• 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:
    A device for measuring the density of a fuel rod is disclosed, the device being able to adjust an amount of the irradiation produced by a gamma source that applies gamma rays to the fuel rod. The device includes a shield (110) in which gamma sources of cs-137 (120) are housed adjacent to a fuel rod transport port (111) through which the fuel rod (1) passes, and they inspect defects in the fuel rod. The shield (110) includes shutters (130) that open and close gamma ray guide holes (112) that connect the gamma sources of cs-137 (120) and the fuel rod transport port (111). (Machine-translation by Google Translate, not legally binding)
    公开号:ES2621025A1
    申请号:ES201630207
    申请日:2016-02-24
    公开日:2017-06-30
    发明作者:Lak-min CHOI；Chan Hyun Park；Hyung-sup KIM；Shin-Young Lee；Mun-seog BAEK；Do-in KIM；Seong Yong CHOI
    申请人:Kepco Nuclear Fuel Co Ltd；
    IPC主号:
    专利说明:

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    DESCRIPTION
    Device for measuring the density of a fuel rod
    BACKGROUND OF THE INVENTION FIELD OF THE INVENTION
    The present invention relates to a device for measuring the density of a fuel rod, the device being able to adjust an amount of the radiation produced by each gamma source that applies gamma rays to the fuel rod.
    DESCRIPTION OF THE RELATED TECHNIQUE
    In general, the nuclear fuel used in a reactor is composed of fuel bundles that constitute a fuel element. Each of the fuel bundles is formed by sintering uranium oxide to form a plurality of pads, loading the plurality of sintered pads and a pressure spring in each hollow sheathing tube that is approximately four meters in length and is formed of a Zircaloy alloy, filling the casing tubes with helium gas, and sealing the plugs for the fabrication of fuel rods.
    The fuel rods must be loaded into the reactor after the degree of enrichment, gaps, defects, etc., of the sintered pads inside each of the fuel rods have been previously inspected using a scanner, so that are able to carry out a stable nuclear fission in the reactor; subsequently, defects are eliminated.
    Examples of scanners for inspecting fuel rods may include passive and active scanners available from NDA-TECH Inc. (USA).
    The passive scanner detects defects of a fuel rod by detecting and analyzing the radioactivity emitted from the fuel rod, and does not require a neutron source. However, the passive scanner requires a large size to ensure accurate detection of fuel rod defects, and therefore requires a
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    Excessive space for installation. Consequently, passive scanning is not widely used.
    On the contrary, the active scanner is configured to detect defects of a fuel rod by applying neutrons to the fuel rod using a neutron source and detecting and analyzing the gamma rays emitted by the reaction of the uranium with the neutrons inside the fuel rod; In addition, it is capable of measuring a space between pads, a length of the fuel rod, a length of a pressure spring, etc. using the penetration capacity of a gamma source. The active scanner requires a small space for installation, and has high precision in detecting fuel rod defects. Therefore, the active scanner is widely used.
    Referring to FIG. 1, an active scanner of this type includes a cylindrical shield box 10 formed of lead, a densimeter 12 that is installed in a position of a loading port 11 through which a fuel rod 1 is transported to one side of the cylindrical shield box 10 and measures the length and density of a sintered pellet, a source of Cf-252 13 where the Cf-252 acts as a radiation from a neutron source and is placed inside the cylindrical shield box 10, and a gamma ray detector 14 installed on an external side of the cylindrical shielding box 10 from which the fuel rod 1 is discharged and in which a photodetector, a bismuth and germanium oxide detector (BGO) are housed, etc. to detect gamma rays.
    The fuel rod is loaded into the cylindrical shielding box 10 by means of a fuel rod conveyor (which is not reproduced) disposed in an inlet of the cylindrical shielding box 10; The fuel rod whose inspection has been completed is discharged outside the cylindrical shield box 10.
    The densimeter used in this active scanner uses a Cs-137 source, and is composed of a collimator (1 mm diameter) and a detector. The densimeter detects the amount of gamma rays penetrated after they have been applied to the fuel rod by a gamma source, and measures a space between pads using a density difference between the components housed in the fuel rod.
    However, this active scanner is not separately provided with means capable of
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    adjust the amount of gamma irradiation between the source of Cs-137 used and the fuel rod to be inspected.
    The foregoing is merely intended to help understand the background of the present invention, and is not intended to mean that the present invention falls within the scope of the related technique that is already known to those skilled in the art.
