JP2013213806A - Radiation measurement sample container - Google Patents

Radiation measurement sample container Download PDF

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JP2013213806A
JP2013213806A JP2012244463A JP2012244463A JP2013213806A JP 2013213806 A JP2013213806 A JP 2013213806A JP 2012244463 A JP2012244463 A JP 2012244463A JP 2012244463 A JP2012244463 A JP 2012244463A JP 2013213806 A JP2013213806 A JP 2013213806A
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container body
container
main body
container main
diameter
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Eisuke Itatsu
英輔 板津
Toshiro Abe
敬朗 阿部
Yukitsugu Takahashi
幸嗣 高橋
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Seiko EG&G Co Ltd
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Seiko EG&G Co Ltd
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Abstract

PROBLEM TO BE SOLVED: To secure desired detection efficiency with respect to a plurality of radiation detectors having various types of shapes that are frequently used for environmental radiation measurement.SOLUTION: A radiation measurement sample container 10 comprises: a bottomed cylindrical type container main body 11; and a cylindrical recessed portion 12 provided coaxially with a central axis of the container main body 11 on a bottom surface 11A of the container main body 11. A diameter of an inner peripheral wall surface 11C of the container main body 11 ranges from 130.6 mm to 139 mm, a diameter of a cylindrical portion 14 provided inside the container main body 11 corresponding to the cylindrical recessed portion 12 ranges from 81 mm to 95 mm, a distance from an inner bottom surface 11B of the container main body 11 to an accommodation end 13 of a radiation measurement sample provided on the inner peripheral wall surface 11C ranges from 90 mm to 129 mm, a distance from the inner bottom surface 11B of the container main body 11 to a leading end surface 14A of the cylindrical portion 14 ranges from 79 mm to 100 mm and an interior volume from the inner bottom surface 11B of the container main body 11 to the accommodation end is 1 liter.

Description

この発明は、放射能測定用試料容器に関する。   The present invention relates to a sample container for measuring radioactivity.

従来、例えば各種の放射能測定用試料を内部に収容可能な放射能測定用試料容器として、０．７リットルまたは２リットルの内容積を有する所定寸法のマリネリ容器が知られている（例えば、非特許文献１参照）。
また、従来、例えば所定形状のゲルマニウム半導体検出器に対して各種の内容積のマリネリ容器の最適形状（つまり、マリネリ容器内に収容された測定試料から放出されるγ線の検出効率が最大となる形状）を、モンテカルロ法のシミュレーションにより算出する方法が知られている（例えば、非特許文献２参照）。 Conventionally, for example, a marinelli container of a predetermined size having an internal volume of 0.7 liters or 2 liters is known as a radioactive measurement sample container capable of accommodating various radioactive measurement samples inside (for example, non-radioactive measurement sample containers). Patent Document 1).
Conventionally, for example, a germanium semiconductor detector having a predetermined shape has an optimum shape of a marinelli container with various internal volumes (that is, the detection efficiency of γ rays emitted from a measurement sample stored in the marinelli container is maximized). There is known a method of calculating (shape) by Monte Carlo simulation (for example, see Non-Patent Document 2).

「放射能測定法シリーズ ７ ゲルマニウム半導体検出器によるガンマ線スペクトロメトリー」、文部科学省、平成４年、ｐ.９７−１０４"Radioactivity measurement series 7 Gamma-ray spectrometry using germanium semiconductor detector", Ministry of Education, Culture, Sports, Science and Technology, 1992, p.97-104 「ニュークリア インスツルメント アンド メソッド イン フィジックス リサーチ エー 第６１０巻（２００９年） ｐ.７１８−７２３（Nuclear Instruments and Methods in Physics Research A 610 (2009) 718-723）“Nuclear Instruments and Methods in Physics Research A 610 (2009) 718-723”, “Nuclear Instruments and Methods in Physics Research A 610 (2009) 718-723”

ところで、上記従来技術に係るマリネリ容器においては、各種の形状を有する放射線検出器に対して最適形状を有しているか否かは明らかではなく、特に、環境放射能の測定に多用される各種の形状の放射線検出器に対して所望の検出効率を確保するような形状を有する放射能測定用試料容器が望まれている。   By the way, in the marinellier container according to the above-mentioned prior art, it is not clear whether or not it has an optimum shape for radiation detectors having various shapes, and in particular, various types frequently used for measurement of environmental radioactivity. There is a demand for a sample container for radioactivity measurement having a shape that ensures a desired detection efficiency for a radiation detector having a shape.

