• 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:
    The present invention relates to a method of detecting and/or measuring defects in at least one part. The method includes providing a neutron source that produces a neutron flux, arranging the neutron source such that the neutron flux at least partly penetrates said part, providing a detection device for detecting neutrons, providing a hydrogen containing substance on a surface of said part such that the hydrogen containing substance penetrates into defects in said part, arranging the detection device to detect neutrons from the neutron flux that have been reflected by said substance, and detecting and/or measuring at least one possible defect in said part using the detection device to detect defects by detecting said reflected neutrons.
    公开号:SE1250257A1
    申请号:SE1250257
    申请日:2012-03-19
    公开日:2013-09-20
    发明作者:David Stenman
    申请人:Wesdyne Sweden Ab；
    IPC主号:
    专利说明:

    ring and characterization of defects on surfaces in other contexts.
    The choice of technology depends, for example, on the composition of the material to be examined and the availability of the material.
    A disadvantage of some technologies is that the ongoing process in, for example, the nuclear reactor must be redirected or stopped before the technology can be applied. Some technologies require the disassembly of enclosed parts that need to be measured to provide access to such parts. Other technicians use a device that cannot be moved within the system and require the part to be transported to the device. This makes it impossible to identify defects during ongoing operations. Most technicians use space-consuming equipment, which does not allow measurements in confined spaces.
    Only a few technicians can measure through materials. X-ray and ultrasound measurements are techniques that are often used to measure and detect defects through materials. However, these techniques depend on the composition of the material in the part. These techniques are not particularly suitable for materials such as stainless steel and concrete.
    There is a need for a method that is insensitive to the composition of the material from which the part to be measured is made.
    There is also a need for a method which enables measurement and / or detection of defects in a part of, for example, a nuclear power plant during ongoing operations of the plant. There is also a need for a method which can detect and / or measure defects in one part enclosed in another part and a method which can suitably be used in a cramped space inside the plant.
    SUMMARY OF THE INVENTION An object of the present invention is to provide a method for measuring and / or detecting defects during quality and safety checks of parts, which are used where other techniques such as X-ray and ultrasonic measurements cannot be used. Another object is the provision of a method which is less sensitive to the composition of the material of which the part to be measured is made. A further object is the provision of a method that can be used during an ongoing operation in an industrial plant, such as a nuclear power plant.
    The method preferably enables measurement and / or detection of defects in parts which are located within another part or which are located in a cramped space. Yet another object is to provide a method that can be used to identify and characterize a change in a defect over time. The objects are achieved by a method defined in claim 1.
    The method of the present invention can be used to measure and / or detect a defect in materials such as stainless steel or concrete, where other techniques cannot be used. As neutrons pass through such materials, the method can be used to measure and / or detect defects in the part enclosed within another part such as a part enclosed by concrete. No disassembly of the part is needed before a measurement can be performed. Furthermore, the method can be used regardless of the thickness of the material in the part to be measured. The method can be used to advantage during an ongoing operation in an industrial plant such as a nuclear power plant.
    In one embodiment, the detection device is a mobile detection device, which can be transported between different locations.
    The mobility of the detection device improves the flexibility of the application of the method at different locations of, for example, a nuclear power plant. This improves the efficiency of the quality and safety checks that need to be performed in the plant.
    In another embodiment, the detecting device comprises a scintillator arranged to convert energy from reflected neutrons into light and an image generating device arranged to produce and record at least one image of the possible defect based on the light produced by said conversion of the scintillator. The use of the image generating device, such as a camera, allows accurate recording of the result of the measurement. An additional advantage is that the result can be available quickly after or even during the measurement. In a further embodiment, the image generating device provides a sequence of images from the part to identify and characterize a change of a possible defect in the part. Some defects on or in the surface of the part to be measured change over time. For example, a crack in the surface may result from a minor scratch on the surface of the part. It is therefore interesting to measure changes in defects over time. The method according to the present invention can thus be used for both static and dynamic analysis of the defect in the part. In one embodiment, the sequence of images is taken for a period of at least 24 hours, preferably at least 7 days, more preferably at least 30 days.
