JPH06103279B2 - Component analysis method - Google Patents
Component analysis methodInfo
- Publication number
- JPH06103279B2 JPH06103279B2 JP59192564A JP19256484A JPH06103279B2 JP H06103279 B2 JPH06103279 B2 JP H06103279B2 JP 59192564 A JP59192564 A JP 59192564A JP 19256484 A JP19256484 A JP 19256484A JP H06103279 B2 JPH06103279 B2 JP H06103279B2
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- rays
- energy
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- fast
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Classifications
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N23/00—Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00
- G01N23/02—Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00 by transmitting the radiation through the material
- G01N23/06—Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00 by transmitting the radiation through the material and measuring the absorption
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- Physics & Mathematics (AREA)
- Health & Medical Sciences (AREA)
- Life Sciences & Earth Sciences (AREA)
- Chemical & Material Sciences (AREA)
- Analytical Chemistry (AREA)
- Biochemistry (AREA)
- General Health & Medical Sciences (AREA)
- General Physics & Mathematics (AREA)
- Immunology (AREA)
- Pathology (AREA)
- Analysing Materials By The Use Of Radiation (AREA)
Description
【発明の詳細な説明】 〔産業上の利用分野〕 本発明は、放射性同位元素から放出される放射線を利用
して、各種物質の元素又は化合物組成の各成分を定量分
析する方法に関するものである。TECHNICAL FIELD The present invention relates to a method for quantitatively analyzing each component of an element or compound composition of various substances using radiation emitted from a radioisotope. .
石炭や鉱石などの粉状，塊状又はスラリー状物体の流れ
において、試料を採取することなく物質組成を連続的に
オンライン分析する方法としては、非破壊，非接触的な
放射線法以外に適当な方法がなく、放射線の散乱及び２
次的放射線発生等を用いる方法が試みられてきた。その
うち、励起Ｘ線，中性子捕獲γ線などの２次的放射線発
生を利用する方法は、原理的に特定Ｘ線あるいはγ線の
スペクトル解析に基づく元祖組成分析法であり、特定元
素には適しているが、例えば鉱石の成分を鉱物成分，岩
石成分及び水分のように大きく分けて各成分の含有率を
求めるのには適していない。また、元素成分の分析に関
しても、水素，炭素，酸素のような低原子番号元素の組
合せからなる均質の場合には、そのどの方法でも単独で
は不可能であり、中性子捕獲γ線分析と中性子非弾性散
乱γ線分析の方法を組合せるなど、２種以上の方法を併
せ用いなければならない。Non-destructive and non-contact radiation methods are suitable for continuous online analysis of material composition without collecting samples in the flow of powdery, lumpy or slurry-like objects such as coal and ore. Radiation scattering and 2
A method using secondary radiation generation has been tried. Among them, the method of utilizing secondary radiation generation such as excited X-rays and neutron capture γ-rays is an original composition analysis method based on the spectrum analysis of specific X-rays or γ-rays in principle, and is suitable for specific elements. However, it is not suitable for obtaining the content rate of each component by roughly dividing the components of the ore into mineral components, rock components and water. Also, regarding the analysis of elemental components, in the case of homogeneous consisting of a combination of low atomic number elements such as hydrogen, carbon and oxygen, none of these methods can be used alone. Two or more methods must be used in combination, such as a combination of elastic scattering γ-ray analysis methods.
これに対し、放射線の透過，散乱を利用する場合は、各
成分のもつ実効吸収係数又は散乱係数の違いに着目して
いるので、比較的簡単な装置で上記の実用目的を達成し
うる。しかしながら、上記例のように多成分の分析を行
うには、当該成分数と同数だけの種類又はエネルギーの
異なる放射線を用いそれらの放射線計数値から演算によ
り各成分量を求める必要がある。従来このためには、複
数の放射線源と複数の検出器とを使用し、流れている物
体に対して異なる個所をそれぞれ測定して行わざえるを
得なかった。このような従来技術として、具体的に特開
昭49−96791号公報に開示された分析用放射線測定装置
が挙げられる。この装置は、３個の線源と、３個の検出
器を使用するものであり、それぞれの線源から放射され
た放射線を測定対象の同一個所ではなく、別個の個所を
透過させて測定するものであった。On the other hand, in the case of utilizing the transmission and scattering of radiation, since attention is paid to the difference in the effective absorption coefficient or the scattering coefficient of each component, the above practical purpose can be achieved with a relatively simple device. However, in order to perform multi-component analysis as in the above example, it is necessary to use radiations of the same number and different types or different energies as the number of components, and calculate the amount of each component from the radiation count values. For this purpose, it has been unavoidable that a plurality of radiation sources and a plurality of detectors are used to measure different points of a flowing object. An example of such a conventional technique is the analytical radiation measuring apparatus disclosed in Japanese Patent Application Laid-Open No. 49-96791. This device uses three radiation sources and three detectors, and the radiation emitted from each radiation source is measured not by passing through the same location of the measurement target but through different locations. It was a thing.