本発明は上記事情に鑑みてなされたもので、環境放射能の測定に多用される複数の各種の形状を有する放射線検出器に対して所望の検出効率を確保することが可能な放射能測定用試料容器を提供することを目的としている。   The present invention has been made in view of the above circumstances, and for radioactivity measurement capable of ensuring a desired detection efficiency for a radiation detector having a plurality of various shapes frequently used for measurement of environmental radioactivity. The object is to provide a sample container.

上記課題を解決して係る目的を達成するために、本発明の請求項１に係る放射能測定用試料容器は、有底円筒型の容器本体（例えば、実施の形態での容器本体１１）と、該容器本体の中心軸に同軸に前記容器本体の底面（例えば、実施の形態での底面１１Ａ）上に設けられた円柱状凹部（例えば、実施の形態での円柱状凹部１２）と、を備え、前記容器本体の内部に放射能測定用試料を収容可能な放射能測定用試料容器であって、前記容器本体の内周壁面（例えば、実施の形態での内周壁面１１Ｃ）の直径は１３０．６ｍｍ〜１３９ｍｍ、かつ前記円柱状凹部に応じて前記容器本体の内部に設けられる円柱状部（例えば、実施の形態での円柱状部１４）の直径は８１ｍｍ〜９５ｍｍ、かつ前記容器本体の内底面（例えば、実施の形態での内底面１１Ｂ）から前記内周壁面上に設けられた前記放射能測定用試料の収容端（例えば、実施の形態での収容端１３）までの距離は９０ｍｍ〜１２９ｍｍ、かつ前記容器本体の内底面から前記円柱状部の先端面（例えば、実施の形態での先端面１４Ａ）までの距離は７９ｍｍ〜１００ｍｍ、かつ前記容器本体の内底面から前記収容端までの内容積は１リットルである。   In order to solve the above-described problems and achieve the object, a radioactivity measurement sample container according to claim 1 of the present invention is a bottomed cylindrical container body (for example, the container body 11 in the embodiment). A cylindrical recess (for example, the cylindrical recess 12 in the embodiment) provided on the bottom surface of the container body (for example, the bottom surface 11A in the embodiment) coaxially with the central axis of the container body, A radioactivity measurement sample container capable of accommodating a radioactivity measurement sample in the container body, wherein the inner peripheral wall surface of the container main body (for example, the inner peripheral wall surface 11C in the embodiment) has a diameter of 130.6 mm to 139 mm, and the diameter of the columnar portion (for example, the columnar portion 14 in the embodiment) provided inside the container body according to the columnar recess is 81 mm to 95 mm, and the container body Inner bottom surface (for example, inner bottom in the embodiment) 11B) to the accommodation end (for example, the accommodation end 13 in the embodiment) of the radioactivity measurement sample provided on the inner peripheral wall surface, and the distance from 90 mm to 129 mm, and from the inner bottom surface of the container body The distance to the front end surface (for example, front end surface 14A in the embodiment) of the columnar portion is 79 mm to 100 mm, and the internal volume from the inner bottom surface of the container body to the accommodation end is 1 liter.

さらに、本発明の請求項２に係る放射能測定用試料容器では、前記円柱状凹部は、２０％〜４０％の相対効率値を有する放射線検出器のエンドキャップを収容可能であり、前記放射線検出器の結晶の直径は４８ｍｍ〜６０ｍｍ、かつ前記結晶の長さは３０ｍｍ〜７０ｍｍである。   Furthermore, in the sample container for radioactivity measurement according to claim 2 of the present invention, the cylindrical recess can accommodate an end cap of a radiation detector having a relative efficiency value of 20% to 40%, and the radiation detection The diameter of the crystal of the vessel is 48 mm to 60 mm, and the length of the crystal is 30 mm to 70 mm.