    In one embodiment, a control unit is provided and set up to control at least one of the neutron source or detection device. The handling of the various devices is preferably coordinated. The use of the control unit enables such coordination and will thus improve the efficiency of the measurement and / or detection of defects in one or more parts.
    In another embodiment, the neutron source is a mobile neutron source, which can be transported between different locations. The mobility of the neutron source will improve the efficiency of the quality and safety controls.
    In a further embodiment, the neutron source is a linear accelerator. Linear accelerators are commercially available in various sizes and can be easily implemented in the method according to the invention.
    In an alternative embodiment, the neutron source is provided by a nuclear fuel of a nuclear power plant. If neutrons are available from the nuclear fuel, these neutrons can be used effectively in the method. In this case, no separate neutron source is needed. This makes it easier to implement the method according to the invention and costs can be reduced.
    In one embodiment, the hydrogen-containing substance is water.
    Neutrons are reflected by hydrogen atoms. It is therefore important that the substance contains hydrogen atoms. Water is rich in hydrogen atoms and water is used in many industrial plants, such as a nuclear power plant, or is otherwise easily accessible at the plant. The water can be in liquid form or gaseous form.
    In another embodiment, the part is made of stainless steel and / or concrete.
    In yet another embodiment, the part is located within another part made of cast stainless steel. Since neutrons penetrate through materials such as stainless steel and concrete, the method can be advantageously used to measure and / or detect defects in the part made of such materials or in the part enclosed in such materials.
    In one embodiment, the defect is an irregularity in the surface of the part.
    In another embodiment, the irregularity is a crack in the surface of the part. The method of the present invention enables the detection of hydrogen atoms present at or in the surface of the part.
    Therefore, any type of defect at or in the surface of the part can be measured using the method of the present invention. In another embodiment, the method is used for detecting and / or measuring defects in a part that is used or that has been used or that is designed for use in a nuclear power plant. In a further embodiment, the method is used in a nuclear power plant.
    BRIEF DESCRIPTION OF THE DRAWINGS Fig. 1 shows a flow chart of a method according to the invention. Fig. 2 shows schematically how the method according to the invention can be carried out. Fig. 3 shows an example of a detection device and control unit. 5 shows a schematic view containing a crack in a pipe filled with water.
    DETAILED DESCRIPTION OF THE INVENTION Devices and materials for use in the method according to the UDD invention As an example, the following description will describe the invention for detecting and / or measuring defects in a part of a nuclear power plant. However, as stated above, the invention can be applied to any other part.
    Fig. 2 shows a neutron source 1 which produces a neutron flux 2.
    The neutron flux 2 is directed towards a part 3, such as a tube or a base bed. The neutrons 2a of a neutron flux 2 penetrate at least partially through the part 3. When the neutrons hit hydrogen atoms on their way, the neutrons will be reflected. The reflected neutrons 4 can be detected by a detection device 5.
    The neutron source 1 can be a linear particle accelerator (linac). A linac is a type of particle accelerator that greatly increases the velocity of charged subatomic particles or ions by exposing the charged particles to a series of oscillating electrical potentials along a linear radius. The linear accelerator uses microwave technology to accelerate electrons in a part of the accelerator called a “waveguide”. It then allows these electrons to collide with a heavy metal target. As a result of the collisions, high-energy neutrons are produced from the target. Suitable heavy metal targets may be tungsten, uranium, gold, lead, beryllium, mercury and the like, or combinations thereof. Depending on the energy of the neutrons, the neutrons can be slow, such as thermal neutrons, or fast. Linacs are known and commercially available from, for example, Toshiba or Radia-Beam Technologies.
    Linacen is available in different sizes. For the method of the present invention, a linac having a length of one to two meters is preferably used. This gives the possibility to transport the neutron source 1 between different locations or between different areas in the nuclear power plant and to use the method in confined spaces.
    In some cases, it may be possible to use the neutron flux 2 produced by the nuclear power plant's nuclear fuel as the neutron source 1.
