite limit. of the field of view of the optical transducer. This operation allows the system to continue with the measurements in a continuous way.
    Additionally, the memory of the control unit comprises first sub-instructions that determine the sub-volumes:
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    Xr ¥, E - Dx ■ í I- Xa.Dy ■ J -t- Yo.Di ■ fc-t-JBn
    Where:
    • X, Y, Z: are the spatial coordinates of each sub-volume (cm), called LOC_X.
    • i, j, k: are integers that identify the position of the voxel (three-dimensional point)
    • Dx, Dy, Dz: are integer values that represent the distance between the spatial coordinates between one voxel and the next.
    • Xo, Yo, Zo: are the initial spatial coordinates of the voxel (cm).
    Likewise, the memory of the control unit comprises in the measurement instructions some second sub-instructions that measure the radiation for each sub-volume according to:
    B = I- + Ee
    Where:
    • E, is the energy factor (Ke),
    • I, is the value of the signal measured in the detector (V),
    • CAL_E, is the scale factor that relates the detector signal to energy (Ke / V),
    • Eo, is the energy value when the detector signal is 0 (Ke).
    Also, the memory of the control unit comprises in the measurement instructions some third sub-instructions that relate the sub-volumes to the energy factor to obtain the radioactive intensity factor (FI) of each sub-volume, by means of the following equation:
    FI = E (LOC _X, POSE_D (t)) • E ((POSE_D (t) - LOC _X) 2) • EFF_C (E) • FC
    where:
    In
    • E (LOC_X, POSE_D (t)), is the known efficiency factor of the gamma detector and in this case it depends on the orientation of the gamma radiation detector, and its construction,
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    E ((POSE_D (t) - LOC _X) 2), is the efficiency factor relative to the distance that relates the relative distance between the position of the radioactive source with each sub-volume of the measurement,
    EFF_C (E), is the factor that determines the efficiency of the gamma radiation detector of
    obtain a signal for each photopic of a given energy, and
    FC. are additional factors referred to the gamma detector obtained by means of
    calibration.
    A second aspect of the invention describes a method for the isotopic and volumetric identification of the spatial distribution of an ionizing radiation from point (or extensive) radioactive sources in radioactive scenes, by the system described in the first aspect of the invention.
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    More specifically, the method comprises the following stages:
    a) determine an initial location of the system in the radioactive scene,
    b) establish a measurement region within the field of vision of the optical translator in the radioactive scene so that it includes at least the visual reference,
    c) obtain, by means of the positioning instructions, an initial image of the measuring region of the radioactive scene, by means of the optical transducer and obtain the initial orientation of the gamma radiation detector,
    d) determine, by means of the positioning instructions, the initial absolute position of the system with respect to the visual reference,
    e) modify, at least once, the system position and perform the following steps for each succession of positions after the initial position:
    I. carry out, through the optical transducer and positioning instructions, a succession of successive images to the initial image,
    II. perform, by means of the measurement instructions and the gamma radiation detector, radiation measurements in the radioactive scene,
    III. generate, by means of the control unit, a measurement volume in the image to project the radiation measurements by generating subvolumes,
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    IV. determine the three-dimensional coordinates that determine the subvolumes and relate them to the measurements of the radioactive scene using the control unit,
    V. establish, by means of the measurement instructions, a value greater than zero for each sub-volume and that in each succession of positions will be increased (for each sub-volume) where radioactive intensity is detected and will be decreased (again, in each sub -volume) where radioactive intensity is not detected, and
    SAW. characterize the ionizing radiation according to the value of the electrical signal produced by the transducer according to the photopic to determine its isotope composition.
    The location determination of the system in the radioactive scene is carried out by means of the equation and parameters of the optical transducer.
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    More specifically, the measuring region of the radioactive scene is within the field of vision of the optical translator.
    It should be noted that, if the orientation of the gamma radiation detector is in the field of vision of the optical translator, the control unit merges both information, although the object of the invention is to be able to quantify the radioactive scene with quality by precise location of the sensor.
