JP2019148578A - Inspection method of uranium contamination of surface of inspection object - Google Patents
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- 238000007689 inspection Methods 0.000 title claims abstract description 58
- 238000000034 method Methods 0.000 title claims abstract description 37
- 238000011109 contamination Methods 0.000 title claims abstract description 35
- 229910052770 Uranium Inorganic materials 0.000 title claims abstract description 31
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 title claims abstract description 31
- 230000005260 alpha ray Effects 0.000 claims abstract description 17
- 238000001514 detection method Methods 0.000 claims abstract description 17
- 230000002070 germicidal effect Effects 0.000 claims description 4
- 238000003384 imaging method Methods 0.000 claims description 4
- 230000001678 irradiating effect Effects 0.000 claims description 4
- 239000002699 waste material Substances 0.000 abstract description 33
- 239000002901 radioactive waste Substances 0.000 abstract description 15
- 238000005259 measurement Methods 0.000 description 43
- 239000000463 material Substances 0.000 description 25
- 230000005855 radiation Effects 0.000 description 15
- 238000010586 diagram Methods 0.000 description 14
- 239000003758 nuclear fuel Substances 0.000 description 6
- 238000012360 testing method Methods 0.000 description 6
- 238000004891 communication Methods 0.000 description 5
- 238000012545 processing Methods 0.000 description 4
- 238000011156 evaluation Methods 0.000 description 3
- -1 uranyl ions Chemical class 0.000 description 3
- 239000003086 colorant Substances 0.000 description 2
- 230000005251 gamma ray Effects 0.000 description 2
- 230000005865 ionizing radiation Effects 0.000 description 2
- 230000002265 prevention Effects 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- 125000005289 uranyl group Chemical group 0.000 description 2
- 229910000831 Steel Inorganic materials 0.000 description 1
- 238000004458 analytical method Methods 0.000 description 1
- 238000013459 approach Methods 0.000 description 1
- 230000005250 beta ray Effects 0.000 description 1
- 238000005202 decontamination Methods 0.000 description 1
- 230000003588 decontaminative effect Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000006870 function Effects 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 238000007670 refining Methods 0.000 description 1
- 238000012958 reprocessing Methods 0.000 description 1
- 238000000926 separation method Methods 0.000 description 1
- 239000007787 solid Substances 0.000 description 1
- 239000010959 steel Substances 0.000 description 1
- 239000005314 uranium glass Substances 0.000 description 1
- 230000000007 visual effect Effects 0.000 description 1
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Abstract
Description
本発明は、検査対象物の表面のウラン汚染の検査方法に関し、より具体的には、放射性廃棄物でない廃棄物などの検査対象物の表面のウラン汚染の有無を迅速かつ効率的に検査するための検査方法に関する。 The present invention relates to a method for inspecting uranium contamination on the surface of an inspection object, and more specifically, for quickly and efficiently inspecting the presence or absence of uranium contamination on the surface of an inspection object such as waste that is not radioactive waste. It relates to the inspection method.
原子力施設等の核燃料物質を扱う施設において放射線防御の観点から特別の管理を必要とする放射性廃棄物のほかに、放射性廃棄物でない廃棄物も大量に発生する。この放射性廃棄物でない廃棄物については、経済産業省がその取扱いについてのガイドライン（指示）を出しており（非特許文献１）、その内容に沿って廃棄物として判断し管理等を行う必要がある。例えば、放射性廃棄物でない廃棄物であると判断される、汚染の恐れがある管理区域に設置された資材等及び汚染の恐れがある管理区域で使用された物品は、念ための放射線測定評価を行うこと等が求められる。 In addition to radioactive waste that requires special management from the viewpoint of radiation protection in facilities that handle nuclear fuel materials such as nuclear facilities, a large amount of waste that is not radioactive waste is also generated. Regarding waste that is not radioactive waste, the Ministry of Economy, Trade and Industry has issued guidelines (instructions) on its handling (Non-Patent Document 1), and it is necessary to judge and manage it as waste according to its contents. . For example, materials installed in a control area that is likely to be contaminated and that are used in a control area that is likely to be contaminated, and that are used in a control area that is likely to be contaminated, should be subjected to a radiological evaluation. What to do is required.