    The neutron flux 2 produced by the nuclear fuel may be present in, for example, pipes and basins in the nuclear power plant. When measuring and / or detecting defects on such parts 3, there is no need for an additional neutron source 1.
    Alternatively, the neutrons can be produced by a neutron source in the form of a liquid medium, such as water, and then applied to the part 3 in which any defects are to be measured and / or detected. For this purpose, a radioactive material in gaseous, liquid or solid form may be added to a fluid medium. This fluid medium with radioactive material can then be injected onto the surface of the part 3. The agent can be injected as a beam of neutrons focused on a particular area on the surface of the part 3. This allows the beam to be focused from different angles relative to the surface of the part 3.
    The neutron flux 2 produced by the nuclear fuel or by means of the fluid medium can also be diffuse as long as the neutrons produce sufficient light in the detection device 5 used for the measurement and / or the detection. Examples of diffuse neutron sources can be neutrons arising from a leak in the nuclear fuel or neutrons arising from nuclear waste.
    Neutrons 4 reflected from hydrogen atoms present in part 3 can be detected and visualized using a detection device 5. Such a device 5 enables detection and registration of a 2-dimensional image of the part 3. However, the neutron is not directly detected as light in a regular camera. A converter called a scintillator 6 can be used to convert neutrons to light and this light can then be detected with an image generating device 7, 8, 9, 10, such as a camera or a digitizing device which can detect light. The camera can be an analogue or a digital camera.
    Fig. 3 shows an example of a detection device 5. Reflected neutrons 4 are incident on a scintillator 6. The light from the scintillator 6 can then be reflected by a mirror 7 in a light box 8 and transmitted to a camera lens 9. By means of a CCD chip, such as a Peltier-cooled CCD chip, an image can be produced and recorded, for example, by using a computer 11. A screen 12 and input means 13, such as a keyboard, can also be used. The various devices and apparatus can be controlled by a control unit 14.
    The control unit 14 can be used in carrying out the method. Such a unit 14 can be used to control the neutron source 1 and the detection device 5, which may comprise the scintillator 6, the image generating device 7, 8, 9, 10, the computer 11, the screen 12 and the input means 13. The various devices may be connected by means of cables 15. or the connections may be wireless.
    Scintillators 6 are materials that transfer energy from a neutron to light. For scintillation purposes, the neutron must first transfer some or all of its energy to a charged atomic nucleus. The positively charged core then produces ionization. Various methods are available to carry out this reaction. For example, fast neutrons (generally> 0.5 MeV) are primarily dependent on the recoil proton in (n, p) reactions. Materials that are hydrogen rich, e.g. plastic scintillators 6, are therefore best suited for their detection. Slow neutrons depend on nuclear reactions such as the (n, y) or (n, oQ reactions to produce ionization.
    For this purpose, the scintillator material 6 is loaded with elements having a high cross-section for these nuclear reactions such as 6Li or 108. Materials such as glass silicate are particularly good for detecting slow (thermal) neutrons.
    Various scintillators 6 can be used in the method according to the invention. The choice may, for example, depend on the amount of radiation used at the site of part 3 to be measured. Examples of suitable scintillators 6 are liquid organic scintillators, crystals, plastics and scintillation fibers.
    The image generating device 7, 8, 9, 10 produces and registers at least one image of the possible defect based on the light produced by the conversion of the scintillator 6. To capture the image of the light created by the scintillator 6, different types of devices can be used . An example is a charge coupled device (CCD) camera with a photographic focusing lens 9 of normal photographic quality. Since most electronic devices are sensitive to radiation damage, it is necessary to protect the image generating device 7, 8, 9, 10 from neutron radiation 2, 4. The CCD device can be easily protected by mounting it outside the neutron radiation 2, 4. The focusing lens 9 forms a image on the CCD of the light image formed on the scintillator screen 7. Another device that can be used is an amorphous silicon detector. This type of device is resistant to radiation damage.
    Neutron detection devices are commercially available, for example from Toshiba or Medway Technologies. Preferably, the detection device 5 is efficient, fast and sensitive.
