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JPH0520710B2 - - Google Patents
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JPH0520710B2 - - Google Patents

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Publication number
JPH0520710B2
JPH0520710B2 JP10324288A JP10324288A JPH0520710B2 JP H0520710 B2 JPH0520710 B2 JP H0520710B2 JP 10324288 A JP10324288 A JP 10324288A JP 10324288 A JP10324288 A JP 10324288A JP H0520710 B2 JPH0520710 B2 JP H0520710B2
Authority
JP
Japan
Prior art keywords
hollow straight
straight pipe
gamma ray
gamma rays
radioactivity
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired - Lifetime
Application number
JP10324288A
Other languages
Japanese (ja)
Other versions
JPH01274094A (en
Inventor
Masaki Katagiri
Naoaki Wakayama
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
National Institute of Advanced Industrial Science and Technology AIST
Original Assignee
Agency of Industrial Science and Technology
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Agency of Industrial Science and Technology filed Critical Agency of Industrial Science and Technology
Priority to JP10324288A priority Critical patent/JPH01274094A/en
Publication of JPH01274094A publication Critical patent/JPH01274094A/en
Publication of JPH0520710B2 publication Critical patent/JPH0520710B2/ja
Granted legal-status Critical Current

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  • Measurement Of Radiation (AREA)

Description

【発明の詳細な説明】 [産業上の利用分野] 本発明は、水中にある構造物の放射能濃度を中
空の直管を用いて遠方より非破壊的に定量測定す
る方法の改良に関するものである。当該測定法
は、目的とする構造物の測定箇所に先端を板で封
じた中空の管を近接し水を遮蔽体としてガンマ線
コリメータを形成し、測定箇所から放出されるガ
ンマ線を直管中を通過させ、反対側に置かれたガ
ンマ線スペクトル検出器に導き計測し、このスペ
クトル解析結果をもとに当該構造物の放射能濃度
を求めるものである。
[Detailed Description of the Invention] [Industrial Application Field] The present invention relates to an improvement in a method for non-destructively and quantitatively measuring the radioactivity concentration of structures in water from a distance using a hollow straight pipe. be. In this measurement method, a hollow tube whose tip is sealed with a plate is placed close to the measurement point of the target structure, forming a gamma ray collimator using water as a shield, and the gamma rays emitted from the measurement point are passed through the straight tube. The radioactivity concentration of the structure is determined based on the spectrum analysis results.

[従来の技術] 従来、当該測定法は第1図に示すように、目的
とする構造物の測定箇所1に先端を板2で封じた
中空の直管3を近接し、水4を遮蔽体としてガン
マ線コリメータ5を構成し、測定箇所から放出さ
れるガンマ線6を直管中を通過させ、反対側に置
かれたガンマ線スペクトル検出器7に導き計測
し、このガンマ線スペクトルを解析して得られる
ガンマ線計数結果をもとに構造物の放射能濃度を
求めてきた。
[Prior Art] Conventionally, as shown in Fig. 1, the measurement method involves placing a hollow straight pipe 3 whose tip is sealed with a plate 2 in close proximity to a measurement point 1 of a target structure, and blocking water 4 with a shield. The gamma ray collimator 5 is configured as a gamma ray collimator 5, and the gamma rays 6 emitted from the measurement point are passed through a straight tube, guided to the gamma ray spectrum detector 7 placed on the opposite side, and measured, and the gamma rays obtained by analyzing this gamma ray spectrum. Radioactivity concentrations in structures have been determined based on the counting results.

[発明が解決しようとする課題] 従来の定量測定法により中空の直管を使用して
水中の構造物の放射能を測定する場合第2図に示
すように、水中8において中空の直管9の長さが
長くまた挿入角度10が大きくなると浮力により
中空の直管が曲りその直進性を確保することは非
常に難かしくなるため、中空の直管が望む構造物
の測定箇所11から放出されるガンマ線12を他
端に置かれたガンマ線スペクトル検出器13によ
り完全に測定することは困難となり定量測定がで
きなくなる問題点があつた。
[Problems to be Solved by the Invention] When measuring the radioactivity of underwater structures using a hollow straight pipe according to the conventional quantitative measurement method, as shown in FIG. If the length is long and the insertion angle 10 is large, the hollow straight pipe will bend due to buoyancy and it will be very difficult to ensure its straightness. There was a problem in that it was difficult to completely measure the gamma rays 12 at the other end using the gamma ray spectrum detector 13 placed at the other end, making quantitative measurements impossible.