上記の如く従来技術は、複数の放射線源と複数の検出器
とを使用し、流れている物体に対して異なる個所をそれ
ぞれ測定する方法であるため、流れている測定対象物体
のかさ密度，組成及び流量が充分均一なときには特に問
題ないが、一般的には、粉体，塊状物体等の流れはそれ
程均質でも一定でもないので、異なる個所の測定に基づ
いた演算結果からは充分に良い分析精度を得ることがで
きないという問題があった。As described above, the prior art is a method of using a plurality of radiation sources and a plurality of detectors, and measuring different points of a flowing object. Therefore, the bulk density and composition of the flowing object to be measured are measured. And when the flow rate is sufficiently uniform, there is no particular problem, but in general, the flow of powders, lumps, etc. is not so uniform or constant, so the calculation results based on the measurement at different points show sufficiently good analysis accuracy. There was a problem that I could not get.
本発明の目的は、上記した従来技術の欠点をなくし、測
定対象物体の流れの不均質あるいは時々刻々の変化等に
かかわりなく、流れている物体の主要各成分を精度良く
定量分析する方法を提供するにある。An object of the present invention is to eliminate the above-mentioned drawbacks of the prior art, and to provide a method for accurately quantitatively analyzing each main component of a flowing object regardless of inhomogeneity of the flow of an object to be measured or momentary changes. There is.
物質ごとの質量吸収係数の変り方が大きく異なる多種の
放射線を放出する線源として、広いエネルギー分布を有
する高速中性子と適当なエネルギーのγ線と両方を同時
に放出する線源を用いる。さらにまた、検出器として
は、高速中性子とγ線との両方に感度を有し、両者をそ
れぞれ分離して測定しうるとともに、それぞれのエネル
ギーに応じたパルス信号を出力し、それぞれのエネルギ
ー範囲を選択指定して計数することができる検出器を用
いる。すなわち、これらによって単一線源と単一検出器
とを用い、両者を結ぶ線束幅内の同一個所についての測
定を行いながらエネルギー領域の異なる多種の放射線の
透過による多種成分の分析を可能なるようにしたもので
ある。As a radiation source that emits various types of radiation, the mass absorption coefficient of which varies greatly depending on the substance, a radiation source that simultaneously emits both fast neutrons having a wide energy distribution and γ-rays of appropriate energy is used. Furthermore, as a detector, it has sensitivity to both fast neutrons and γ-rays, and it is possible to separate and measure both, and output a pulse signal according to each energy to determine the energy range of each. A detector that can be selectively designated and counted is used. That is, by using these, a single radiation source and a single detector can be used to analyze various components by transmitting various radiations having different energy regions while measuring at the same position within the flux width connecting them. It was done.
まず本発明にかかわる分析の原理を簡単に説明する。
今、分析対象物が３成分A,B,Cから成るものとし、放射
線束の透過する個所において同線束内の透過方向の各成
分質量厚さ（g/cm2）がmA，mB，mCであるとき、３種類
の放射線の各透過率を測定し次のように３元連立方程式
を解くことによって、mA，mB，mCを求めることができ
る。すなわち、３種類の放射線を表示するため1,2,3の
添字をもってし、各放射線の各成分による実効吸収係数
をμij（ただしｉは1,2,3のいずれか、ｊはA,B,Cのいず
れか）で表わすとき、測定される各放射線の透過率T
i（ｉは1,2,3）は、mj（ｊはA,B,C）と、 （１）式の関係にある。First, the principle of analysis according to the present invention will be briefly described.