    DOCUMENTS OF RELATED TECHNIQUE Patent document
    (Patent document 1) Korean patent No. 10-0988574 SUMMARY OF THE INVENTION
    Accordingly, the present invention has been made taking into account the above problems that occur in the related art, and the present invention is intended to propose a device for measuring the density of a fuel rod, the device being able to adjust the amount of radiation produced by a gamma source that applies gamma rays to the fuel rod in an active fuel rod scanner.
    To achieve the above objective, according to an aspect of the present invention, a device for measuring the density of a fuel rod for inspecting fuel rod defects is provided. The device includes: a shield in which the Cs-137 gamma sources are housed adjacent to a fuel rod transport hole through which the fuel rod passes, in which the shield includes shutters that open and close the gamma ray holes that connect the gamma sources of Cs-137 and the fuel rod transport hole.
    Here, the gamma ray glide holes are connected vertically to the fuel rod transport hole.
    In addition, the shutters are bars that slide in parallel with the hole of
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    transport fuel rods and open and close the gamma ray glutton holes.
    In addition, the bars are coupled with a separate drive device that is installed outside the shield and is used in a linear motion.
    In the device for measuring the density of the fuel rod in accordance with the present invention, the gamma ray glutton holes are formed in the shield to allow passage between the gamma sources of Cs-137 and the fuel rod that is it will inspect, and the shutters are arranged to open and close the gamma ray glutton holes. In this way, the amount of irradiation produced by each gamma source that applies gamma rays to the fuel rod can be adjusted by adjusting the size of a collimator slot, and the dimension of a space between pads can be measured more precisely. .
    BRIEF DESCRIPTION OF THE DRAWINGS
    The foregoing and other objectives, features and other advantages of the present invention will be more clearly understood from the following detailed description when taken in conjunction with the accompanying drawings, in which:
    FIG. 1 is a perspective view illustrating an active typical fuel bar scanner, of which a part is cut;
    FIG. 2 is a view illustrating a configuration of the main parts of a device for measuring a density of a fuel rod in accordance with the present invention; Y
    FIGS. 3A and 3B are seen to describe an example of operation of the device for measuring the density of the fuel rod in accordance with the present invention.
    DETAILED DESCRIPTION OF THE INVENTION
    The structural and functional descriptions of the embodiments of the present invention disclosed herein are for illustrative purposes only of the embodiments of the present invention. The present invention can be performed
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    in many different ways without departing from the spirit and significant characteristics of the present invention. Therefore, the present invention is intended to cover not only exemplary embodiments, but also several alternatives, modifications, equivalents and other embodiments that may be included within the scope and scope of the present invention as defined by the attached claims.
    It will be understood that, although the terms "first", "second", etc. can be used herein to describe various elements, these elements should not be limited by these terms. These terms are only used to distinguish one element from another element. For example, a first element analyzed below could be called a second element without departing from the teachings of the present invention. Similarly, the second element could also be called the first element.
    It will be understood that when an element is referred to as "coupled" or "connected" to another element, it may be coupled or connected directly to the other element or intermediate elements may be present between them. On the contrary, it should be understood that when an element is referred to as "directly coupled" or "directly connected" to another element, intermediate elements are not present. Other expressions that explain the relationship between elements, such as "between", "directly between", "adjacent to" or "directly adjacent to" should be interpreted in the same way.
    In addition, in the following description of the present invention, a detailed description of the known functions and configurations incorporated herein will be omitted when the subject matter of the present invention can be made unclear. Therefore, the description will focus on a configuration of the main parts associated with the technical characteristics of the present invention.
    Hereinafter, a preferred embodiment of the present invention will be described in detail with reference to the accompanying drawings.
    In reference to FIGS. 2, 3A and 3B, a device for measuring a density of a fuel rod according to the present invention includes a shield 110 in which gamma sources of Cs-137 120 are housed in the vicinity of a busbar transport hole. fuel 111 through which the fuel rod passes. Shielding
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    110 is equipped with shutters 130 that open and close gamma ray glutton holes 112 connecting the gamma sources of Cs-137 120 and the fuel rod transport hole 111.
    Shield 110 may be formed of lead (Pb), which is effective in shielding radioactivity, and may be arranged in a separate shield box with which shield 110 is enclosed. Shield 110 is formed of at least two materials in instead of a single material, and its material, structure and conformation is not limited, provided it can effectively shield radioactivity.
    Cs-137 120 gamma sources are installed in source loading holes so that they are interchangeable in shield 110.