[課題を解決するための手段] 本発明の測定方法の一つは、中空の直管の直進
性が得られなくなつた場合でも、基準となる円板
状のガンマ線線源を用いることによつて測定した
ガンマ線計測結果を較正し、目標としている構造
物の放射能濃度を求めることを特徴とするもので
ある。
[Means for Solving the Problems] One of the measurement methods of the present invention is to use a disc-shaped gamma ray source as a reference, even when the straightness of a hollow straight pipe cannot be obtained. This method is characterized by calibrating the gamma ray measurement results obtained using the method and determining the radioactivity concentration of the target structure.

本発明の測定方法の他の一つは、中空の直管の
先端に置いた円板状の光源をガンマ線スペクトル
検出器の直前でモニタしその投影面積をもとにガ
ンマ線スペクトル検出器によつて計測されたガン
マ線計数を補正し、水中において中空の直管が曲
がつた場合にも構造物の放射能濃度を定量できる
ことを特徴としている。
Another measurement method of the present invention is to monitor a disc-shaped light source placed at the tip of a hollow straight tube in front of a gamma-ray spectrum detector, and then use the gamma-ray spectrum detector to detect the projected area of the light source. The system corrects the measured gamma ray counts and is characterized by the ability to quantify the radioactivity concentration in structures even when a hollow straight pipe is bent underwater.

[実施例] 本発明の前者の測定方法を図によつて説明す
る。
[Example] The former measuring method of the present invention will be explained with reference to the drawings.

本発明の原理図(実施例)を第3図に示す。水
中14に挿入された先端を板15で封じた中空の
直管16の先端部17に直管内径と同じ直径18
の円板状で一様な放射能分布を持ちかつ測定する
放射能と異なるエネルギーのガンマ線を放出する
標準線源19を装着する。使用する放射能核種は
測定する核種以外のものから1種類以上を選択す
る。この線源を第3図に示すように封じ切り板に
固定する。この場合、中空の直管が望む構造物の
測定箇所20から放出されるガンマ線がガンマ線
スペクトル検出器に入射する時の幾何学条件と当
該円板状線源から放出されるガンマ線がガンマ線
スペクトル検出器21に入射する時の幾何条件2
2が同等になる。従つて、中空の配管の直進性が
得られなくなり、一部のガンマ線が中空の配管及
び周囲を取り巻く水によつて吸収されても、中空
の直管が望む構造物の測定箇所から放出されるガ
ンマ線及び円板状の標準線源から放出されるガン
マ線ともガンマ線スペクトル検出器まで到達する
までに同じ比率で減少する。
A principle diagram (embodiment) of the present invention is shown in FIG. A diameter 18 having the same diameter as the inner diameter of the straight pipe is attached to the distal end 17 of a hollow straight pipe 16 whose distal end is sealed with a plate 15 inserted into the water 14.
A standard radiation source 19 is mounted, which has a disc shape and emits gamma rays having a uniform distribution of radioactivity and having an energy different from that of the radioactivity to be measured. As the radioactive nuclide to be used, one or more types are selected from those other than the nuclide to be measured. This radiation source is fixed to a sealing plate as shown in FIG. In this case, the geometric conditions when the gamma rays emitted from the measurement point 20 of the structure where the hollow straight pipe is desired are incident on the gamma ray spectrum detector, and the gamma rays emitted from the disc-shaped source are the gamma ray spectrum detector. Geometric condition 2 when incident on 21
2 will be equivalent. Therefore, the straightness of the hollow pipe cannot be obtained, and even though some gamma rays are absorbed by the hollow pipe and the surrounding water, the hollow straight pipe is emitted from the desired measurement point of the structure. Both the gamma rays and the gamma rays emitted from the disc-shaped standard radiation source are reduced at the same rate by the time they reach the gamma ray spectrum detector.