また、管理区域から持ち出す物品（廃棄物を含む）については、他の規定、例えば電離放射線障害防止規則（昭和４７年９月３０日労働省令第４１号）等に沿って、放射線同位元素による表面汚染が規定上の限度以下であることを確認した上で搬出等を行う必要がある。したがって、原子力施設で発生する放射性廃棄物でない廃棄物を処理する際には、そうした各種の規制に従った適切な放射線測定を含む処理、管理を行うことが求められる。 In addition, for articles (including waste) taken out from the management area, the surface with radioactive isotopes in accordance with other regulations, such as the Regulation for Prevention of Ionizing Radiation Hazards (Ministry of Labor Ordinance No. 41 of September 30, 1972), etc. It is necessary to carry out removal after confirming that the contamination is below the specified limit. Therefore, when processing non-radioactive waste generated at nuclear facilities, it is required to perform processing and management including appropriate radiation measurement in accordance with such various regulations.
特許文献１は、放射性廃棄物についてα線核種を含むものとα線核種を含まないものに仕分けする放射性廃棄物の仕分け方法、仕分け装置およびα線測定装置を開示する。しかし、特許文献１は放射性廃棄物でない廃棄物の放射線測定評価について開示するものではない。また、α線測定を迅速かつ効率的に行うことを開示するものではない。 Patent Document 1 discloses a radioactive waste sorting method, a sorting device, and an α-ray measuring device that sorts radioactive waste into those containing α-ray nuclides and those that do not contain α-ray nuclides. However, Patent Document 1 does not disclose radiation measurement evaluation of waste that is not radioactive waste. Moreover, it does not disclose that the α-ray measurement is performed quickly and efficiently.
特許文献２は、原子力施設の解体撤去に伴う解体廃棄物から分別されたクリアランス対象物のクリアランス前測定（表面汚染密度の測定、γ線測定とβ線測定）とクリアランス測定（平均放射能濃度、γ線測定）を含む分別・クリアランス処理システムを開示する。しかし、特許文献２はクリアランス対象物から汚染の高い部位を除去する除染を行うことを前提としており、放射性廃棄物でない廃棄物の放射線測定評価及び処理について具体的に開示するものではない。また、表面汚染密度の測定を迅速かつ効率的に行うことを開示するものではない。 Patent Document 2 describes the pre-clearance measurement (measurement of surface contamination density, γ-ray measurement and β-ray measurement) and clearance measurement (average radioactivity concentration, Disclosed is a separation / clearance processing system including γ-ray measurement. However, Patent Document 2 is based on the premise that decontamination is performed to remove highly contaminated parts from the clearance object, and does not specifically disclose radiation measurement evaluation and treatment of waste that is not radioactive waste. Further, it does not disclose that the surface contamination density is measured quickly and efficiently.
特許文献３は、紫外のレーザ光を固体試料に照射して発生する蛍光を分光分析してウラン濃度を測定する分析方法を開示する。しかし、特許文献３は、検査対象物の表面のウラン汚染の有無を迅速かつ効率的に検査するための検査方法を開示するものではない。 Patent Document 3 discloses an analysis method for measuring the uranium concentration by spectroscopically analyzing fluorescence generated by irradiating a solid sample with ultraviolet laser light. However, Patent Document 3 does not disclose an inspection method for quickly and efficiently inspecting the presence or absence of uranium contamination on the surface of an inspection object.
本発明は、放射性廃棄物でない廃棄物などの検査対象物の表面のウラン汚染の有無を迅速かつ効率的に検査するための検査方法を提供することを目的とする。 An object of the present invention is to provide an inspection method for quickly and efficiently inspecting the presence or absence of uranium contamination on the surface of an inspection object such as waste that is not radioactive waste.
本発明は、検査対象物の表面のウラン汚染の有無を検査する検査方法を提供する。その検査方法は、（ａ）検査対象物の表面に紫外線を照射する工程と、（ｂ）紫外線の照射下における検査対象物の表面での緑色、青色、またはこれら両方を含む蛍光を発する領域を特定する工程と、（ｃ）蛍光を発する領域のウラン汚染の有無を直接サーベイ法を用いたα線検出により測定する工程と、を含む。 The present invention provides an inspection method for inspecting the presence or absence of uranium contamination on the surface of an inspection object. The inspection method includes (a) a step of irradiating the surface of the inspection object with ultraviolet light, and (b) a region emitting fluorescence including green, blue, or both on the surface of the inspection object under the irradiation of ultraviolet light. And (c) a step of measuring the presence or absence of uranium contamination in the fluorescence emitting region by α ray detection using a direct survey method.