Assume that the analyte is composed of three components A, B, C, and the mass thickness (g / cm 2 ) of each component in the transmission direction in the same line flux is m A , m B , When m C , m A , m B , and m C can be obtained by measuring the respective transmittances of three types of radiation and solving the simultaneous three-dimensional equation as follows. That is, in order to display three types of radiation, the subscripts 1, 2, and 3 are used, and the effective absorption coefficient of each component of each radiation is μ ij (where i is 1, 2, or 3, j is A, B). , C), the transmittance T of each measured radiation
i (i is 1,2,3) has a relationship with m j (j is A, B, C) according to the equation (1).
そこで、（１）式を通常の数学的手法で解くことによ
り、以下の通りmA，mB，mCを算出できる。 Therefore, by solving the equation (1) by an ordinary mathematical method, m A , m B , and m C can be calculated as follows.
この方法で各成分の質量厚さを求めるにあたって、その
精度をよくするためには、一般に（２），（３），
（４）式の共通の分母の行列式の値を大きくするように
３種類の放射線を選ぶ必要がある。同行列式の値は、２
つの列の間で成分ごとの比の値が等しいとき、例えばμ
1A／μ2A＝μ1B／μ2B＝μ1C／μ2Cで零となり、その反
対に成分ごとの比の値が大きく異なるほど大となる。同
様にして分析対象物が４成分以上から成るものであると
きは、成分数に等しい種類数の放射線の各透過率を測定
し、多元連立方程式を解くことによって各成分の質量厚
さの値を求めることができる。 In order to improve the accuracy in determining the mass thickness of each component by this method, in general, (2), (3),
It is necessary to select three types of radiation so as to increase the value of the denominator of the common denominator of equation (4). The value of the determinant is 2
When the ratio values for each component are equal between two columns, for example μ
When 1A / μ 2A = μ 1B / μ 2B = μ 1C / μ 2C, it becomes zero, and conversely, the larger the value of the ratio of each component is, the larger it becomes. Similarly, when the analysis target is composed of 4 or more components, the transmittance of radiation of the same number of types as the number of components is measured, and the mass thickness of each component is calculated by solving the multi-dimensional simultaneous equations. You can ask.
なおここで、多種類の放射線としてエネルギーの異なる
電磁放射線のみの組合せを用いるのではなく、電磁放射
線であるγ線とともに高速中性子線を用いる理由の一つ
は、高速中性子の透過率を決める実効質量吸収係数が第
１図に示すごとく、他の元素に比し水素において桁違い
に大きく、このため物質中の水分または水素化合物成分
を測定対象の一つとして分析するとき他法に比較し有利
となることにある。Note that here, instead of using only a combination of electromagnetic radiation with different energies as many types of radiation, one of the reasons for using fast neutron rays with γ rays that are electromagnetic radiation is that the effective mass that determines the transmittance of fast neutrons As shown in Fig. 1, the absorption coefficient in hydrogen is incomparably larger than that of other elements. Therefore, when analyzing water or hydrogen compound components in a substance as one of the measurement targets, it is advantageous compared to other methods. Is to be.
さらに、上記高速中性子を一種類の放射線とせず広範囲
にエネルギー分布するものを用い、同時にエネルギー領
域の異なる２個以上のチャンネルの中性子について測定
を行う理由は、そのような広いエネルギー分布を有する
252Cf中性子源について実測した第１図の例から明らか
なように、高速中性子の物質に対する実効質量吸収係数
がエネルギーにより、かつ物質により大きく変化するこ
とを利用するためである。これは、高速中性子の特異な
原子核反応の結果によるもので電磁放射線の組合せでは
識別不可能なC,N,Oのような原子番号の近接した軽元素
を含む成分の分析にも有効となるものである。Furthermore, the reason why the fast neutrons are used as one type of radiation that has a wide energy distribution without being one type of radiation and at the same time the neutrons of two or more channels with different energy regions are measured has such a wide energy distribution.
This is because the fact that the effective mass absorption coefficient of fast neutrons with respect to a substance largely changes depending on energy and depending on the substance, as is clear from the example of FIG. 1 which was actually measured for the 252 Cf neutron source. This is a result of the unique nuclear reaction of fast neutrons, which is also effective for the analysis of components containing light elements with close atomic numbers such as C, N, and O that cannot be distinguished by the combination of electromagnetic radiation. Is.
