Deprecated: The each() function is deprecated. This message will be suppressed on further calls in /home/zhenxiangba/zhenxiangba.com/public_html/phproxy-improved-master/index.php on line 456
JPH0616102B2 - Method and apparatus for measuring the depthwise distribution of gamma ray emitting nuclides existing inside a wall such as concrete - Google Patents
[go: Go Back, main page]

JPH0616102B2 - Method and apparatus for measuring the depthwise distribution of gamma ray emitting nuclides existing inside a wall such as concrete - Google Patents

Method and apparatus for measuring the depthwise distribution of gamma ray emitting nuclides existing inside a wall such as concrete

Info

Publication number
JPH0616102B2
JPH0616102B2 JP12483986A JP12483986A JPH0616102B2 JP H0616102 B2 JPH0616102 B2 JP H0616102B2 JP 12483986 A JP12483986 A JP 12483986A JP 12483986 A JP12483986 A JP 12483986A JP H0616102 B2 JPH0616102 B2 JP H0616102B2
Authority
JP
Japan
Prior art keywords
wall
ray emitting
concrete
depth direction
measuring
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 - Fee Related
Application number
JP12483986A
Other languages
Japanese (ja)
Other versions
JPS62282288A (en
Inventor
茂生 沼田
鉄夫 斉藤
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.)
Shimizu Construction Co Ltd
Original Assignee
Shimizu Construction Co Ltd
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 Shimizu Construction Co Ltd filed Critical Shimizu Construction Co Ltd
Priority to JP12483986A priority Critical patent/JPH0616102B2/en
Publication of JPS62282288A publication Critical patent/JPS62282288A/en
Publication of JPH0616102B2 publication Critical patent/JPH0616102B2/en
Anticipated expiration legal-status Critical
Expired - Fee Related legal-status Critical Current

Links

Landscapes

  • 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、原子力施設等におけるコンクリート等の内部
に存在するγ線放出核種の深さ方向の分布を測定する方
法及び装置に関する。
The present invention relates to a method and apparatus for measuring the depthwise distribution of γ-ray emitting nuclides existing inside concrete or the like in nuclear facilities and the like.

〔従来の技術〕[Conventional technology]

原子炉等の原子力施設を解体する場合に、コンクリート
中の、γ線放出核種のような放射性核種の存在量、分布
を解体前に調査しておくことは解体作業時の被爆低減の
ために重要なことである。その推定方法としては、従
来、大型計算機を駆使して大規模な計算を行ったり、或
いは計算精度の確認のため実際に現場でコンクリート型
のコアボーリングを実施し、サンプルを採取して測定を
行っていた。
When dismantling nuclear facilities such as nuclear reactors, it is important to investigate the abundance and distribution of radionuclides such as γ-ray emitting nuclides in concrete before dismantling to reduce exposure during dismantling work. That's right. As the estimation method, conventionally, a large-scale computer was used to perform large-scale calculation, or concrete type core boring was actually performed on site to confirm the calculation accuracy, and samples were taken and measured. Was there.

〔発明が解決しようとする問題点〕[Problems to be solved by the invention]

しかしながら、大型計算機を用いた大規模な計算による
方法は費用がかかり、その精度も明確でない。また、コ
アボーリングしてサンプルを一個一個測定する方法は、
精度は高いが何ヶ所もコアボーリング行うため長時間を
要していまう欠点がある。
However, the method of large-scale calculation using a large-scale computer is expensive and its accuracy is not clear. In addition, the method of measuring each sample by core boring is
The accuracy is high, but it has a drawback that it takes a long time because core boring is performed at several places.

本発明は上記問題点を解決するためのものであって、簡
便で且つ精度よくコンクリート等壁体内部のγ線放出核
種の深さ方向の分布を測定することができる方法及び装
置を提供することを目的とする。
The present invention is to solve the above problems, and provides a method and an apparatus capable of simply and accurately measuring the distribution of γ-ray emitting nuclides in the depth direction inside a wall such as concrete. With the goal.