本発明によれば最初に紫外線照射によって定対象物の表面での蛍光を発する領域を特定した上でその領域での放射線（α線）検出による測定を行うので、測定領域が予め限定されていることから、ウラン汚染の有無を迅速かつ効率的に検査することができる。特に、飛程の短いα線検出では、検出器を検査対象物の表面に当ててあるいはごく近傍に置いて測定し、順次検出器を移動させて測定領域を変えながら測定する必要があることから、その測定領域が事前に特定／限定されることは測定作業時間を大幅に短縮でき、かつ測定漏れを減らすことができるという大きな利点がある。 According to the present invention, first, a region that emits fluorescence on the surface of a fixed object is identified by ultraviolet irradiation, and then measurement is performed by detecting radiation (α-rays) in that region, so the measurement region is limited in advance. Therefore, the presence or absence of uranium contamination can be inspected quickly and efficiently. Especially for alpha ray detection with a short range, it is necessary to measure by placing the detector on the surface of the object to be inspected or in close proximity, and moving the detector sequentially to change the measurement area. Since the measurement area is specified / limited in advance, there is a great advantage that the measurement work time can be greatly shortened and measurement omission can be reduced.
図面を参照しながら本発明の実施の形態を説明する。図１は、本発明の一実施形態の検査対象物の表面のウラン汚染の有無を検査する検査方法の工程を示す図である。本発明の検査対象となる検査対象物は、基本的に核燃料物質を扱う施設においてその表面がウランで汚染される可能性があるあらゆる物が該当するが、以下の説明ではその一例として、放射性廃棄物でない廃棄物を例として挙げて説明を行う。また、本明細書で言う「ウラン」とは、紫外線を当てるとウラン特有の蛍光、すなわち緑色、青色、またはこれらの両方（混合色）を含む蛍光を発する性質を有する６価のウランを意味し、廃棄物中での存在形態としては、例えば、ウラニルイオン（ＵＯ２ ２＋）を含むウラニル化合物、ウラニル塩が挙げられる。 Embodiments of the present invention will be described with reference to the drawings. FIG. 1 is a diagram showing the steps of an inspection method for inspecting the presence or absence of uranium contamination on the surface of an inspection object according to an embodiment of the present invention. The inspection object to be inspected according to the present invention basically includes any object whose surface may be contaminated with uranium in a facility that handles nuclear fuel materials. In the following description, as an example, radioactive waste An explanation will be given by taking a waste that is not a waste as an example. In addition, “uranium” as used in this specification means hexavalent uranium having a property of emitting fluorescence characteristic of uranium, ie, green, blue, or both (mixed colors) when irradiated with ultraviolet rays. Examples of the existing form in waste include uranyl compounds and uranyl salts containing uranyl ions (UO 2 2+ ).
核燃料物質を扱う施設には、原子力施設の他に原子力とは直接的には関係がないが、６価のウラン（例えばウラニルイオン（ＵＯ２ ２＋））を扱うことがある化学工場等の製造施設、加工施設も含まれる。原子力施設には、例えば非特許文献１に記載される精錬施設、原子炉施設、再処理施設等が含まれる。さらに、放射性廃棄物でない廃棄物（以下、ＮＲ廃棄物と呼ぶ）は、基本的に非特許文献１のガイドラインに沿って判断されるものを言うが、対象となる廃棄物が発生する施設には、原子力施設の他に上述した原子力とは直接的には関係のない化学工場等も含むものとする。 In addition to nuclear facilities, facilities that handle nuclear fuel materials are not directly related to nuclear power, but manufacturing facilities such as chemical factories that may handle hexavalent uranium (eg, uranyl ions (UO 2 2+ )) Processing facilities are also included. The nuclear facility includes, for example, a refining facility, a nuclear reactor facility, a reprocessing facility described in Non-Patent Document 1. Furthermore, waste that is not radioactive waste (hereinafter referred to as NR waste) is basically determined in accordance with the guidelines of Non-Patent Document 1, but in facilities where target waste is generated, In addition to nuclear facilities, chemical factories that are not directly related to nuclear energy are also included.