本発明の放射能測定用試料容器によれば、各直径および各距離の寸法範囲は、例えば、２０％〜４０％の相対効率値を有する複数の放射線検出器に対して、放射能測定用試料容器の各直径および各距離を適宜に変化させた所定の演算によって設定されている。
この所定の演算は、環境放射能の測定に多用される複数の放射線検出器に対して系統的に実行され、例えば、放射線の輸送をシミュレーションにより演算して、この演算結果に基づいて放射線検出器の検出効率を算出するものなどである。
これにより、複数の放射線検出器、特に環境放射能の測定に多用される２０％〜４０％の相対効率値を有する複数の放射線検出器に対して、所望の検出効率を容易に確保することができる。 According to the sample container for measuring radioactivity of the present invention, the size range of each diameter and each distance is, for example, for a plurality of radiation detectors having a relative efficiency value of 20% to 40%. Each diameter and each distance of the container are set by a predetermined calculation that is appropriately changed.
This predetermined calculation is systematically executed for a plurality of radiation detectors frequently used for measurement of environmental radioactivity. For example, the radiation transport is calculated by simulation, and the radiation detector is calculated based on the calculation result. Or the like that calculates the detection efficiency.
Thereby, it is possible to easily ensure a desired detection efficiency for a plurality of radiation detectors, particularly a plurality of radiation detectors having a relative efficiency value of 20% to 40%, which is frequently used for measurement of environmental radioactivity. it can.

本発明の実施の形態に係る放射能測定用試料容器の断面図である。It is sectional drawing of the sample container for radioactivity measurement which concerns on embodiment of this invention. 本発明の実施の形態に係る放射能測定用試料容器の断面図である。It is sectional drawing of the sample container for radioactivity measurement which concerns on embodiment of this invention. 本発明の実施の形態に係る放射能測定用試料容器に収容される放射線検出器の構成図である。It is a block diagram of the radiation detector accommodated in the sample container for radioactivity measurement which concerns on embodiment of this invention. 本発明の実施の形態に係る放射能測定用試料容器の直径Ｄ１に応じた全吸収ピーク効率の変化を、結晶寸法が異なる３つの放射線検出器に対して示すグラフ図である。It is a graph which shows the change of the total absorption peak efficiency according to the diameter D1 of the sample container for radioactivity measurement which concerns on embodiment of this invention with respect to three radiation detectors from which a crystal size differs.

以下、本発明の一実施形態に係る放射能測定用試料容器について添付図面を参照しながら説明する。   Hereinafter, a sample container for measuring radioactivity according to an embodiment of the present invention will be described with reference to the accompanying drawings.

本実施の形態による放射能測定用試料容器１０は、例えば図１に示すように、いわゆるマリネリ容器であって、有底円筒型の容器本体１１と、容器本体１１の中心軸Ｏに同軸に容器本体１１の底面１１Ａ上に設けられた円柱状凹部１２と、を備え、容器本体１１の内部に試料を収容可能である。   A radioactivity measurement sample container 10 according to the present embodiment is a so-called marinelli container as shown in FIG. 1, for example, and is a container having a bottomed cylindrical container body 11 and a container coaxially with a central axis O of the container body 11. A cylindrical recess 12 provided on the bottom surface 11 </ b> A of the main body 11, and a sample can be accommodated inside the container main body 11.

放射能測定用試料容器１０は、例えば図２に示すように、容器本体１１の内底面１１Ｂから内周壁面１１Ｃ上に設けられた試料の収容端１３までの内容積は１リットルである。
そして、容器本体１１の内周壁面１１Ｃの直径Ｄ１は１３０．６ｍｍ〜１３９ｍｍ、かつ円柱状凹部１２に応じて容器本体１１の内部に設けられる円柱状部１４の直径Ｄ２は８１ｍｍ〜９５ｍｍとされ、例えば直径Ｄ１＝１３５ｍｍかつ直径Ｄ２＝８９ｍｍである。
さらに、容器本体１１の内底面１１Ｂから収容端１３までの距離Ｌ１は９０ｍｍ〜１２９ｍｍ、かつ容器本体１１の内底面１１Ｂから円柱状部１４の先端面１４Ａまでの距離Ｌ２は７９ｍｍ〜１００ｍｍとされ、例えば距離Ｌ１＝１０４．１８ｍｍかつ距離Ｌ２＝７９ｍｍである。 For example, as shown in FIG. 2, the sample container 10 for measuring radioactivity has an internal volume of 1 liter from the inner bottom surface 11B of the container body 11 to the sample storage end 13 provided on the inner peripheral wall surface 11C.
The diameter D1 of the inner peripheral wall surface 11C of the container body 11 is 130.6 mm to 139 mm, and the diameter D2 of the columnar portion 14 provided inside the container body 11 according to the columnar recess 12 is 81 mm to 95 mm. For example, the diameter D1 = 135 mm and the diameter D2 = 89 mm.
Furthermore, the distance L1 from the inner bottom surface 11B of the container body 11 to the receiving end 13 is 90 mm to 129 mm, and the distance L2 from the inner bottom surface 11B of the container body 11 to the tip surface 14A of the cylindrical portion 14 is 79 mm to 100 mm. For example, the distance L1 = 104.18 mm and the distance L2 = 79 mm.