このため、標準線源の放射能核種として、放射
能濃度が既知の種々のエネルギーのガンマ線を放
出する核種を使用し、ガンマ線スペクトル検出器
のガンマ線エネルギーに対する検出効率を求め、
この検出効率をもとに中空の直管が望む構造物の
測定箇所から放出されるガンマ線を較正すれば、
中空の直管の直進性が完全に得られなくても構造
物の放射能濃度を定量測定することが可能とな
る。
For this reason, we used nuclides that emit gamma rays of various energies with known radioactive concentrations as the radioactive nuclides of the standard radiation source, and determined the detection efficiency of the gamma ray spectrum detector for gamma ray energies.
If the hollow straight pipe calibrates the gamma rays emitted from the desired measurement point of the structure based on this detection efficiency,
Even if the straightness of the hollow straight pipe cannot be completely achieved, it becomes possible to quantitatively measure the radioactivity concentration of the structure.

また、本発明の定量測定法を使用すれば、長さ
を変えることのできる中空の管を使用した場合で
も自動的に上記円板状標準線源によつて検出効率
が求まるためどの位置でも定量測定ができる。
In addition, by using the quantitative measurement method of the present invention, even when using a hollow tube whose length can be changed, the detection efficiency is automatically determined using the disc-shaped standard radiation source, so quantification can be performed at any position. Can be measured.

本発明の後者の測定方法を図によつて説明す
る。
The latter measuring method of the present invention will be explained with reference to the drawings.

本発明の原理図(実施例)を第4図に示す。中
空の直管23、封じ切り板24、円板状の光源2
5、反射板26、投影板27、ガンマ線スペクト
ル検出器28から構成される。円板状の光源は、
中空の管の内径と同じ直径の光源とする。この光
源を第4図に示すように中空の直管の先端内部に
固定する。この場合、中空の直管が十分長い場合
には、中空の直管が望んだ構造物の測定箇所29
から放出されたガンマ線がガンマ線スペクトル検
出器に入射する時の幾何学条件と円状の光源から
放出される光が反射板で反射され投影板に映され
る時の幾何学条件が同等になる。従つて、中空の
直管が浮力等により曲り直進性が得られなくな
り、一部のガンマ線が中空の直管によつて吸収さ
れても、中空の直管が望んだ構造物の測定箇所か
ら放出されたガンマ線及び円状の光源から放出さ
れる光源とも、他端にあるガンマ線スペクトル検
出器及び投影板まで到達するまでに同じ比率で減
少するので、この比率をもとにガンマ線計数結果
を補正すれば、中空の直管の直進性が完全に得ら
れなくなつても、構造物の放射能を精度良く測定
できる。また、反射板については、薄いものを使
用しかつ材質及びその厚さが分かつていればガン
マ線の吸収補正を行うことができるため、測定中
も外す必要はない。
A principle diagram (embodiment) of the present invention is shown in FIG. Hollow straight pipe 23, sealing plate 24, disc-shaped light source 2
5, a reflection plate 26, a projection plate 27, and a gamma ray spectrum detector 28. The disc-shaped light source is
The light source has the same diameter as the inner diameter of the hollow tube. This light source is fixed inside the tip of a hollow straight tube as shown in FIG. In this case, if the hollow straight pipe is long enough, the hollow straight pipe can be used at the desired measurement point 29 of the structure.
The geometric conditions when the gamma rays emitted from the circular light source enter the gamma ray spectrum detector are the same as the geometric conditions when the light emitted from the circular light source is reflected by the reflector and projected onto the projection plate. Therefore, even if the hollow straight pipe bends due to buoyancy or other factors and becomes unable to travel straight, and some gamma rays are absorbed by the hollow straight pipe, the hollow straight pipe will still emit it from the desired measurement location of the structure. Both gamma rays emitted from the circular light source and the light source emitted from the circular light source decrease at the same rate before reaching the gamma ray spectrum detector and projection plate at the other end, so the gamma ray counting results should be corrected based on this ratio. For example, even if the straightness of a hollow straight pipe cannot be achieved completely, the radioactivity of the structure can be measured with high accuracy. Furthermore, as long as a thin reflector is used and the material and thickness are known, gamma ray absorption correction can be performed, so there is no need to remove it during measurement.