図１の工程Ｓ１において、検査対象物の表面に紫外線を照射する。検査対象物は上述したように例えば核燃料物質を扱う施設において収集されたＮＲ廃棄物である。このＮＲ廃棄物には、核燃料物質を扱う施設において設置された資材または使用された物品であって核燃料物質によって汚染された物で廃棄しようとするものではない廃棄物が含まれる。その設置された資材または使用された物品には、構造材プレート、機器部材、鋼材、金物、配管、電線管類、及び機器類等の解体物や切断材が含まれる。これらの解体物や切断材は、概ね１〜２ｍ程度のサイズを有し台車等に載せて移動可能な状態になっている。収集されたＮＲ廃棄物は、これらの各部材ごとに選別された後に、番号が付され重量が測定されて、各情報がパソコン等にデータとして登録（保管）されている。 In step S1 of FIG. 1, the surface of the inspection object is irradiated with ultraviolet rays. As described above, the inspection object is, for example, NR waste collected in a facility that handles nuclear fuel material. This NR waste includes materials installed in facilities that handle nuclear fuel materials or used items that are not intended to be disposed of with materials contaminated with nuclear fuel materials. The installed materials or used articles include dismantled materials and cutting materials such as structural material plates, equipment members, steel materials, hardware, pipes, conduits, and equipment. These dismantled materials and cutting materials have a size of about 1 to 2 m and are movable on a carriage or the like. The collected NR waste is sorted for each of these members, then numbered and weighted, and each information is registered (stored) in a personal computer or the like as data.
図２は、本発明の一実施形態の検査対象物への紫外線照射と蛍光発光の様子を示す模式図である。ここでは、検査対象物との一例として構造材プレート１を用い、その表面に紫外線光源１０から紫外線１２を照射する例を示している。紫外線光源１０は、基本的に波長が４００ｎｍより短い不可視な電磁波を発することができる光源であればよいが、本発明ではウランの蛍光を検出する必要があることから、ウランが蛍光を発しやすい波長域を含む紫外線を発することができる紫外線光源が望ましいい。その波長域はウランガラスを用いた測定データから、例えば３２７ｎｍ付近にピークを持つ波長域、あるいは４２０ｎｍ付近にピークを持つ波長域が望ましいが、少なくともこれらの波長域を含む紫外線を発する紫外線光源であればよい。市販の紫外線光源としては、例えばＵＶ−ＬＥＤ、ブラックライト、または紫外線殺菌灯などを用いることができる。 FIG. 2 is a schematic diagram showing the state of ultraviolet irradiation and fluorescence emission on an inspection object according to an embodiment of the present invention. Here, an example in which the structural material plate 1 is used as an example of an inspection object and the surface is irradiated with ultraviolet rays 12 from an ultraviolet light source 10 is shown. The ultraviolet light source 10 may basically be any light source that can emit an invisible electromagnetic wave having a wavelength shorter than 400 nm. However, in the present invention, since it is necessary to detect uranium fluorescence, the wavelength at which uranium easily emits fluorescence. An ultraviolet light source capable of emitting ultraviolet light including a region is desirable. The wavelength range is preferably a wavelength range having a peak near 327 nm or a wavelength range having a peak near 420 nm, for example, from measurement data using uranium glass, but at least an ultraviolet light source that emits ultraviolet rays including these wavelength ranges. That's fine. As a commercially available ultraviolet light source, for example, a UV-LED, a black light, or an ultraviolet germicidal lamp can be used.
図３は、一実施形態の紫外線光源の例（形状）を示す模式図である。図３（ａ）はランプ型の紫外線光源１４であり、内蔵する発光素子（例えばＵＶランプ、格子状のＵＶ−ＬＥＤ等）からの紫外線を表面から放射状に発するタイプである。スポット的に所定の広がりを持つ紫外線を照射できるので、検査対象物の表面が比較的小さい場合に特に有効な光源である。（ｂ）はライン状に複数の発光素子（例えばＵＶ−ＬＥＤ）を配置したライン紫外線光源１５である。所定の長さの領域に紫外線を照射できるので、図１の構造材プレート１のような幅が広く比較的大きな表面を持つ検査対象の場合に特に有効である。（ｃ）は横長の蛍光管式の紫外線光源（例えば紫外線殺菌灯）１６である。（ｂ）の紫外線光源１５と同様に、幅が広く比較的大きな表面を持つ検査対象の場合に特に有効である。 FIG. 3 is a schematic diagram illustrating an example (shape) of an ultraviolet light source according to an embodiment. FIG. 3A shows a lamp-type ultraviolet light source 14 that emits ultraviolet rays from a built-in light emitting element (for example, a UV lamp, a grid-shaped UV-LED, etc.) radially from the surface. Since it is possible to irradiate ultraviolet rays having a predetermined spread as a spot, the light source is particularly effective when the surface of the inspection object is relatively small. (B) is the line ultraviolet light source 15 which has arrange | positioned the several light emitting element (for example, UV-LED) in the shape of a line. Since a region of a predetermined length can be irradiated with ultraviolet rays, it is particularly effective in the case of an inspection object having a wide width and a relatively large surface, such as the structural material plate 1 in FIG. (C) is a horizontally long fluorescent tube type ultraviolet light source (for example, ultraviolet germicidal lamp) 16. Similar to the ultraviolet light source 15 in (b), this is particularly effective in the case of an inspection object having a wide width and a relatively large surface.