〔問題点を解決するための手段〕[Means for solving problems]

そのために、本発明のコンクリート等の壁体内部に存在
するγ線放出核種の深さ方向の分布を測定する方法及び
装置は、内部にγ線放出核種が存在する壁体の表面から
の距離を変えて、ある1つの核種に注目してn回放射線
測定し、そのときのn個の測定値C、C……C
ら、壁体深さ方向のγ線放出核種の存在量N、N
…Nを、 但し ε:あるγ線放出核種のγ線エネルギーに対する検出器
の検出効率 λ:そのγ線放出核種のγ線エネルギーに対する壁体の
線減衰係数 t:壁体中の透過距離 B:透過距離tの壁体に体するビルドアップ係数 r:壁体から検出器までの距離 の多元連立一次方程式から求めること、及び放射線測定
器と、放射線測定器を、内部にγ線放出核種が存在する
壁体の表面に対して垂直方向に移動させる測定器駆動装
置と、壁体表面との距離がそれぞれ異なる測定位置で得
られた核測定値が入力される演算装置とを備え、前記演
算装置は、各測定値と壁体深さ方向に分布するγ線放出
核種の存在量との間の多元連立一次方程式を解くことに
より壁体深さ方向に分布するγ線放出核種の存在量を算
出することを特徴とする。
Therefore, the method and apparatus for measuring the distribution in the depth direction of the γ-ray emitting nuclide existing inside the wall body such as concrete of the present invention, the distance from the surface of the wall body in which the γ-ray emitting nuclide exists inside. Instead, one radionuclide is focused on and measured n times, and from the n measured values C 1 , C 2 ... C n at that time, the abundance N of the γ-ray emitting radionuclides in the depth direction of the wall is determined. 1 , N 2 ...
... N n However ε: Detection efficiency of the detector for γ-ray energy of a certain γ-ray emitting nuclide λ: Linear attenuation coefficient of the wall for γ-ray energy of the γ-ray emitting nuclide t n : Transmission distance in the wall B n : Transmission distance t build-up factor Karadasuru in the wall of the n r n: be determined from multiple simultaneous linear equations of the distance from the wall to the detector, and a radiation measuring instrument, a radiation measuring instrument, there are γ-ray emitting nuclide inside A measuring device driving device that moves in a direction perpendicular to the surface of the wall body, and a computing device to which the nuclear measurement values obtained at measurement positions with different distances from the wall surface are input, and the computing device is , Calculate the abundance of γ-ray emitting nuclides distributed in the wall depth direction by solving a multi-dimensional simultaneous linear equation between each measured value and the abundance of γ-ray emitting nuclides distributed in the wall depth direction It is characterized by

〔作用〕[Action]

本発明のコンクリート等の壁体内部に存在するγ線放出
核種の深さ方向の分布を測定する方法及び装置は、γ線
を放出する核種だけに注目し、コンクリート等の壁体外
部から、壁体表面との距離を変えて複数回放射線を測定
し、各測定値と壁体深さ方向に分布するγ線放出核種の
存在量との間に成立する多元連立一次方程式を解くこと
により壁体深さ方向に分布するγ線放出核種の存在量を
極めて容易に、且つ精度良くもとめることができる。
The method and apparatus for measuring the distribution in the depth direction of the γ-ray emitting nuclide existing inside the wall body such as concrete of the present invention focuses on only the nuclide that emits γ-rays, from the outside of the wall body such as concrete, the wall By measuring the radiation multiple times by changing the distance from the body surface, and solving the multi-dimensional simultaneous linear equation that holds between each measured value and the abundance of γ-ray emitting nuclides distributed in the wall depth direction The existing amount of γ-ray emitting nuclides distributed in the depth direction can be obtained very easily and accurately.

〔実施例〕〔Example〕

以下、図面を参照しつつ実施例を説明する。 Hereinafter, embodiments will be described with reference to the drawings.

第1図は本発明によるγ線放出核種の存在量の測定原理
を説明するための図で、図中、1は測定器、2は遮蔽
体、3はコンクリート表面、4は測定対象領域である。
FIG. 1 is a diagram for explaining the principle of measuring the amount of γ-ray emitting nuclides according to the present invention, in which 1 is a measuring instrument, 2 is a shield, 3 is a concrete surface, and 4 is a measurement target region. .