    The detection field of the gamma radiation detector is also defined by a projective image. This means that each point of the image of the gamma radiation detector on a line that contains all the possible points that connect the gamma radiation detector with the image. These imaginary cones or lines are known as epipolar, or activity cones, depending on whether it refers to geometric aspects or to regions of contamination determined by said epipolar regions. In this way, the detection field of the gamma radiation detector is transformed into a measurement volume by means of a cartography comprising the movement and orientation of the camera, where this position in space is called POSE (t) and is a value that depends on time, since the position varies in time. It should be noted that the POSE (t) also comprises the POSE_X (t), which comprises the position of the system, and the POSE_D (t), which in turn comprises the orientation of the detector of
    gamma radiation
    In this way, the control unit considers the measurement volume as in a region of the space of the radioactive scene where it is possible that radioactive sources exist, and it pixels it, voxelizes, or discretizes, forming a three-dimensional matrix in the form of sub-volumes comprised in a detection cone, where the control unit provides each sub-volume with an initial value greater than 0, which will subsequently be increased in each sub-volume where radioactive intensity is detected and will be decreased in each sub-volume where do not detect radioactive intensity, allowing the volumetric identification of the spatial distribution of an ionizing radiation from radioactive sources in a fast and direct way.
    That is, as the system moves and takes a succession of measurements, the sub-volumes that receive a higher radioactive incidence within the measurement volume 15 will increase their value, facilitating the detection of the radioactive source in a dynamic way and in real time.
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    More specifically to perform said voxelization, the control unit applies the following three-dimensional coordinates that determine the sub-volumes:
    C, Y, Z = ñs-t + Ko, ■ / -t- Yej Bz ■ faith 4- 2a
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    Where:
    • X, Y, Z: are the spatial coordinates of each sub-volume (cm), called LOC_X.
    • i, j, k: are integers that identify the position of the voxel
    • Dx, Dy, Dz: are integer values that represent the distance between the spatial coordinates between one voxel and the next.
    • Xo, Yo, Zo: are the initial spatial coordinates of the voxel (cm).
    Specifically, these coordinates are included in the first sub-instructions of the measurement instructions of the control unit memory.
    In this way, the control unit measures the radiation for each sub-volume of the cone
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    generated by the gamma radiation detector, and relates the radiation to each coordinate for each sub-volume of the cone. Thus, the control unit considers radiation as an energy factor that generally depends on the following equation.
    K = í- CAL_E + So
    • Where:
    • E, is the energy factor (Ke),
    • I, is the value of the signal measured in the detector (V),
    • CAL_E, is the scale factor that relates the detector signal to energy (Ke / V),
    • Eo, is the energy value when the detector signal is 0 (Ke).
    Specifically, this energy equation is comprised in second sub-instructions of the measurement instructions of the control unit memory.
    Finally, the control unit relates the sub-volumes to the energy factor to obtain the radioactive intensity factor (FI) of each sub-volume, using the following equation:
    FI = E (LOC _X, POSE_D (t)) • E ((POSE_D (t) - LOC _X) 2) • EFF_C (E) • FC
    where:
    In
    • E (LOC_X, POSE_D (t)), is the known efficiency factor of the gamma detector and in this case it depends on the orientation of the gamma radiation detector, and its construction.
    • E ((POSE_D (t) - LOC _X) 2), is the efficiency factor relative to the distance that relates the relative distance between the position of the radioactive source with each sub-volume of the measurement.
    • EFF_C (E), is the factor that determines the efficiency of the gamma radiation detector in obtaining a signal for each photopic of a given energy.
    • FC, are additional factors related to the gamma detector obtained through calibration.
    It should be noted that, although the invention has been described in a radioactive scene, this system
    and method can be applied to any determination where precision measurements of the intensity of a radioactive source used in other purposes are required, such as the medical, industrial sector in the generation of isotopes, monitoring of material misuse, security surveillance.
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    The main advantage of this system and method is the possibility of allowing continuous movement of the system and taking it into account during each measurement of radioactivity. By incorporating the information of the initial position of the system, and having a real-time mechanism of knowledge about the orientation of the gamma radiation detector for each measurement, it is possible to integrate into the solution of the determination of the radioactive scene, facilitating an aggregation Continuous real-time data.
    In addition, during the acquisition of the measurements, the system allows its connection, through a communications port included in the control unit, with a display device that allows the radioactive scene to be reproduced in two or three dimensions, to sample and explore the regions of interest more interesting while in real time the distribution of radiation is detected. In this way the system allows to obtain higher quality measurements since the user, manually or automatically, can choose the following positions of the system from the level of previous radiation reproduced in the display device.
    On the other hand, the system has advantages in terms of the preparation of the radioactive scene to be characterized, requiring a minimum intervention by additional personnel to the incorporation of previously calibrated sensors.