図１の工程Ｓ２において、検査対象の表面において、紫外線照射によりウラン特有の蛍光である、青色、緑色、あるいはこれら双方を含む（混合した）色の蛍光を発する領域を特定する。図２では、符号２〜５の領域がこの蛍光を発する領域として例示されている。この蛍光領域の特定は目視によって行うことができるが、例えば図４に例示するように、撮像デバイス２０、２２を用いて画像として取得し記録することもできる。図４では、図２の場合と同様に紫外線光源１０を用いて紫外線１２を構造材プレート１の表面に照射している間に、デジタルカメラ２０、あるいはスマートフォン２２のカメラ機能を用いて、蛍光領域２〜５を画像として取得し記憶する。その画像の記憶は、デジタルカメラ２０、スマートフォン２２が内蔵するメモリへの記憶に加えて、これらから無線信号を介してパーソナルコンピュータ（ＰＣ）等のメモリに、該当するＮＲ廃棄物の番号等に関連付けて記憶させることができる。 In step S2 of FIG. 1, a region that emits fluorescence of a color including (mixed) blue, green, or both, which is fluorescence unique to uranium by ultraviolet irradiation, is specified on the surface to be inspected. In FIG. 2, the area | region of the code | symbol 2-5 is illustrated as an area | region which emits this fluorescence. Although this fluorescent region can be identified by visual observation, it can also be acquired and recorded as an image using the imaging devices 20 and 22, for example, as illustrated in FIG. In FIG. 4, as in the case of FIG. 2, while the ultraviolet light source 10 is used to irradiate the surface of the structural material plate 1 with the ultraviolet light 12, the digital camera 20 or the camera function of the smartphone 22 is used. 2 to 5 are acquired and stored as images. In addition to storing the image in the memory built in the digital camera 20 and the smartphone 22, the image is stored in a memory such as a personal computer (PC) via a wireless signal and associated with the corresponding NR waste number. Can be memorized.
このように、本発明では検査対象物の表面でのウラン汚染の有無を検査する際に、最初にその表面に紫外線を照射してウラン特有の蛍光を発する領域、すなわちウラン汚染がある可能性が高い領域を特定することに１つの特徴がある。これにより、後工程の放射線（α線）の測定をその特定された領域に限定することができるので、その測定を無駄なく迅速かつ効率的に行うことが可能となる。特に大量のＮＲ廃棄物の汚染検査をする場合にその検査時間や検査工数／検査費用の低減効果が大きくなる。 Thus, in the present invention, when inspecting the presence or absence of uranium contamination on the surface of the object to be inspected, there is a possibility that there is a region where the surface is first irradiated with ultraviolet rays to emit fluorescence unique to uranium, that is, uranium contamination. There is one feature in identifying high areas. Thereby, since the measurement of the radiation (α ray) in the subsequent process can be limited to the specified region, the measurement can be performed quickly and efficiently without waste. In particular, when performing a contamination inspection of a large amount of NR waste, the effect of reducing the inspection time and the inspection man-hour / inspection cost is increased.