他方、高速中性子線と同時にγ線を用いる主な理由は、
100KeV以下の低エネルギー領域を除けばγ線の質量吸収
係数が物質の種類によってほとんど変らず、したがっ
て、対象物の全体としての質量厚さあるいはかさ密度が
その透過率から求まるためである。もちろん厳密にいえ
ば、物質の種類の影響をいくらかうけているので、すで
に述べたとおり、中性子線の透過率とともに複数の式か
らなる連立方程式を解いて求めるものである。On the other hand, the main reason for using gamma rays at the same time as fast neutron rays is
This is because the mass absorption coefficient of γ-rays hardly changes depending on the type of substance, except for the low energy region of 100 KeV or less, and therefore the mass thickness or bulk density of the object as a whole can be obtained from its transmittance. Strictly speaking, of course, it is affected somewhat by the type of substance, so as already mentioned, it is determined by solving a simultaneous equation consisting of multiple equations together with the neutron beam transmittance.
以上は流れている物体に対するオンライン分析への応用
に関して述べたが、採取試料の場合においても、試料物
質の粒度やその他不均一がしばしば問題となり、そのよ
うな場合にも上記の方法が有用となるものである。The above describes the application to online analysis of flowing objects, but even in the case of collected samples, particle size and other non-uniformity of the sample substance often become a problem, and in such cases the above method is also useful. It is a thing.
以下に本発明の実施例について説明する。 Examples of the present invention will be described below.
第２図において、252Cf線源10すなわち１個の放射線源
から放出される放射線すなわち広い連続エネルギー分布
を有し平均約2MeVの高速中性子線と、同じく平均約1MeV
のγ線とは、線源10を取囲む線源格納容器12内の放射線
放射孔14から適当に絞られた線束として放射され、ベル
トコンベア16の上の分析対象物18に投射される。投射さ
れた放射線のうち分析対象物18を透過した高速中性子線
20とγ線22とは、遮蔽をかねたコリメータ24内にある有
機シンチレータ26すなわち１個の検出器により検知され
る。有機シンチレータ26の応答すなわちシンチレーシヨ
ン光の実効的な減衰時間は、高速中性子の場合とγ線の
場合とでかなり異なるので、シンチレータ26に接続した
光電子増倍管28の出力パルスの波形も、高速中性子によ
るパルスとγ線によるパルスとで異なる。そこで、光電
子増倍管28の出力パルスを前置増巾器30を通し増巾した
のち、まず一方をパルス波形弁別器32に導き、高速中性
子信号（論理信号）34又はγ線信号（論理信号）36のい
ずれかを発生させる。他方同時に、前置増巾器30の出力
パルスを線型増巾器38及びタイミング調整のための遅延
増巾器40を通したのち、リニアゲート部42及び44に導
く。リニアゲート部42及び44へは、前記高速中性子識別
信号34及びγ線識別信号36がそれぞれ加えられ、各々の
識別信号により各ゲートが開かれる。すなわち、シンチ
レータ26の検知した放射線が高速中性子であるときは、
ゲート42から同中性子のエネルギーに対応したリニアパ
ルス46が出力し、逆にγ線であるときは、ゲート44から
γ線のエネルギーに対応したリニアパルス48が出力され
る。In Fig. 2, the radiation emitted from a 252 Cf radiation source 10, that is, one radiation source, that is, a fast neutron beam having a wide continuous energy distribution and having an average of about 2 MeV, and also an average of about 1 MeV.
The .gamma.-rays are emitted from the radiation emitting hole 14 in the radiation source storage container 12 that surrounds the radiation source 10 as a suitably narrowed bundle of rays, and are projected onto the analyte 18 on the belt conveyor 16. Fast neutron beam transmitted through the analyte 18 in the projected radiation
20 and gamma rays 22 are detected by an organic scintillator 26, i.e. one detector, in a collimator 24 which also acts as a shield. Since the response of the organic scintillator 26, that is, the effective decay time of the scintillation light, is considerably different between the case of fast neutrons and the case of γ rays, the waveform of the output pulse of the photomultiplier tube 28 connected to the scintillator 26 is also high-speed. Different between neutron pulses and γ-ray pulses. Therefore, the output pulse of the photomultiplier tube 28 is amplified through the preamplifier 30, and then one of them is guided to the pulse waveform discriminator 32, and the fast neutron signal (logical signal) 34 or γ-ray signal (logical signal) ) Generate one of 36. On the other hand, at the same time, the output pulse of the pre-widening device 30 passes through the linear widening device 38 and the delay widening device 40 for timing adjustment, and then is guided to the linear gate sections 42 and 44. The fast neutron identification signal 34 and the γ-ray identification signal 36 are applied to the linear gate sections 42 and 44, respectively, and the respective gates are opened by the respective identification signals. That is, when the radiation detected by the scintillator 26 is fast neutrons,
A linear pulse 46 corresponding to the energy of the same neutron is output from the gate 42. Conversely, when it is a γ ray, a linear pulse 48 corresponding to the energy of the γ ray is output from the gate 44.