    Noise that may be present in the images can be removed by using noise reduction measures used in the shooting area. The noise is preferably removed without affecting the measured signal.
    The detection device 5, or at least the scintillator 6 and the image generating device 7, 8, 9, 10 used in the method according to the present invention, are preferably movable so that it can be transported to different parts 3 located at different locations of the nuclear power plant.
    According to the method of the present invention, the neutron source 1 and the detection device 5 are arranged so that the reflected neutrons 4 from the neutron flux 2 can be detected (Fig. 2). Those skilled in the art will understand how to arrange the neutron source 1 and the detection device 5 in each individual situation where the possible defect is to be measured.
    Neutrons 4 are reflected by hydrogen atoms from hydrogen-containing substances. It is therefore important for the method that such substances are present at or in part 3 to be measured. Examples of hydrogen-containing substances are water, oils, waxes, lubricants and the like. Mixtures of two or more hydrogen-containing substances can also be used. The hydrogen-containing substance (s) may be in any physical form such as gas, liquid, solid or even any mixture thereof. In a preferred embodiment, water is used in liquid form or as a gas.
    The part 3 to be measured may, for example, be a wall of a pipe or a basin, or a valve, a baffle, a pump housing or a sealing ring. The part 3 may be located within another part 3 such as a pipe inside a concrete casing. The method according to the invention can be used regardless of the thickness or granularity of the material of which the part 3 is composed.
    The method according to the invention Fig. 1 shows a flow chart of a method according to the invention.
    The method comprises the steps of: - providing a neutron source 1 producing a neutron flux 2, - arranging the neutron source 1, so that the neutron flux 2 at least partially penetrates the part 3, - providing a detecting device 5 for detecting neutrons, - providing a hydrogen-containing substance on a surface of said part 3, so that the hydrogen-containing substance penetrates into defects in said part 2, - arranging the detecting device 5 for detecting neutrons from the neutron flux 2 which has been reflected by said substance, and - detecting and / or measuring at least one possible defect in said part 3 by using the detecting device 5 to detect defects by detecting said reflected neutrons 4.
    The method can be used during routine inspections of various parts 3 located in the nuclear power plant. The method can also be used outside the nuclear power plant to measure and / or detect a possible defect in part 12 that has been manufactured but not yet installed. After repair or installation of part 3, but before part 3 is used, the method can also be used.
    Different types of defects can be found in part 3. The present invention is not limited to any type or size of defect and can be used for any irregularity in the surface of part 3. Figs. 4a and 4b show examples of irregularities in a wall 3a of a part 3 as a tube. Fig. 4a shows a crack and Fig. 4b shows a scratch in the surface of the wall 3a. More than one defect may be present in Part 3.
    The hydrogen-containing substance will enter the defect in the surface of part 3. For example, by capillary action, the substance will be sucked into a crack in the surface of part 3. Neutrons from a neutron flux 2 directed towards such a defect will be partially reflected by the hydrogen atoms present in the crack. These reflected neutrons 4 can be visualized by using the detection device 5. Since the hydrogen atoms in the defect will reflect the neutrons, the method provides the possibility of detecting very small defects. The precision of the method can be such that the design or shape of the defect can also be visualized.
    The hydrogen-containing substance in the produced image will be in clear contrast to other materials in part 3. An example is shown in Fig. 5, where a crack in the wall 3a of a tube 3 can be seen. The pipe 3 is filled with (running) water. Although the method can be used in parts 3 which are filled with a water-containing substance, such as water, it may be advantageous in some cases to empty the part 3 before the method according to the invention is applied. After emptying, a hydrogen-containing substance is arranged on the surface of the part 3, after which the possible defect can be detected and / or measured. This emptying of part 3 can improve the quality of the results obtained. To detect and / or measure possible defects in a part 3, the hydrogen-containing substance can also be applied to the surface of the part 3 by applying the substance for a short period of time and then removing the substance from the surface. The substance will remain inside the surface defects, such as cracks, and can be detected and / or measured. The substance may be liquid or gas, such as pressurized gas.