図１の工程Ｓ３において、検査対象物の表面の特定された蛍光領域の放射線測定を行う。図５は、本発明の一実施形態の蛍光領域の放射線測定の様子を示す模式図である。図５では、一測定例として、直接サーベイ法による表面汚染検査用サーベイメータ３０を用いて、図２、図４の構造材プレート１の表面上の蛍光領域４での放射線（α線）を測定する例を示している。（ａ）は測定の斜め上面図であり、（ｂ）はそのＡ−Ａ´断面図である。表面汚染検査用サーベイメータ３０は、例えばα線の検出可能なＺｎＳ（Ａｇ）シンチレーション検出器、あるいはα線とβ線の検出可能なＺｎＳ（Ａｇ）＋プラスチックシンチレータを用いたシンチレーション検出器等を用いることができる。α線検出の場合はその検出限界が０．４Ｂｑ／ｃｍ２以下である性能を有する検出器を用いて行う。 In step S3 of FIG. 1, radiation measurement is performed on the specified fluorescent region on the surface of the inspection object. FIG. 5 is a schematic diagram showing a state of radiation measurement in the fluorescent region according to one embodiment of the present invention. In FIG. 5, as one measurement example, radiation (α-rays) in the fluorescent region 4 on the surface of the structural material plate 1 in FIGS. 2 and 4 is measured using a survey meter 30 for surface contamination inspection by a direct survey method. An example is shown. (A) is a diagonal top view of a measurement, (b) is the AA 'sectional drawing. The surface contamination inspection survey meter 30 uses, for example, a ZnS (Ag) scintillation detector capable of detecting alpha rays, or a scintillation detector using ZnS (Ag) + plastic scintillator capable of detecting alpha rays and beta rays. Can do. In the case of α-ray detection, a detector having a performance whose detection limit is 0.4 Bq / cm 2 or less is used.
図５の測定例では、ハンディタイプの表面汚染検査用サーベイメータ３０は、（ｂ）に示すように構造材プレート１の表面上の蛍光領域に当接あるいはできるだけ近接させてα線の測定を行う。その測定結果である表面汚染密度（Ｂｑ／ｃｍ２）は、表面汚染検査用サーベイメータ３０の表示部３１に表示される。特定された蛍光領域の測定箇所を変えながら構造材プレート１の表面上の蛍光領域２〜５の全てについての測定を行う。 In the measurement example of FIG. 5, the handy type surface contamination inspection survey meter 30 measures α rays while contacting or as close as possible to the fluorescent region on the surface of the structural material plate 1 as shown in FIG. The surface contamination density (Bq / cm 2 ), which is the measurement result, is displayed on the display unit 31 of the surface contamination inspection survey meter 30. Measurement is performed for all of the fluorescent regions 2 to 5 on the surface of the structural material plate 1 while changing the measurement location of the specified fluorescent region.
図６は、本発明の他の一実施形態の蛍光領域の放射線測定の様子を示す模式図である。図６では、図５のハンディタイプの表面汚染検査用サーベイメータ３０の代わりに、検出器３３と表示器３４が通信ケーブル３５を介して接続されている構成のサーベイメータを用いて測定を行う。検出器３３としては、上述したように、α線の検出可能なＺｎＳ（Ａｇ）シンチレーション検出器、あるいはα線とβ線の検出可能なＺｎＳ（Ａｇ）＋プラスチックシンチレータを用いたシンチレーション検出器等を用いることができる。α線検出の場合はその検出限界が０．４Ｂｑ／ｃｍ２以下である性能を有する検出器を用いて行う。 FIG. 6 is a schematic diagram showing a state of radiation measurement in the fluorescent region according to another embodiment of the present invention. In FIG. 6, measurement is performed using a survey meter having a configuration in which a detector 33 and a display 34 are connected via a communication cable 35 instead of the handy type surface contamination inspection survey meter 30 of FIG. 5. As described above, the detector 33 is a ZnS (Ag) scintillation detector capable of detecting α-rays, or a scintillation detector using ZnS (Ag) + plastic scintillator capable of detecting α-rays and β-rays. Can be used. In the case of α-ray detection, a detector having a performance whose detection limit is 0.4 Bq / cm 2 or less is used.
図５の場合と同様に検査対象物のＮＲ廃棄物（構造材プレート）１の表面の蛍光領域４に検出器３３の測定面（検出面）が当接され、通信ケーブル３５を介してその検出値が表示器３４に送られる。表示器３４では、その表示画面３７にリアルタイムに測定結果が表示され、同時に測定データとして内蔵するメモリに保管される。メモリに保管された測定データ（Ｂｑ／ｃｍ２）はさらに無線通信などを介してパーソナルコンピュータ（ＰＣ）等のメモリに、該当するＮＲ廃棄物（構造材プレート）の番号、蛍光領域の画像データ等に関連付けて記憶させることができる。 As in the case of FIG. 5, the measurement surface (detection surface) of the detector 33 is brought into contact with the fluorescent region 4 on the surface of the NR waste (structural material plate) 1 to be inspected, and the detection is performed via the communication cable 35. The value is sent to the display 34. In the display device 34, the measurement result is displayed on the display screen 37 in real time, and at the same time, stored in a built-in memory as measurement data. The measurement data (Bq / cm 2 ) stored in the memory is further stored in the memory of a personal computer (PC) or the like via wireless communication or the like, the number of the corresponding NR waste (structural material plate), the image data of the fluorescent region, etc. It can be stored in association with.