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    DESCRIPTION OF THE DRAWINGS
    To complement the description that is being made and in order to help a better understanding of the characteristics of the invention, according to a preferred example of practical implementation thereof, a set of said description is attached as an integral part of said description. Drawings where, for illustrative and non-limiting purposes, the following has been represented:
    Figure 1.- Shows a schematic view of a first preferred embodiment.
    Figure 2.- Shows a schematic view of a second preferred embodiment.
    PREFERRED EMBODIMENT OF THE INVENTION
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    A first preferred embodiment of the invention, as shown in Figure 1, is a system (10) for the isotopic volumetric and isotopic identification of radioactive sources (3) point, or extensive, in a radioactive scene, where the system (10) comprises:
    - a gamma radiation detector (2) to generate an electrical signal proportional to the
    10 energy of ionizing radiation from the radioactive source (3), and that
    it includes collimation mechanisms intended to obtain directional information from the radioactive source (3),
    - an optical transducer (1) such as a visible camera integral with the gamma radiation detector (2) to obtain images or videos of the radioactive scene.
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    More specifically, the system (10) comprises:
    - a control unit linked to the gamma radiation detector (2) and the optical transducer (1) comprising a microprocessor and a memory, wherein the microprocessor is linked to the memory which in turn comprises
    20 positioning instructions and measurement instructions to detect from
    of the images of the radioactive radioactive scene at least one visual reference such as a fiducial mark (4), arranged in a fixed position and in view of the visible chamber, and to determine the direction of origin of the ionizing radiation by successive measurements quantifying the intensity of ionizing radiation.
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    Specifically, thanks to this fiducial mark (4) the control unit obtains the position and orientation of the system (10), with respect to the radioactive scene while the system (10) moves.
    Preferably, the system (10) will be positioned in different locations whose coordinates are defined by said positioning instructions. The following position of the optical transducer (1) is calculated by measuring the variation of position and orientation with respect to the same fiducial mark (4). This position variation is rigidly transferred to the gamma radiation detector (2) as it is integral to the visible chamber (1). The new orientations
    determine with precision radioactive source (3). Successively, the radioactive scene is measured by the displacement of the system (10).
    The measurements obtained by gamma radiation detector (2) give information about the intensity of the radioactive source (3) since, by means of the control unit, the distance and intrinsic energy efficiency of the gamma radiation detector (2) is known ). Additionally, by means of the control unit it is possible to calculate the distance between the system (10) and the radioactive source (3) since the intensity of the radioactive is inversely proportional to its distance from the radioactive source (3) squared.
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    In this way, the control unit with at least two positions obtained from two different places, detects the three-dimensional position of the radioactive source (3) with respect to the fiducial mark (4) by means of the positioning instructions included in the unit's memory of control.
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    Said control unit thanks to these data obtained from the gamma radiation detector (2) and the optical transducer (1) can reconstruct a three-dimensional image showing the spatial distribution of ionizing radiation.
    A second preferred embodiment of the invention, as shown in Figure 2, the system (10) comprises the optical transducer (1) which is a depth or contour chamber integral with the gamma radiation detector (2), being both linked to the control unit. Thus the difference between the first preferred embodiment and the second preferred embodiment is the type of optical transducer (1).
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    This depth or contour chamber is capable of obtaining the contour of nearby objects and obtaining three-dimensional information about the surface of neighboring objects or in the scope of the contour chamber. The complexity of obtaining the different locations is compensated by not requiring prefabricated fiducial marks (4), with the contour of the scene being that of the fixed spatial reference.
    In this second preferred embodiment, the contour itself detected by the depth or contour chamber is used as a visual reference, since the movement of the system (10) can be recalculated by identifying different objects. Additionally, the information in this
    The contour can be combined with the gamma camera information (2) and again determine the distance to the radioactive source (3) and its position with respect to the system (10) using the positioning instructions included in the memory of the control unit .