このように振り分けられた高速中性子及びγ線のリニア
パルスに対して、次にそれぞれ必要なエネルギー選別計
数を行う。第２図の実施例では、高速中性子パルス46に
対しては、マルチチャンネルパルス波高分析器50を用
い、中性子のエネルギースペクトルに対応したパルス波
高分布を一定時間観測し、そのデータを演算処理装置52
に入れて、着目する複数のエネルギー区間に相応したパ
ルス計数をそれぞれ求める。また他方、γ線パルス48に
対しては、シングルチャンネルパルス波高分析器54によ
り特定のエネルギー範囲に対応する波高のパルスを選択
しスケーラ56により一定時間演算計数し、その数値を演
算処理装置52へ入れる。For the fast neutron and γ-ray linear pulses distributed in this way, next, necessary energy screening and counting are performed. In the embodiment shown in FIG. 2, for the fast neutron pulse 46, a multi-channel pulse height analyzer 50 is used to observe a pulse height distribution corresponding to the energy spectrum of neutrons for a certain period of time, and the data thereof is processed by an arithmetic processing unit 52.
Then, the pulse counts corresponding to the plurality of energy sections of interest are obtained. On the other hand, for the γ-ray pulse 48, a pulse having a pulse height corresponding to a specific energy range is selected by the single-channel pulse height analyzer 54, and the scaler 56 calculates and counts for a certain period of time, and the calculated value is sent to the processing unit 52. Put in.
このようにして演算処理装置52内に得られた複数の異な
る放射線の計数値、例えば中性子計数２種とγ線計数１
種の合計３種の計数値は、それぞれ異なる放射線の物質
の減弱透過率を与えるもので、演算処理装置52により連
立方程式を解くことにより、すでに述べたように３種の
計数値から３成分の各物質量が求まる。分析対象物18が
実効的に３成分からなるものである場合、この３成分量
測定によって流れの断面における全物質量が求まる。す
なわち、物質の放射線透過部の質量厚さが未知であり、
かつ不定であっても上記の測定演算によってすべてがわ
かることを意味する。In this way, a plurality of different radiation count values obtained in the arithmetic processing unit 52, for example, two neutron counts and a γ-ray count 1
The total of the three kinds of count values give the attenuated transmittances of the substances of different radiations. By solving the simultaneous equations by the arithmetic processing unit 52, as described above, the three kinds of count values of the three kinds of species are obtained. The amount of each substance is obtained. When the analyte 18 is effectively composed of three components, the total amount of substance in the cross section of the flow can be obtained by measuring the amount of these three components. That is, the mass thickness of the radiation transmitting part of the substance is unknown,
And even if it is indefinite, it means that everything can be understood by the above measurement calculation.
また、もし流れの断面形状あるいは物質分布が一定であ
るならば、流量も同時に求まることを意味している。Further, if the cross-sectional shape of the flow or the substance distribution is constant, it means that the flow rate can be obtained at the same time.
分析対象物18がさらに１成分多く４成分からなる場合に
は、成分の種類に応じて、高速中性子のエネルギースペ
クトルから３つのエネルギー区間の計数をとるようマル
チチャンネルパルス波高分析器50で得られるスペクトル
データについて演算処理装置52で演算処理を行うか、ま
たはγ線リニアパルス48に対して、エネルギー設定範囲
の異なるさらに１個のシングルチャンネルパルス波高分
析器を設けるようにすることで同様の目的を達成するこ
とができる。なお、第２図の説明においては、高速中性
子リニアパルス46に対するエネルギー選定器としてマル
チチャンネルパルス波高分析器を用いているが、エネル
ギー選定区間の数が決っている場合には、その数だけの
シングルチャンネルパルス波高分析器とスケーラとの組
合せを用いることもできる。When the analyte 18 is made up of one component and four components, the spectrum obtained by the multi-channel pulse height analyzer 50 to count the three energy sections from the energy spectrum of fast neutrons according to the type of component. The same purpose is achieved by performing arithmetic processing on the data with the arithmetic processing unit 52 or providing one more single channel pulse height analyzer with different energy setting range for the γ-ray linear pulse 48. can do. In the description of FIG. 2, a multi-channel pulse height analyzer is used as the energy selector for the fast neutron linear pulse 46, but if the number of energy selection sections is fixed, only that number of singles is selected. A combination of channel pulse height analyzer and scaler can also be used.