そして、放射能測定用試料容器１０の円柱状凹部１２は、２０％〜４０％の相対効率値を有する放射線検出器のエンドキャップ、例えば図３に示す放射線検出器２０のエンドキャップハウジング３１を収容可能に形成されている。   And the cylindrical recessed part 12 of the sample container 10 for radioactivity measurement accommodates the end cap of the radiation detector which has a relative efficiency value of 20%-40%, for example, the end cap housing 31 of the radiation detector 20 shown in FIG. It is made possible.

なお、放射線検出器２０は、例えばクローズドエンド同軸型のゲルマニウム半導体検出器であって、ゲルマニウム結晶３０と、エンドキャップハウジング３１と、エンドキャップハウジング３１内部の真空領域３２と、真空領域３２内にてゲルマニウム結晶３０を保持するクリスタルホルダ３３と、クリスタルホルダ３３に設けられた樹脂フィルム３４とを備えて構成されている。   The radiation detector 20 is, for example, a closed-end coaxial germanium semiconductor detector, and includes a germanium crystal 30, an end cap housing 31, a vacuum region 32 inside the end cap housing 31, and a vacuum region 32. A crystal holder 33 for holding the germanium crystal 30 and a resin film 34 provided on the crystal holder 33 are provided.

そして、放射線検出器２０は、例えば２０％〜４０％の相対効率値を有している。
有底の円筒形に形成されたゲルマニウム結晶３０は、放射線に対する有感領域３５と表面不感層３６とを備えている。
クリスタルホルダ３３により保持されたゲルマニウム結晶３０は、例えば放射線の入射窓（図示略）を有するエンドキャップハウジング３１の内部に収容され、このエンドキャップハウジング３１の内部は真空状態とされている。 The radiation detector 20 has a relative efficiency value of 20% to 40%, for example.
The germanium crystal 30 formed in a bottomed cylindrical shape includes a sensitive region 35 and a surface insensitive layer 36 for radiation.
The germanium crystal 30 held by the crystal holder 33 is accommodated in an end cap housing 31 having, for example, a radiation incident window (not shown), and the inside of the end cap housing 31 is in a vacuum state.

そして、例えば、ゲルマニウム結晶３０の直径Ａは４８ｍｍ〜６０ｍｍ、かつゲルマニウム結晶３０の長さＢは３０ｍｍ〜７０ｍｍとされている。   For example, the diameter A of the germanium crystal 30 is 48 mm to 60 mm, and the length B of the germanium crystal 30 is 30 mm to 70 mm.

クリスタルホルダ３３は開口部を有する箱型に形成され、クリスタルホルダ３３の内部にゲルマニウム結晶３０が収容された状態で、開口部は樹脂フィルム３４により閉塞されている。
そして、樹脂フィルム３４により閉塞された開口部がエンドキャップハウジング３１の入射窓に臨んで対向するようにして配置されている。 The crystal holder 33 is formed in a box shape having an opening, and the opening is closed by a resin film 34 in a state where the germanium crystal 30 is accommodated in the crystal holder 33.
The opening portion closed by the resin film 34 is disposed so as to face the incident window of the end cap housing 31.