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    权利要求:
    Claims (12)
    [1]
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    R E I V I N D I C A C I O N E S
    1.- System (10) for the volumetric and isotopic identification of the spatial distribution of an ionizing radiation from at least one point, or extensive radioactive source (3) in radioactive scenes where the system (10) comprises:
    - a gamma radiation detector (2), for generating an electrical signal proportional to the energy of the ionizing radiation, and comprising collimation mechanisms intended to obtain directional information of the radioactive scene, and
    - an optical transducer (1) linked to the gamma radiation detector (2) to capture images of the radioactive scene,
    wherein the system (10) is characterized in that the gamma radiation detector (2) is integral with the optical transducer (1) and that the system (10) comprises a control unit which in turn comprises:
    - a microprocessor, and
    - a memory linked to the microprocessor, and comprising:
    or positioning instructions for:
    ■ define an initial image of the radioactive scene captured by the optical transducer (1),
    ■ detect at least one visual reference in the initial image,
    ■ determine the initial orientation of the gamma radiation detector (2) with respect to said visual reference,
    ■ detect the absolute position of the system (10) with respect to the visual reference of the initial image in a succession of locations, from successive images to the initial image, and
    ■ to determine the orientation of the gamma radiation detector (2) for each location within the radioactive scene, and
    or measurement instructions for:
    ■ perform measurements of ionizing radiation, using the gamma radiation detector (2), at each system location (10) within the radioactive scene,
    ■ relate these measures to the absolute position obtained through the positioning instructions,
    ■ establish its spatial distribution in the radioactive scene by forming
    a three-dimensional matrix in the form of sub-volumes where each sub-volume region comprises a value proportional to the intensity of its radiation, and
    ■ characterize the ionizing radiation according to the value of the electrical signal 5 produced by the transducer according to the photopic to determine its
    Isotope composition.
    [2]
    2. - System (10) according to claim 1, characterized in that the collimation mechanisms comprise a structure with segmenters to detect the radiation direction
    10 radioactive source ionizer (3) at each system location (10).
    [3]
    3. - System (10) according to claim 1, characterized in that the control unit comprises in the memory detection instructions comprising collimation techniques such as compton techniques to detect the direction of the ionizing radiation of the source
    15 radioactive (3) at each system location (10).
    [4]
    4. - System (10) according to any one of the preceding claims, characterized in that the optical transducer (1) is a visible light chamber.
    20 5. System (10) according to any one of the preceding claims, characterized in that
    The visual reference is a fiducial mark (4) positioned by a user in the radioactive scene.
    [6]
    6. - System (10) according to any one of claims 1 to 3, characterized in that the optical transducer (1) is a depth or contour chamber.
    [7]
    7. - System (10) according to claim 6, characterized in that the visual reference is an object of dimensions, or size, preset and located within the radioactive scene and within the depth chamber field in its initial potion.
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    [8]
    8. - System (10) according to any one of claims 1 to 7, characterized in that the memory of the control unit comprises first sub-instructions that determine the sub-volumes:
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    Where:
    image 1
    • X, Y, Z: are the spatial coordinates of each sub-volume (cm), called LOC_X.
    • i, j, k: are integers that identify the position of the voxel
    • Dx, Dy, Dz: are integer values that represent the distance between the spatial coordinates between one voxel and the next.
    • Xo, Yo, Zo: are the initial spatial coordinates of the voxel (cm).
    10. System (10) according to claim 8, characterized in that the memory of the unit of
    control comprises in the measurement instructions some second sub-instructions that measure the radiation for each sub-volume according to:
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    Where:
    • E, is the energy factor (Ke),
    • I, is the value of the signal measured in the detector (V),
    • CAL_E, is the scale factor that relates the detector signal to energy (Ke / V),
    • Eo, is the energy value when the detector signal is 0 (Ke).
    [10]
    10. System (10) according to claim 9, characterized in that the memory of the control unit comprises in the measurement instructions comprises third sub-instructions that relate the sub-volumes to the energy factor to obtain the factor of Radioactive intensity (FI) of each sub-volume, using the following equation:
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    FI = E (LOC _X, POSE_D (t)) • E ((POSE_D (t) - LOC _X) 2) • EFF_C (E) • FC
    where:
    In
    • E (LOC_X, POSE_D (t)), is the known efficiency factor of the gamma detector and in this case it depends on the orientation of the gamma radiation detector (2), and its construction,
    5
    10
    fifteen
    twenty
    25
    30
    • E ((POSE_D (t) - LOC _X) 2), is the efficiency factor relative to the distance that relates the relative distance between the position of the radioactive source (3) with each subvolume of the measurement,
    • EFF_C (E), is the factor that determines the efficiency of the gamma radiation detector (2) in obtaining a signal for each photopic energy, and
    • FC. these are additional factors related to the gamma detector obtained through calibration.