すでに述べたように本発明の要点の一つは、単一線源に
対する単一検出器をもってするにあるが、言うまでもな
く、このことは複数の種類の放射線を取扱いながら、被
測定物の同一個所にこれらの放射線を投射し、異なる放
射線の透過減衰率を測定するためである。したがって、
２種以上の線源を複合合体して１個の線源として用いる
こと、また複数のシンチレータを線束軸の方向に重ね合
せ１本の光電子増倍管に接合して１個の検出器として用
いても同様の効果が得られる。As already mentioned, one of the main points of the present invention is to have a single detector for a single radiation source. Needless to say, this means that while handling a plurality of types of radiation, it can be applied to the same location of the object to be measured. This is because these radiations are projected and the transmission attenuation rates of different radiations are measured. Therefore,
Use two or more kinds of radiation sources as a single radiation source by combining them together. Also, stack a plurality of scintillators in the direction of the flux axis and bond them to one photomultiplier tube to use as one detector. However, the same effect can be obtained.
次に、上記実施例における具体的な分析実験結果の例を
説明する。すなわち、約15mCiの252Cf線源とそれから60
cmの距離においた127mm直径×127mm高さの体積をもつ有
機シンチレータとの間に、石炭模擬試料として、グラフ
ァイト板、ガラス板及びアルミセルに入れた水の３種類
の試料を種々組合わせて挿入した。各試料の質量厚さは
第１表の通りで、それぞれ独立に３段階に変え、合計27
組の測定試料を用いた。Next, an example of a concrete analysis experiment result in the above embodiment will be described. That is, about 15 mCi of 252 Cf source and 60
Between the organic scintillator having a volume of 127 mm diameter × 127 mm height and placed at a distance of cm, three kinds of samples of graphite plate, glass plate, and water in aluminum cell were inserted in various combinations as coal simulated samples. . The mass thickness of each sample is as shown in Table 1.
A set of measurement samples was used.
同試料を炭素，水素，酸素、及び灰分金属元素（ケイ素
で代表させる）の４元素系としてみると、各元素成分の
質量厚さは、第２表のようになる。 Considering the sample as a four-element system of carbon, hydrogen, oxygen, and an ash metal element (represented by silicon), the mass thickness of each element component is as shown in Table 2.
この27組の試料について、各300秒間γ線及び高速中性
子両者の同時透過測定を行い、次のような各エネルギー
範囲における計数積算及び透過率計算を行った。それぞ
れのエネルギー範囲での各元素に対する実効質量吸収係
数の値は、別の実験データから第３表のように定められ
た。 Simultaneous transmission measurements of both γ-rays and fast neutrons were carried out for each of these 27 sets of samples for 300 seconds, and counting integration and transmittance calculation were performed in the following energy ranges. The value of the effective mass absorption coefficient for each element in each energy range was determined from another experimental data as shown in Table 3.
各チャンネルの透過率値及び各元素実効質量吸収係数値
を、すでに述べた連立方程式（この場合は、４成分、４
チャンネルであるから４元一次連立方程式）に入れて演
算することにより、試料ごとに各成分質量厚さを求め、
それと第２表に記した調合値との差を算出して、その標
準偏差を求めた結果、第４表のようになった。 The transmittance value of each channel and the effective mass absorption coefficient value of each element are calculated by the simultaneous equations (in this case, 4 components, 4
Since it is a channel, it is calculated by putting it in a four-dimensional linear simultaneous equation) and calculating each component mass thickness for each sample.
The difference between it and the blended value shown in Table 2 was calculated, and the standard deviation was calculated. The result is shown in Table 4.
この結果は、誤差絶対値においても、また相対値におい
ても良い結果であり、本方式の優れた性能を示すもので
ある。 This result is a good result both in the absolute value of the error and in the relative value, and shows the excellent performance of this system.