この放射能測定用試料容器１０の各直径Ｄ１，Ｄ２および各距離Ｌ１，Ｌ２の寸法範囲は、例えば、２０％〜４０％の相対効率値を有する複数の放射線検出器に対して、放射能測定用試料容器１０の各直径Ｄ１，Ｄ２および各距離Ｌ１，Ｌ２を適宜に変化させた所定の演算によって設定されている。
この所定の演算は、環境放射能の測定に多用される複数の放射線検出器に対して系統的に実行され、例えば、γ線の輸送をモンテカルロ法などのシミュレーションにより演算して、この演算結果に基づいて放射線検出器のγ線に対する全吸収ピーク効率を算出するものなどである。
そして、放射能測定用試料容器１０の各直径Ｄ１，Ｄ２および各距離Ｌ１，Ｌ２の寸法範囲は、複数の放射線検出器、特に環境放射能の測定に多用される２０％〜４０％の相対効率値を有する複数の放射線検出器に対して、所望の検出効率を確保するようにして設定されている。 The size ranges of the diameters D1 and D2 and the distances L1 and L2 of the sample container 10 for measuring radioactivity are, for example, for a plurality of radiation detectors having a relative efficiency value of 20% to 40%. The diameters D1 and D2 and the distances L1 and L2 of the sample container 10 are set by predetermined calculations that are appropriately changed.
This predetermined calculation is systematically executed for a plurality of radiation detectors frequently used for measuring the environmental radioactivity. For example, the transport of γ rays is calculated by a simulation such as a Monte Carlo method, and the calculation result is calculated. Based on this, the total absorption peak efficiency with respect to γ rays of the radiation detector is calculated.
The size ranges of the diameters D1 and D2 and the distances L1 and L2 of the sample container 10 for measuring radioactivity are 20% to 40% relative efficiency frequently used for measurement of a plurality of radiation detectors, particularly environmental radioactivity. It is set so as to ensure a desired detection efficiency for a plurality of radiation detectors having values.

例えば図４においては、ゲルマニウム結晶３０の結晶寸法の直径Ｄおよび長さＬの組み合わせが異なる３つの放射線検出器（例えば、Ｄ／Ｌ＝０．８，１．０，１．４の３つの放射線検出器）の６６１ｋｅＶのγ線に対する全吸収ピーク効率と、放射能測定用試料容器１０の直径Ｄ１との対応関係を示した。
各放射線検出器に対して、放射能測定用試料容器１０の直径Ｄ１（ｘ）に応じた全吸収ピーク効率（ｙ）の変化を２次式で近似した場合に、各直径Ｄ１＝１３９．０ｍｍ，１３６．０ｍｍ，１３０．６ｍｍにおいて全吸収ピーク効率が極大になることが認められる。
これによって、環境放射能の測定に多用される２０％〜４０％の相対効率値を有する放射線検出器に対して、結晶寸法の直径Ｄおよび長さＬの組み合わせの範囲をＤ／Ｌ＝０．８〜１．４とすれば、放射能測定用試料容器１０の直径Ｄ１は１３０．６ｍｍ〜１３９ｍｍとなり、より好ましくは、ほぼ中央値の直径Ｄ１＝１３５ｍｍである。 For example, in FIG. 4, three radiation detectors having different combinations of the diameter D and the length L of the crystal dimensions of the germanium crystal 30 (for example, three radiations with D / L = 0.8, 1.0, 1.4). The correlation between the total absorption peak efficiency of the detector) for 661 keV γ rays and the diameter D1 of the sample container 10 for radioactivity measurement is shown.
When the change in the total absorption peak efficiency (y) corresponding to the diameter D1 (x) of the radioactivity measurement sample container 10 is approximated by a quadratic equation for each radiation detector, each diameter D1 = 139.0 mm , 136.0 mm, and 130.6 mm, it is recognized that the total absorption peak efficiency is maximized.
Thus, for a radiation detector having a relative efficiency value of 20% to 40%, which is frequently used for measurement of environmental radioactivity, the range of the combination of the crystal dimension diameter D and length L is D / L = 0. If it is set to 8-1.4, the diameter D1 of the sample container 10 for radioactivity measurement will be 130.6 mm-139 mm, More preferably, it is a substantially median diameter D1 = 135 mm.