図１の工程Ｓ４において、工程Ｓ３の測定結果から検査対象物（ＮＲ廃棄物）の表面のウラン汚染の有無を判定する。具体的には、例えば、図５、図６の検出器３１、３３による測定結果から表面汚染密度が０．４Ｂｑ／ｃｍ２以上である場合にウラン汚染が有ると判断し、それ未満である場合にウラン汚染が無いと判断する。この判断基準値である０．４Ｂｑ／ｃｍ２は、電離放射線障害防止規則（昭和４７年９月３０日労働省令第４１号）の別表第３に定められているα線を放出する放射線同位元素による表面汚染の限度（４Ｂｑ／ｃｍ２）の１／１０に相当し、当該物を施設外に持ち出す際にその値（限度の１／１０）を越えてはいけないとされているものである。 In step S4 of FIG. 1, the presence or absence of uranium contamination on the surface of the inspection object (NR waste) is determined from the measurement result of step S3. Specifically, for example, when the surface contamination density is 0.4 Bq / cm 2 or more from the measurement results by the detectors 31 and 33 in FIGS. 5 and 6, it is determined that there is uranium contamination, and if it is less than that, Is judged to be free of uranium contamination. This criterion value of 0.4 Bq / cm 2 is a radiation isotope that emits alpha rays as stipulated in Schedule 3 of the Regulation for Prevention of Ionizing Radiation Hazards (September 30, 1970, Ministry of Labor Ordinance No. 41) This is equivalent to 1/10 of the limit of surface contamination (4Bq / cm 2 ) due to the above, and when the product is taken out of the facility, the value (1/10 of the limit) must not be exceeded.
図７は、図１の工程Ｓ１の本発明の他の一実施形態の検査対象物への紫外線照射と蛍光発光の様子を示す模式図である。図７では、検査対象物のＮＲ廃棄物として配管６の開口部を含む表面に紫外線光源１０から紫外線１２を照射する例を示している。配管６の開口内の空洞の壁に紫外線によってウラン特有の蛍光（青色、緑色、あるいはこれら双方を含む色の蛍光）を発する領域７、８が存在している。このような比較的狭い領域へ紫外線を照射するには、上述した図３のランプ型の紫外線光源１４を用いることが有効である。配管内の蛍光領域７、８は、図５や図６で示したように直接サーベイメータ（検出器）を当接または近接させることができない。したがって、図７の配管内のような直接サーベイ法では測定が困難な表面での蛍光領域はスミヤ法を用いたα線検出により測定する必要がある。 FIG. 7 is a schematic diagram showing the state of ultraviolet irradiation and fluorescence emission on the inspection object of another embodiment of the present invention in step S1 of FIG. In FIG. 7, the example which irradiates the ultraviolet-ray 12 from the ultraviolet light source 10 to the surface containing the opening part of the piping 6 as NR waste of a test object is shown. Regions 7 and 8 that emit fluorescence characteristic of uranium (fluorescence of colors including blue, green, or both) by ultraviolet rays exist on the cavity wall in the opening of the pipe 6. In order to irradiate such a relatively narrow region with ultraviolet rays, it is effective to use the lamp-type ultraviolet light source 14 shown in FIG. As shown in FIGS. 5 and 6, the fluorescent regions 7 and 8 in the pipe cannot directly contact or approach the survey meter (detector). Therefore, it is necessary to measure the fluorescent region on the surface, which is difficult to measure by the direct survey method as in the pipe of FIG. 7, by α ray detection using the smear method.