図において、測定対象以外からのγ線を遮蔽するために
周囲に充分な遮蔽体2を備えたγ線測定器1、例えばG
e検出器をコンクリート表面3から距離rだけ離して
測定する。コンクリート中に存在するγ線放出核種(例
えば60)は、どの部分にもまなく存在しているが、
コンクリートの深さ方向に、有限の体積を持ったメッシ
ュに分割したとき、メッシュの中心位置t、t…t
にかたまって存在しているものとする。いま、60
の位置tにある量をN1、位置tにある量をN2、……
位置tにある量をNとすると、コンクリート表面か
らrだけ離れた位置での測定値Cは次式のように表
わせる。
In the figure, a γ-ray measuring device 1 provided with a sufficient shield 2 around the γ-ray from other than the measurement target, for example, G
e The detector is measured at a distance r i from the concrete surface 3. Γ-ray emitting nuclides (eg 60 C 0 ) present in concrete are present in all parts,
When the mesh is divided into meshes having a finite volume in the depth direction of the concrete, the center positions of the meshes t 1 , t 2, ... T
It is assumed that n exists and exists. Now, 60 C 0
The amount at the position t 1 of N 1 , the amount at the position t 2 of N 2 , ...
Assuming that the quantity at the position t n is N n , the measured value C i at a position distant from the concrete surface by r i can be expressed by the following equation.

ここで、 ε:60のγ線エネルギーに対する検出器の検出効率 λ:60のγ線エネルギーに対するコンクリートの線
減衰係数 B:透過距離tのコンクリートに対するビルドアッ
プ係数 同様な測定をコンクリート表面3からの距離rを変え
てn回行えば測定値Cもn個求まる。この測定値 60の量 との関係は、行列表現で表すのと次式のようになる。
Here, epsilon: 60 detection efficiency of the detector to γ-ray energy of C 0 lambda: 60 linear attenuation coefficient of the concrete for the γ-ray energy of C 0 B n: the build-up factor similar measurement for concrete transmission distance t n If the distance r i from the concrete surface 3 is changed and the measurement is performed n times, n measurement values C i can be obtained. This measurement And the amount of 60 C 0 The relationship between and is expressed by the matrix expression and the following expression.

ここで行列Rは、 である。したがってあらかじめ行列Rを求めておけば測
定値 から60の量 が求まる。
Where the matrix R is Is. Therefore, if the matrix R is obtained in advance, the measured value To 60 C 0 amount Is required.

第2図は第1図で示した測定原理に基づく測定装置の一
実施例を示す図で、第1図と同一参照番号は同一内容を
示しており、5は測定器駆動装置、6は演算装置であ
る。
FIG. 2 is a diagram showing an embodiment of a measuring device based on the measuring principle shown in FIG. 1, the same reference numerals as those in FIG. 1 indicate the same contents, 5 is a measuring device driving device, and 6 is a calculation. It is a device.

図において、測定器駆動装置5により、測定器1の位置
を移動し、コンクリート表面3からの距離rを変えて
n回測定値を行い、そのときのn個の測定値Cをミニ
コン等の演算装置6に入力する。演算装置6には前述し
た行列Rが記憶されており、n個の測定値Cから、前
述した多元連立一次方程式を解くことによりコンクリー
ト深さ方向各位置における60の量を算出する。
In the figure, the measuring instrument driving device 5 moves the position of the measuring instrument 1 to change the distance r i from the concrete surface 3 to perform the measurement value n times, and the n measurement values C i at that time are compared to the minicomputer etc. Is input to the arithmetic unit 6. The above-mentioned matrix R is stored in the arithmetic unit 6, and the amount of 60 C 0 at each position in the concrete depth direction is calculated by solving the above-mentioned multi-dimensional simultaneous linear equation from the n measured values C i .

〔発明の効果〕〔The invention's effect〕

以上のように本発明によれば、大型計算機を用いた大規
模な計算によらず、また、コアボーリングもせずに、簡
便で且つ精度よくコンクリート内のγ線放出核種の深さ
方向の分布を測定することができる。
As described above, according to the present invention, the depthwise distribution of γ-ray emitting nuclides in concrete can be easily and accurately obtained without relying on a large-scale calculation using a large-scale computer and without core boring. Can be measured.