上述したように、本実施の形態による放射能測定用試料容器１０によれば、各直径Ｄ１，Ｄ２および各距離Ｌ１，Ｌ２の寸法範囲は、例えば、２０％〜４０％の相対効率値を有する複数の放射線検出器に対して、放射能測定用試料容器１０の各直径Ｄ１，Ｄ２および各距離Ｌ１，Ｌ２を適宜に変化させた所定の演算によって設定されている。
これにより、複数の放射線検出器、特に環境放射能の測定に多用される２０％〜４０％の相対効率値を有する複数の放射線検出器に対して、所望の検出効率を容易に確保することができる。 As described above, according to the radioactivity measurement sample container 10 according to the present embodiment, the dimension ranges of the diameters D1 and D2 and the distances L1 and L2 have a relative efficiency value of 20% to 40%, for example. For each of the plurality of radiation detectors, the diameters D1 and D2 and the distances L1 and L2 of the radioactivity measurement sample container 10 are set by predetermined calculations.
Thereby, it is possible to easily ensure a desired detection efficiency for a plurality of radiation detectors, particularly a plurality of radiation detectors having a relative efficiency value of 20% to 40%, which is frequently used for measurement of environmental radioactivity. it can.

なお、上述した実施の形態において、放射線検出器２０をゲルマニウム半導体検出器としたが、これに限定されず、他の検出器であってもよい。   In the above-described embodiment, the radiation detector 20 is a germanium semiconductor detector. However, the present invention is not limited to this, and another detector may be used.

１０…放射能測定用試料容器 １１…容器本体 １１Ａ…底面 １１Ｂ…内底面 １１Ｃ…内周壁面 １２…円柱状凹部 １３…収容端 １４…円柱状部 １４Ａ…先端面 DESCRIPTION OF SYMBOLS 10 ... Sample container for a radioactivity measurement 11 ... Container main body 11A ... Bottom surface 11B ... Inner bottom surface 11C ... Inner peripheral wall surface 12 ... Cylindrical recessed part 13 ... Storage end 14 ... Cylindrical part 14A ... Tip surface

Claims (2)

有底円筒型の容器本体と、該容器本体の中心軸に同軸に前記容器本体の底面上に設けられた円柱状凹部と、を備え、前記容器本体の内部に放射能測定用試料を収容可能な放射能測定用試料容器であって、
前記容器本体の内周壁面の直径は１３０．６ｍｍ〜１３９ｍｍ、かつ前記円柱状凹部に応じて前記容器本体の内部に設けられる円柱状部の直径は８１ｍｍ〜９５ｍｍ、かつ前記容器本体の内底面から前記内周壁面上に設けられた前記放射能測定用試料の収容端までの距離は９０ｍｍ〜１２９ｍｍ、かつ前記容器本体の内底面から前記円柱状部の先端面までの距離は７９ｍｍ〜１００ｍｍ、かつ前記容器本体の内底面から前記収容端までの内容積は１リットルであることを特徴とする放射能測定用試料容器。 A bottomed cylindrical container body, and a cylindrical recess provided on the bottom surface of the container body coaxially with the central axis of the container body, the sample for measuring radioactivity can be accommodated inside the container body A sample container for measuring radioactivity,
The diameter of the inner peripheral wall surface of the container body is 130.6 mm to 139 mm, and the diameter of the columnar portion provided inside the container body according to the columnar recess is 81 mm to 95 mm, and from the inner bottom surface of the container body The distance from the receiving end of the radioactivity measurement sample provided on the inner peripheral wall surface is 90 mm to 129 mm, and the distance from the inner bottom surface of the container body to the tip surface of the cylindrical portion is 79 mm to 100 mm, and A sample container for measuring radioactivity, wherein an inner volume from an inner bottom surface of the container body to the accommodation end is 1 liter. 前記円柱状凹部は、２０％〜４０％の相対効率値を有する放射線検出器のエンドキャップを収容可能であり、
前記放射線検出器の結晶の直径は４８ｍｍ〜６０ｍｍ、かつ前記結晶の長さは３０ｍｍ〜７０ｍｍであることを特徴とする請求項１に記載の放射能測定用試料容器。 The cylindrical recess can accommodate an end cap of a radiation detector having a relative efficiency value of 20% to 40%,
The radioactivity measurement sample container according to claim 1, wherein the radiation detector has a crystal diameter of 48 mm to 60 mm and a length of the crystal of 30 mm to 70 mm.
JP2012244463A 2012-03-09 2012-11-06 Radiation measurement sample container Pending JP2013213806A (en)

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