    The method can be repeated by providing a hydrogen-containing substance on the same surface repeatedly over time.
    By detecting and / or measuring the same defect once a week or once a month, changes in the defects can be identified and characterized.
    Defects, such as a scratch, can also be detected because the distribution of hydrogen atoms from the hydrogen-containing substance at and around the surface of the scratch will be different compared to the distribution of hydrogen atoms at the flat (non-defective) surface.
    A change in the distribution of the neutron scattering intensity around the scratch will be visible on the detector.
    Another alternative is to measure a possible defect in a material by bending and stretching the material before the hydrogen-containing substance is applied. The hydrogen-containing substance will enter a possible defect in the part during stretching and bending of the material. The hydrogen atoms in such defects will reflect neutrons and can thus be detected.
    The type of information that can be obtained can be useful in predicting changes in defects over time. Other valuable information refers to information about the size and type of defect.
    Both static and dynamic analysis of the defect can be performed using the method of the present invention. The present invention is not limited to the described embodiments but may be varied and modified within the scope of the following claims.
    权利要求:
    Claims (16)
    [1]
    A method for detecting and / or measuring defects in at least a part (3), the method comprising the steps of: providing a neutron source (1) which produces a neutron flux (2), arranging the neutron source (1) so that the neutron flux (2) at least partially penetrates said part (3), provide a detection device (5) for detecting neutrons, provide a hydrogen-containing substance on at least one surface of said part (3) so that the hydrogen-containing substance penetrates into possible defects in said part (3), arranging the detecting device (5) so that the detecting device (5) is adapted to detect neutrons from the neutron flux (2) which has been reflected by said hydrogen-containing substance, and to detect and / or measure at least one possible defect in said part (3) by using the detecting device (5) to detect defects containing said substance by detecting said reflected neutrons (4).
    [2]
    The method according to claim 1, wherein the detection device (5) is a mobile detection device (5), which can be transported between different locations.
    [3]
    The method according to claim 1 or 2, wherein the detection device (5) comprises a scintillator (6) arranged to convert energy from reflected neutrons (4) into light and an image generating device (7, 8, 9, 10) arranged to produce and record at least one image of the possible defect based on the light produced by said conversion of the scintillator (6) -
    [4]
    The method of claim 3, wherein the image generating device (7, 8, 9, 10) provides a sequence of images from the part (3) to identify and characterize a change of a possible defect in the part (3).
    [5]
    The method of claim 4, wherein the sequence of images is taken for a period of at least 24 hours, preferably at least 7 days, more preferably at least 30 days.
    [6]
    The method according to any one of claims 1 to 5, wherein a control unit (14) is provided and arranged to control at least one of the neutron source (1) or the detection device (5).
    [7]
    The method according to any one of claims 1 to 6, wherein the neutron source (1) is a mobile neutron source (1), which can be transported between different locations.
    [8]
    The method according to any one of claims 1 to 7, wherein the neutron source (1) is a linear accelerator.
    [9]
    The method according to any one of claims 1 to 6, wherein the neutron source (1) is supplied by a nuclear fuel of a nuclear power plant.
    [10]
    The method of any one of claims 1 to 9, wherein the hydrogen-containing substance is water.
    [11]
    The method according to any one of claims 1 to 10, wherein the part (3) is made of stainless steel and / or concrete.
    [12]
    The method according to any one of claims 1 to 11, wherein the part (3) is located within another part (3) made of cast stainless steel. 10 17
    [13]
    The method according to any one of claims 1 to 12, wherein the defect is an irregularity in the surface of the part (3).
    [14]
    The method of claim 13, wherein the irregularity is a crack in the surface of the part (3).
    [15]
    The method according to any one of claims 1 to 14, wherein the method is used for detecting and / or measuring defects in a part that is used or that has been used or that is designed for use in a nuclear power plant.
    [16]
    The method according to any one of claims 1 to 15, wherein the method is used in a nuclear power plant.
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    法律状态:
    优先权:
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