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

第1図は本発明によるコンクリート内のγ線放出核種の
存在量の測定原理を説明するための図、第2図は第1図
で示した測定原理に基づく測定装置の一実施例を示す図
である。 1……測定器、2……遮蔽体、3……コンクリート表
面、4……測定対象領域、5……測定器駆動装置、6…
…演算装置
FIG. 1 is a diagram for explaining the principle of measuring the amount of γ-ray emitting nuclide in concrete according to the present invention, and FIG. 2 is a diagram showing an embodiment of a measuring device based on the measuring principle shown in FIG. Is. 1 ... Measuring instrument, 2 ... Shield, 3 ... Concrete surface, 4 ... Measurement target area, 5 ... Measuring instrument drive device, 6 ...
… Arithmetic device

Claims (3)

【特許請求の範囲】[Claims] 【請求項1】内部にγ線放出核種が存在する壁体の表面
からの距離を変えて、ある1つの核種に注目してn回放
射線測定し、そのときのn個の測定値C、C……C
から、壁体深さ方向のそのγ線放出核種の存在量
、N……Nを、 但し ε:あるγ線放出核種のγ線エネルギーに対する検出器
の検出効率 λ:そのγ線放出核種のγ線エネルギーに対する壁体の
線減衰係数 t:壁体中の透過距離 B:透過距離tの壁体に体するビルドアップ係数 r:壁体から検出器までの距離 の多元連立一次方程式から求めることを特徴とするコン
クリート等の壁体内部に存在するγ線放出核種の深さ方
向の分布を測定する方法。
1. Radiation measurement is performed n times by focusing on a certain nuclide while changing the distance from the surface of the wall in which the γ-ray emitting nuclide is present, and n measurement values C 1 at that time, C 2 ...... C
From n , the abundances N 1 , N 2 ... N n of the γ-ray emitting nuclides in the wall depth direction are However ε: Detection efficiency of the detector for γ-ray energy of a certain γ-ray emitting nuclide λ: Linear attenuation coefficient of wall for γ-ray energy of the γ-ray emitting nuclide t n : Transmission distance in wall B n : Transmission distance t build-up factor Karadasuru in the wall of the n r n: the γ-ray emitting nuclide existing inside the wall of the concrete or the like and obtaining from the multiple simultaneous linear equations of the distance from the wall to the detector depth To measure the distribution of.
【請求項2】放射線測定器と、放射線測定器を内部にγ
線放出核種が存在する壁体の表面に対して垂直方向に移
動させる測定器駆動装置と、壁体表面との距離がそれぞ
れ異なる測定位置で得られた各測定値が入力される演算
装置とを備え、前記演算装置は、各測定値と壁体深さ方
向に分布するγ線放出核種の存在量との間の多元連立一
次方程式を解くことにより壁体深さ方向に分布するγ線
放出核種の存在量を算出することを特徴とするコンクリ
ート等の壁体内部に存在するγ線放出核種の深さ方向の
分布を測定する装置。
2. A radiation measuring instrument and a radiation measuring instrument inside the gamma
A measuring instrument driving device that moves in the direction perpendicular to the surface of the wall body where the line-emitting nuclide is present, and a computing device that inputs each measurement value obtained at measurement positions where the distance to the wall surface is different. Comprising, the arithmetic unit, the γ-ray emitting nuclides distributed in the wall depth direction by solving a multi-dimensional simultaneous linear equation between each measured value and the abundance of γ-ray emitting nuclides distributed in the wall depth direction. A device for measuring the distribution in the depth direction of γ-ray emitting nuclides existing inside a wall body of concrete or the like, which is characterized by calculating the existing amount of.
【請求項3】前記放射線測定器は、遮蔽体により遮蔽さ
れることを特徴とする特許請求の範囲第2項記載のコン
クリート等の壁体内部に存在するγ線放出核種の深さ方
向の分布を測定する装置。
3. The distribution of γ-ray emitting nuclides existing in the wall of concrete or the like in the depth direction according to claim 2, wherein the radiation measuring device is shielded by a shield. Measuring device.
JP12483986A 1986-05-30 1986-05-30 Method and apparatus for measuring the depthwise distribution of gamma ray emitting nuclides existing inside a wall such as concrete Expired - Fee Related JPH0616102B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP12483986A JPH0616102B2 (en) 1986-05-30 1986-05-30 Method and apparatus for measuring the depthwise distribution of gamma ray emitting nuclides existing inside a wall such as concrete

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP12483986A JPH0616102B2 (en) 1986-05-30 1986-05-30 Method and apparatus for measuring the depthwise distribution of gamma ray emitting nuclides existing inside a wall such as concrete

Publications (2)