上記分析例と全く同じ実験においてγ線を用いることな
く、中性子のエネルギー範囲を0.84〜1.25,1.67〜2.51,
2.61〜3.66、及び4.18以上と４チャンネル設定して同様
のことを行った結果は第５表の通りとなった。水素とケ
イ素の２成分に関し第４表より若干誤差が大きくなった
が、炭素と酸素の２成分に関しては第４表とほとんど同
じ良い値が得られた。Without using γ rays in the same experiment as the above analysis example, the energy range of neutrons is 0.84 to 1.25, 1.67 to 2.51,
Table 5 shows the results of doing the same with 4 channels set to 2.61 to 3.66 and 4.18 or higher. The error for the two components of hydrogen and silicon was slightly larger than that in Table 4, but the same good values as in Table 4 were obtained for the two components of carbon and oxygen.
すなわち、一般に全質量厚さあるいは密度の測定に適す
るγ線を利用する方が、全体的に良い結果を生むと云え
るが、目的と場合によっては、γ線を用いずに中性子の
みの複数チャンネルでも、充分良い結果が得られること
を示すものである。ただし、その場合でも例えば第２図
の実施例で云えば、リニアゲート18、シングルチャンネ
ル波高分析器23及びスケーラ24の３部分が不要となるほ
かは、実際上、線源から検出器を経て演算処理装置に至
るまで、全く同等のもので構成されることになる。 That is, in general, it can be said that using γ-rays suitable for measurement of total mass thickness or density produces better results overall, but depending on the purpose and case, multiple channels of neutrons only without using γ-rays However, it shows that sufficiently good results are obtained. However, even in that case, for example, in the embodiment of FIG. 2, the linear gate 18, the single-channel wave height analyzer 23, and the scaler 24 are not necessary in addition to the three parts, and in reality, calculation is performed from the source through the detector. From the processing equipment to the processing equipment, it will consist of exactly the same.
以上述べた如く、本発明ではエネルギー分布を有する高
速中性子とγ線との両方を放出する１個の線源と、高速
中性子とγ線との両方に感度を有し、かつパルス波形弁
別の手段で両者を分離しうるとともにそれぞれの検出放
射線エネルギーをパルス波高分析の手段で判別しうる１
個のシンチレーション検出器とを使用して、物体の同一
個所につき高速中性子とγ線両者の透過測定を行い、各
放射線の検出パルスに対して、それぞれ異なるエネルギ
ー範囲の係数チャンネル設定により分析成分数に等しい
数の係数値を得、それらの演算によって各成分量を求め
る。このため、測定対象物の厚さ、かさ密度、粒度その
他の不均質等に関係なく、測定個所におけるい正しい成
分量が得られるとともに、測定対象物が連続的に流れて
いるものである場合には、時々刻々の変化と同時に任意
時間内の各成分平均分析値をも得ることができるもので
ある。As described above, in the present invention, a single radiation source that emits both fast neutrons and γ-rays having an energy distribution and a means for discriminating pulse waveforms that is sensitive to both fast neutrons and γ-rays. And the detected radiation energy can be discriminated by means of pulse height analysis 1
Using both scintillation detectors, transmission measurements of both fast neutrons and γ-rays are performed at the same location on the object, and the number of analytical components is determined for each detection pulse of each radiation by setting coefficient channels in different energy ranges. An equal number of coefficient values are obtained, and the amount of each component is calculated by these calculations. Therefore, regardless of the thickness, bulk density, particle size and other inhomogeneities of the object to be measured, it is possible to obtain the correct amount of components at the measurement point and when the object to be measured is continuously flowing. Can obtain the average analysis value of each component within an arbitrary time at the same time as the momentary change.
第１図は252Cf中性子の４元素に対する実効質量吸収係
数をエネルギーの関数として示す図、第２図は本発明に
係る成分分析計の基本構成を含む一実施例を示す図であ
る。 10…線源、18…分析対象物、20…高速中性子線、22…γ
線、24…コリメータ、34…高速中性子論理信号、36…γ
線論理信号、46…高速中性子リニアパルス、48…γ線リ
ニアパルス、50…マルチチャンネル波高分析器、52…演
算処理装置、54…シングルチャンネルパルス波高分析
器。FIG. 1 is a diagram showing the effective mass absorption coefficient of 252 Cf neutrons for four elements as a function of energy, and FIG. 2 is a diagram showing an embodiment including the basic configuration of a component analyzer according to the present invention. 10 ... Source, 18 ... Analyte object, 20 ... Fast neutron beam, 22 ... γ
Line, 24 ... Collimator, 34 ... Fast neutron logic signal, 36 ... γ
Line logic signal, 46 ... Fast neutron linear pulse, 48 ... γ-ray linear pulse, 50 ... Multi-channel pulse height analyzer, 52 ... Arithmetic processing unit, 54 ... Single channel pulse height analyzer.