    The fuel rod transport hole 111 is formed in the shield 110 to allow the fuel rod 1 to pass through it in a horizontal direction, and the gamma sources of Cs-137 120 are arranged adjacent to the transport hole of fuel rods 111. In the present embodiment, the gamma sources of Cs-137 120 are arranged above and below the fuel rod transport hole 111, and have the same configuration. Therefore, the following description will focus on the gamma source of Cs-137 120 above.
    To be specific, referring to FIGS. 3A and 3B, the fuel rod transport hole 111 and the gamma source of Cs-137 120 are separated from each other in parallel. The gamma ray glide holes 112 are connected vertically to the fuel rod transport hole 111.
    The shutters 130 can slide in parallel with the fuel rod transport hole 111, and are formed of bars that open and close the gamma ray glide holes 112. Here, each of the bars is formed of tungsten.
    The shutters 130 move linearly. Therefore, according to a quantity of movement, the shutters 130 open or close the gamma ray glide holes 112 or control an amount of opening or closing to adjust an amount of gamma radiation applied to the fuel rod.
    In addition, the shutters 130 may be coupled with a device for
    separate drive that is installed outside the shield and is used for linear movement. This drive device includes a hydraulic or electric actuator. In addition, a driving force can be mechanically transmitted to the shutters.
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    Although a preferred embodiment of the present invention has been described for illustrative purposes, those skilled in the art will appreciate that various modifications, additions and substitutions are possible, without departing from the scope and spirit of the invention as disclosed in the appended claims.
    权利要求:
    Claims (3)
    [1]

    1. A device for measuring the density of a fuel rod to inspect defects in the fuel rod, comprising:
    5 a shield in which the gamma sources of Cs-137 adjacent to a hole are housed
    of transporting fuel rods through which the fuel rod passes, in which the shield includes shutters that open and close the gamma ray glutton holes that connect the gamma sources of Cs-137 and the bar transport hole made out of fuel.
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    [2]
    2. The device according to claim 1, wherein the gamma ray glutton holes are connected vertically to the fuel rod transport hole.
    The device according to claim 2, wherein the shutters are
    bars that slide in parallel with the fuel rod transport hole and open and close the gamma ray glutton holes.
    [4]
    4. The device according to claim 3, wherein the bars are coupled with
    20 a separate drive device that is installed outside the shield and is used for linear motion.
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    同族专利:
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    引用文献:
    公开号 | 申请日 | 公开日 | 申请人 | 专利标题
    GB2138129A|1983-04-13|1984-10-17|Doryokuro Kakunenryo|Method and apparatus for measuring uranium isotope enrichment|
    ES2065952T3|1988-08-31|1995-03-01|Gen Electric|NON-DESTRUCTIVE TESTING OF NUCLEAR FUEL BARS.|
    ES2391522A1|2008-12-26|2012-11-27|Korea Nuclear Fuel Co., Ltd.|Detector of defects in fuel bars using a neutron generator. |
    JP2012185108A|2011-03-08|2012-09-27|Nuclear Fuel Ind Ltd|Internal inspection method of nuclear fuel rod|ES2850778A1|2020-02-28|2021-08-31|Consejo Superior Investigacion|GAMMA RAY DETECTOR WITH MULTI-HOLE COLLIMATOR AND VARIABLE SAMPLING REGION |US3728544A|1970-07-24|1973-04-17|Nat Nuclear Corp|Method and apparatus for measurement of concentration of thermal neutron absorber contained in nuclear fuel|
    CN2366129Y|1998-08-13|2000-03-01|深圳奥沃国际科技发展有限公司|Power source adjusting device for radiation therapy|
    AU2002361919A1|2002-12-24|2004-07-22|Belgonucleaire S.A.|Method and apparatus for carrying out a mox fuel rod quality control|
    AU2003281907A1|2003-11-20|2005-06-08|Ge Medical Systems Global Technology Company, Llc.|Collimator and radiation irradiator|
    ES2351020B1|2009-06-08|2011-11-18|Enusa Industrias Avanzadas S.A.|SCANNER FOR ANALYSIS OF A NUCLEAR FUEL BAR.|
    CN103337272B|2013-06-27|2016-02-03|东软飞利浦医疗设备系统有限责任公司|X-ray collimator and collimation thereof crack width adjustment method|
    法律状态:
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    优先权:
    申请号 | 申请日 | 专利标题
    KR20150189178|2015-12-30|
    KR10-2015-0189178|2015-12-30|
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