Publication Number Publication Date
JPS62282288A JPS62282288A (en) 1987-12-08
JPH0616102B2 true JPH0616102B2 (en) 1994-03-02

Family

ID=14895366

Family Applications (1)

Application Number Title Priority Date Filing Date
JP12483986A Expired - Fee Related JPH0616102B2 (en) 1986-05-30 1986-05-30 Method and apparatus for measuring the depthwise distribution of gamma ray emitting nuclides existing inside a wall such as concrete

Country Status (1)

Country Link
JP (1) JPH0616102B2 (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR20190025393A (en) * 2017-09-01 2019-03-11 한국원자력연구원 System and method for determining radioactive concentration

Families Citing this family (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5412206A (en) * 1994-02-18 1995-05-02 Westinghouse Electric Company Method and apparatus for determining the depth of a gamma emitting element beneath the surface
JP5810066B2 (en) * 2012-11-15 2015-11-11 株式会社神鋼環境ソリューション Method for estimating the amount of radioactive material
JP5955760B2 (en) * 2012-12-20 2016-07-20 日立Geニュークリア・エナジー株式会社 Radiation measurement equipment
JP2014169981A (en) * 2013-03-05 2014-09-18 Hitachi Power Solutions Co Ltd Surface contamination measurement apparatus
JP2018141669A (en) * 2017-02-27 2018-09-13 清水建設株式会社 Method for estimating non-radioactivated portion in concrete
WO2019198260A1 (en) * 2018-04-12 2019-10-17 国立研究開発法人理化学研究所 Nondestructive inspection method and apparatus
JP7489094B2 (en) 2020-05-13 2024-05-23 国立研究開発法人理化学研究所 Concentration detection device and concentration detection method
KR102737203B1 (en) * 2022-11-16 2024-12-03 (주)나일프렌트 Sludge collection device

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR20190025393A (en) * 2017-09-01 2019-03-11 한국원자력연구원 System and method for determining radioactive concentration

Also Published As

Publication number Publication date
JPS62282288A (en) 1987-12-08

Similar Documents

Publication Publication Date Title
Piton et al. Efficiency transfer and coincidence summing corrections for γ-ray spectrometry
JPH0574794B2 (en)
JPH0616102B2 (en) Method and apparatus for measuring the depthwise distribution of gamma ray emitting nuclides existing inside a wall such as concrete
EP1315004B1 (en) Method and apparatus for measuring radioactivity
KR101707957B1 (en) Apparatus and method for determining source depth and radioactivity in medium
US20120245858A1 (en) Apparatuses and methods for analysis of samples through multiple thicknesses
Kull et al. Guidelines for gamma-ray spectroscopy measurements of 235U enrichment
Blaauw Calibration of the well-type germanium gamma-ray detector employing two gamma-ray spectra
JPH0688873A (en) Radiation dose rate distribution evaluation method and device
Peerani et al. Assessment of a Compton-event suppression γ-spectrometer for the detection of fission products at trace levels
JP3009358B2 (en) Measuring method of contamination distribution inside radioactively contaminated piping
JPH1048342A (en) Radioactivity measurement method
JPH09230051A (en) Radioactivity quantity measuring method for radioactive waste solidified body
JPH05333155A (en) Radioactive concentration measuring method for artificial radioactive nuclide in concrete
Prusachenko et al. The measurement of the 6Li (n, t) 4He reaction cross-section in the energy range of 4.25–7.50 MeV
JP2635860B2 (en) Radioactivity evaluation method for solidified radioactive waste
JPH0479597B2 (en)
Kennedy et al. Parameterization of detector efficiency for the standardization of NAA with stable low flux reactors
JPH06288939A (en) Method and apparatus for measuring boron concentration in reactor cooling water
JPS61235783A (en) Liquid scintillation counting device and its usage
Vauramo et al. The design of the detector and collimators for a hybrid scanner
Estep et al. A demonstration of the gross count tomographic Gamma scanner (GC-TGS) method for the nondestructive assay of transuranic waste
Eckhoff et al. Trace element determinations by neutron activation analysis: theory and development
JPH05223938A (en) Measuring method of filling boundary of radioactive-substance filling container
JPH02222855A (en) Pollution depth discriminator

Legal Events

Date Code Title Description
LAPS Cancellation because of no payment of annual fees