図８は、本発明の一実施形態のスミヤ法を用いた蛍光領域の放射線測定の模式図である。検査対象物（ＮＲ廃棄物）である配管６の蛍光領域７、８の表面をふき取ったスミヤろ紙４０にα線検出器４１の測定面（検出面）が当接され、通信ケーブル４２を介してα線の検出値がパーソナルコンピュータ（ＰＣ）４３に送られる。ＰＣ４３では、その表示画面４４にリアルタイムに測定結果が表示され、同時に測定データとして内蔵するメモリに保管される。その際に、該当するＮＲ廃棄物（配管）の番号、蛍光領域の画像データ等に関連付けて記憶させることができる。α線検出器４１は、図５や図６の直接サーベイ法による測定と同様に、例えばＺｎＳ（Ａｇ）シンチレーション検出器であって、検出限界が０．４Ｂｑ／ｃｍ２以下である性能を有するものを用いることができる。 FIG. 8 is a schematic diagram of radiation measurement of a fluorescent region using the smear method according to one embodiment of the present invention. The measurement surface (detection surface) of the α-ray detector 41 is brought into contact with the smear filter paper 40 that wipes off the surfaces of the fluorescent regions 7 and 8 of the pipe 6 that is the inspection object (NR waste), and is connected via the communication cable 42. The detected value of α rays is sent to a personal computer (PC) 43. In the PC 43, the measurement result is displayed in real time on the display screen 44, and at the same time, stored in a built-in memory as measurement data. At that time, it can be stored in association with the number of the corresponding NR waste (piping), image data of the fluorescent region, and the like. The α-ray detector 41 is, for example, a ZnS (Ag) scintillation detector having a performance with a detection limit of 0.4 Bq / cm 2 or less, as in the measurement by the direct survey method in FIGS. Can be used.
本発明の実施形態について、図を参照しながら説明をした。しかし、本発明はこれらの実施形態に限られるものではない。本発明はその趣旨を逸脱しない範囲で当業者の知識に基づき種々なる改良、修正、変形を加えた態様で実施できるものである。 Embodiments of the present invention have been described with reference to the drawings. However, the present invention is not limited to these embodiments. The present invention can be implemented in variously modified, modified, and modified embodiments based on the knowledge of those skilled in the art without departing from the spirit of the present invention.
本発明の検査方法は、放射性廃棄物でない廃棄物（ＮＲ廃棄物）のみならず各施設から出るウラン汚染が疑われる廃棄物の処理／処分においてその放射能レベルに応じた仕分けを行うための検査方法として幅広く利用することができる。 The inspection method of the present invention is an inspection for sorting according to the radioactivity level in the treatment / disposal of waste that is suspected of uranium contamination from each facility as well as waste that is not radioactive waste (NR waste). It can be widely used as a method.
１ 構造材プレート（検査対象物、ＮＲ廃棄物）
２、３、４、５、７、８ 蛍光領域
６ 配管（検査対象物、ＮＲ廃棄物）
１０ 紫外線光源
１２ 紫外線
１４ ランプ型の紫外線光源
１５ ライン紫外線光源
１６ 蛍光管式の紫外線光源（紫外線殺菌灯）
２０ デジタルカメラ
２２ スマートフォン
３０ 表面汚染検査用サーベイメータ
３１、３７、４４ 表示部
３３ 検出器
３４ 表示器
３５、４２ 通信ケーブル
４０ スミヤろ紙
４１ α線検出器
４３ パーソナルコンピュータ（ＰＣ）
1 Structural material plate (inspection object, NR waste)
2, 3, 4, 5, 7, 8 Fluorescent area 6 Piping (inspection object, NR waste)
10 UV light source 12 UV 14 Lamp type UV light source 15 Line UV light source 16 Fluorescent tube type UV light source (UV germicidal lamp)
20 Digital Camera 22 Smartphone 30 Survey Meter 31, 37, 44 for Surface Contamination Inspection Display 33 Detector 34 Display 35, 42 Communication Cable 40 Smear Filter Paper 41 Alpha Ray Detector 43 Personal Computer (PC)
Claims (5)
検査対象物の表面に紫外線を照射する工程と、
前記紫外線の照射下における前記検査対象物の表面の緑色、青色、またはこれら両方を含む蛍光を発する領域を特定する工程と、
前記蛍光を発する領域のウラン汚染の有無を直接サーベイ法によるα線検出により検査する工程と、を含む検査方法。 An inspection method for inspecting the surface of an inspection object for uranium contamination,
Irradiating the surface of the inspection object with ultraviolet rays;
Identifying a fluorescent region including green, blue, or both of the surface of the inspection object under the irradiation of the ultraviolet rays,
Inspecting the presence or absence of uranium contamination in the fluorescent region by direct detection by α-ray detection.
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