[発明の効果] 本発明により、直管の直進性が損なわれても水
中の構造物の放射能濃度を定量測定することが可
能となつたため、直管の厚ち等を厚くすることな
く水中の深い場所に置かれた構造物の放射能濃度
を求めることが可能となつた。また、検出効率も
測定ごとに同時に測定されるため、測定精度を上
げることができる。
[Effect of the invention] The present invention makes it possible to quantitatively measure the radioactivity concentration of underwater structures even if the straightness of straight pipes is impaired. It has now become possible to determine the radioactivity concentration of structures placed at deep locations. Moreover, since detection efficiency is also measured simultaneously for each measurement, measurement accuracy can be improved.

【図面の簡単な説明】[Brief explanation of drawings]

第1図は従来の放射能定量測定法の原理図であ
る。第2図は従来の放射能定量測定法により水中
の深い場所にある構造物の放射能濃度を測定した
例である。第3図は本発明の原理図(実施例)で
ある。第4図は本発明の原理図(実施例)であ
る。 14…水、15…封じ切り板、16…中空の直
管、17…先端部、18…直管内径と同じ直径、
19…円板状で一様な放射能分布を持ちかつ測定
する放射能と異なるエネルギーのガンマ線を放出
する標準線源、20…中空の直管が望む構造物の
測定箇所、21…ガンマ線スペクトル検出器、2
2…円板状線源から放出されるガンマ線がガンマ
線検出器に入射する時の幾何学条件、23…中空
の直管、24…封じ切り板、25…円板状の光
源、26…反射板、27…投影板、28…ガンマ
線スペクトル検出器、29…中空の直管が望む構
造物の測定箇所。
FIG. 1 is a diagram showing the principle of a conventional quantitative radioactivity measurement method. Figure 2 is an example of measuring the radioactivity concentration of a structure located deep underwater using the conventional quantitative radioactivity measurement method. FIG. 3 is a diagram (embodiment) of the principle of the present invention. FIG. 4 is a principle diagram (embodiment) of the present invention. 14...Water, 15...Sealing plate, 16...Hollow straight pipe, 17...Tip part, 18...Same diameter as the straight pipe inner diameter,
19...Standard radiation source that is disc-shaped and has a uniform radioactivity distribution and emits gamma rays with energy different from the radioactivity to be measured, 20...Measurement location of a structure where a hollow straight pipe is desired, 21...Gamma ray spectrum detection vessel, 2
2...Geometric conditions when gamma rays emitted from the disc-shaped source enter the gamma-ray detector, 23...Hollow straight tube, 24...Sealing plate, 25...Disc-shaped light source, 26...Reflector plate , 27... Projection plate, 28... Gamma ray spectrum detector, 29... Measurement location of the structure where a hollow straight pipe is desired.

Claims (1)