───────────────────────────────────────────────────── フロントページの続き (72)発明者 立川 登 茨城県東茨城郡大洗町大貫1044番地 (72)発明者 堀内 昭一 茨城県勝田市市毛882番地 株式会社日立 製作所那珂工場内 (72)発明者 佐瀬 義広 茨城県勝田市市毛882番地 株式会社日立 製作所那珂工場内 (56)参考文献 特開 昭59−77346（ＪＰ，Ａ) 特開 昭49−96791（ＪＰ，Ａ) ─────────────────────────────────────────────────── --- Continuation of the front page (72) Inventor Noboru Tachikawa 1044, Onuki, Oarai-cho, Higashi-Ibaraki-gun, Ibaraki Prefecture (72) Inventor Shoichi Horiuchi, 882, Igemo, Katsuta-shi, Ibaraki Hitachi Ltd. (72) Invention Yoshihiro Sase 882, Mao, Katsuta City, Ibaraki Prefecture, Hitachi, Ltd. Naka Factory (56) References JP 59-77346 (JP, A) JP 49-96791 (JP, A)
Claims (1)
有する高速中性子と所定のエネルギーのγ線の両方を発
し、被測定物の同一個所を透過した高速中性子とγ線の
両方を１個の検出器で検出し、前記検出器によって検出
された信号を演算処理手段にて受けて、前記信号から少
なくとも高速中性子の透過率を求めると共に該高速中性
子透過率は分析対象成分数に応じた数の異なるエネルギ
ー領域毎に選別して求め、更にこれら複数の放射線の透
過率に基づいて前記被測定物中の成分を求めるようにし
たことを特徴とする成分分析方法。1. A single radiation source emits both fast neutrons having a wide energy distribution and γ-rays of a predetermined energy, and both fast neutrons and γ-rays transmitted through the same point of the object to be measured are collected. Detected by the detector, receiving the signal detected by the detector by the arithmetic processing means, and at least the fast neutron transmittance from the signal is obtained and the fast neutron transmittance of the number according to the number of components to be analyzed. A component analysis method, characterized in that it is selected for each different energy region, and further, the components in the object to be measured are obtained based on the transmittances of these plural radiations.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59192564A JPH06103279B2 (en) | 1984-09-17 | 1984-09-17 | Component analysis method |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59192564A JPH06103279B2 (en) | 1984-09-17 | 1984-09-17 | Component analysis method |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS6171341A JPS6171341A (en) | 1986-04-12 |
| JPH06103279B2 true JPH06103279B2 (en) | 1994-12-14 |
Family
ID=16293378
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP59192564A Expired - Fee Related JPH06103279B2 (en) | 1984-09-17 | 1984-09-17 | Component analysis method |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH06103279B2 (en) |
Families Citing this family (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2821708B2 (en) * | 1990-06-13 | 1998-11-05 | アースニクス株式会社 | Density / moisture measurement device |
| NZ237767A (en) * | 1992-04-09 | 1994-09-27 | Inst Geolog Nuclear Sciences | Luggage scanning by fast neutrons and gamma radiation |
| US5513428A (en) * | 1992-12-04 | 1996-05-07 | Toyota Jidosha Kabushiki Kaisha | Automatic assembling apparatus |
| KR100716047B1 (en) | 2004-12-23 | 2007-05-09 | 한국원자력연구소 | Organic scintillator-impregnated membranes and its preparation method |
| US7693261B2 (en) * | 2007-05-17 | 2010-04-06 | Durham Scientific Crystals Limited | Method and apparatus for inspection of materials |
| GB2484315B (en) * | 2010-10-06 | 2016-07-13 | Univ Of Lancaster | Improvements in and relating to gamma ray and neutron detection |
Family Cites Families (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS571781B2 (en) * | 1973-01-18 | 1982-01-12 | ||
| JPS5977346A (en) * | 1982-10-25 | 1984-05-02 | Japan Atom Energy Res Inst | Analyzing apparatus for element composition of substance |
-
1984
- 1984-09-17 JP JP59192564A patent/JPH06103279B2/en not_active Expired - Fee Related
Also Published As
| Publication number | Publication date |
|---|---|
| JPS6171341A (en) | 1986-04-12 |
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