    [11]
    11. Method for the isotopic identification and characterization of the spatial distribution of an ionizing radiation from one or a few radioactive sources (3), or extensive, in radioactive scenes, which uses the system (10) according to any one of the claims above, characterized in that it comprises the following stages:
    a) determine an initial location of the system (10) in the radioactive scene,
    b) establish a measurement region within the field of vision of the optical translator in the radioactive scene so that it includes at least the visual reference,
    c) obtain, by means of the positioning instructions, an initial image of the measuring region of the radioactive scene, by means of the optical transducer (1) and obtain the initial orientation of the gamma radiation detector (2),
    d) determine, by means of the positioning instructions, the initial absolute position of the system (10) with respect to the visual reference,
    e) modify, at least once, the position of the system (10) and perform the following steps for each succession of positions after the initial position:
    i. perform, through the optical transducer (1) and positioning instructions, a succession of successive images to the initial image,
    ii. perform, by means of the measurement instructions and the gamma radiation detector (2), radiation measurements in the radioactive scene,
    iii. generate, by means of the control unit, a measurement volume in the image to project the radiation measurements by generating subvolumes,
    iv. determine the three-dimensional coordinates that determine the subvolumes and relate them to the measurements of the radioactive scene using the control unit,
    v. establish, by means of the measurement instructions, a value greater than zero for each sub-volume that in each succession of positions will be increased in each sub-volume where radioactive intensity is detected and will be decreased in each sub-volume where radioactive intensity is not detected , and 5 vi. characterize ionizing radiation according to the value of the electrical signal produced
    by the transducer according to the photopic to determine its isotope composition.
    [12]
    12. Method according to claim 11, characterized in that the memory of the control unit comprises first sub-instructions that determine the sub-volumes:
    fifteen
    twenty
    image2
    Where:
    • X, Y, Z: are the spatial coordinates of each sub-volume (cm), called LOC_X.
    • i, j, k: are integers that identify the position of the voxel
    • Dx, Dy, Dz: are integer values that represent the distance between the spatial coordinates between one voxel and the next.
    • Xo, Yo, Zo: are the initial spatial coordinates of the voxel (cm).
    [13]
    13. Method according to claim 11 or 12, characterized in that the memory of the control unit comprises in the measurement instructions second sub-instructions that measure the radiation for each sub-volume according to:
    25
    30
    a = i ■ + ao
    Where:
    • E, is the energy factor (Ke),
    • I, is the value of the signal measured in the detector (V),
    • CAL_E, is the scale factor that relates the detector signal to energy (Ke / V),
    • Eo, is the energy value when the detector signal is 0 (Ke).
    [14]
    14. Method according to claim 11, 12 or 13, characterized in that the memory of the control unit comprises in the measurement instructions comprises a third sub
    5
    10
    fifteen
    instructions that relate the sub-volumes to the energy factor to obtain the radioactive intensity factor (FI) of each sub-volume, using the following equation:
    FI = E (LOC _X, POSE_D (t)) • E ((POSE_D (t) - LOC _X) 2) • EFF_C (E) • FC
    where:
    In
    • E (LOC_X, POSE_D (t)), is the known efficiency factor of the gamma detector and in this case it depends on the orientation of the gamma radiation detector (2), and its construction,
    • E ((POSE_D (t) - LOC _X) 2), is the efficiency factor relative to the distance that relates the relative distance between the position of the radioactive source (3) with each subvolume of the measurement,
    • EFF_C (E), is the factor that determines the efficiency of the gamma radiation detector (2) in obtaining a signal for each photopic of a given, and
    • FC. these are additional factors related to the gamma detector obtained through calibration.
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    同族专利:
    公开号 | 公开日
    ES2681094B1|2019-10-21|
    EP3581969A1|2019-12-18|
    EP3581969A4|2020-12-16|
    WO2018146358A1|2018-08-16|
    US20200003915A1|2020-01-02|
    US11022705B2|2021-06-01|
    JP2020512565A|2020-04-23|
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    PCT/ES2018/070074| WO2018146358A1|2017-02-10|2018-02-01|System and metod for the volumetric and isotopic identification of radiation distribution in radioactive surroundings|
    US16/484,956| US11022705B2|2017-02-10|2018-02-01|System and method for the volumetric and isotopic identification of radiation distribution in radioactive surroundings|
    JP2019565065A| JP2020512565A|2017-02-10|2018-02-01|System and method for identification of distribution volumes and isotopes in a radioactive environment|
    EP18752001.0A| EP3581969A4|2017-02-10|2018-02-01|System and metod for the volumetric and isotopic identification of radiation distribution in radioactive surroundings|
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