【特許請求の範囲】 1 水中にある構造物の表面に先端を板で封じた
中空の直管を近接し、水を遮蔽体としてガンマ線
コリメータを構成し、当該構造物から放出される
ガンマ線を直管内部を通過させ他端に置かれたガ
ンマ線スペクトル検出器によつて計測し当該構造
物の放射能濃度を定量測定する方法において、先
端を板で封じた中空の直管の先端部に直管内径と
同じ直径の円板状で一様な放射能分布を持ちかつ
測定する放射能と異なるエネルギーのガンマ線を
放出する標準線源を装着し当該標準線源から放出
されるガンマ線と中空の直管が望む構造物の測定
箇所から放出されるガンマ線とを同時に中空の直
管の他端においたガンマ線スペクトル検出器によ
つて計測し、当該円板状標準線源から放出される
ガンマ線の計測結果から得られる検出効率曲線を
もとに中空の直管が望む構造物の測定箇所から放
出されるガンマ線の計測結果を較正することによ
つて測定箇所の放射能濃度を求める水中構造物放
射能定量測定法。 2 水中にある構造物の表面に先端を板で封じた
中空の直管を近接し、水を遮蔽体としてガンマ線
コリメータを構成し、当該構造物から放出される
ガンマ線を直管内部を通過させ他端に置かれたガ
ンマ線スペクトル検出器によつて計測し当該構造
物の放射能濃度を定量測定する方法において、先
端を板で封じた中空の直管の先端内部に、直管の
内径と同じ直径の円板状の光源を置き、他端のガ
ンマ線スペクトル検出器の直前に置かれた反射板
及び投影板を用いてこの円板状の光源の形状を映
し、全ての光源が見える時を基準に、中空の直管
が曲がることによつて減少する投影面積の割合を
求め、この割合をもとにガンマ線スペクトル検出
器によつて計測された中空の直管が望んだ構造物
の測定箇所から放出されたガンマ線計数結果を補
正し、中空の直管が水中で曲がり完全に構造物か
ら放出されたガンマ線を計測できない場合でも構
造物の放射能濃度を定量可能とする水中構造物放
射能定量法。
[Claims] 1. A gamma ray collimator is configured by placing a hollow straight pipe whose tip is sealed with a plate close to the surface of a structure in water, using water as a shield, and directly directing gamma rays emitted from the structure. In the method of quantitatively measuring the radioactivity concentration of the structure by passing through the inside of the tube and measuring with a gamma ray spectrum detector placed at the other end, a straight tube is placed at the tip of a hollow straight tube whose tip is sealed with a plate. A standard radiation source that is disc-shaped with the same diameter as the inner diameter and has a uniform radioactivity distribution and emits gamma rays with energy different from the radioactivity to be measured is attached, and the gamma rays emitted from the standard radiation source and the hollow straight tube are attached. The gamma rays emitted from the desired measurement point of the structure are simultaneously measured by a gamma ray spectrum detector placed at the other end of the hollow straight tube, and from the measurement results of the gamma rays emitted from the disc-shaped standard radiation source. Quantitative measurement of radioactivity in underwater structures to determine the radioactivity concentration at the measurement point by calibrating the measurement results of gamma rays emitted from the measurement point of the structure using a hollow straight pipe based on the obtained detection efficiency curve. Law. 2. A gamma ray collimator is constructed by placing a hollow straight pipe whose tip is sealed with a plate close to the surface of an underwater structure, using water as a shield, and allowing the gamma rays emitted from the structure to pass through the inside of the straight pipe. In the method of quantitatively measuring the radioactivity concentration of the structure by measuring with a gamma ray spectrum detector placed at the end, a tube with the same diameter as the inner diameter of the straight pipe is placed inside the tip of a hollow straight pipe whose tip is sealed with a plate. A disc-shaped light source is placed, and the shape of this disc-shaped light source is projected using a reflection plate and a projection plate placed just in front of the gamma ray spectrum detector at the other end, and the time when all the light sources are visible is used as a reference. , find the percentage of the projected area that decreases due to bending of the hollow straight pipe, and based on this percentage, calculate the amount of light emitted from the desired measurement point of the structure by the hollow straight pipe measured by the gamma ray spectrum detector. A method for quantifying radioactivity in underwater structures that corrects the gamma ray counting results and makes it possible to quantify the radioactivity concentration in structures even when the gamma rays emitted from the structure cannot be measured completely due to hollow straight pipes bending underwater.
JP10324288A 1988-04-26 1988-04-26 Method for measuring quantity of radioactivity in underwater structure Granted JPH01274094A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP10324288A JPH01274094A (en) 1988-04-26 1988-04-26 Method for measuring quantity of radioactivity in underwater structure

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP10324288A JPH01274094A (en) 1988-04-26 1988-04-26 Method for measuring quantity of radioactivity in underwater structure

Publications (2)

Publication Number Publication Date
JPH01274094A JPH01274094A (en) 1989-11-01
JPH0520710B2 true JPH0520710B2 (en) 1993-03-22

Family

ID=14348971

Family Applications (1)

Application Number Title Priority Date Filing Date
JP10324288A Granted JPH01274094A (en) 1988-04-26 1988-04-26 Method for measuring quantity of radioactivity in underwater structure

Country Status (1)

Country Link
JP (1) JPH01274094A (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP6443987B2 (en) * 2014-05-08 2018-12-26 有限会社 川原商会 Radiation shielding ability test method and container used therefor

Also Published As

Publication number Publication date
JPH01274094A (en) 1989-11-01

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