JPH0574029B2 - - Google Patents
Info
- Publication number
- JPH0574029B2 JPH0574029B2 JP63053520A JP5352088A JPH0574029B2 JP H0574029 B2 JPH0574029 B2 JP H0574029B2 JP 63053520 A JP63053520 A JP 63053520A JP 5352088 A JP5352088 A JP 5352088A JP H0574029 B2 JPH0574029 B2 JP H0574029B2
- Authority
- JP
- Japan
- Prior art keywords
- energy
- radiation
- detection element
- semiconductor
- characteristic
- 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
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Classifications
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
- G01T1/02—Dosimeters
- G01T1/026—Semiconductor dose-rate meters
Landscapes
- Measurement Of Radiation (AREA)
- Light Receiving Elements (AREA)
Description
【発明の詳細な説明】
〔産業上の利用分野〕
本発明は、半導体放射線検出素子を用いた放射
線線量測定器に係り、特に、検出素子に入射する
光子エネルギーに対応する照射線量感度や吸収線
量感度の特性を高精度に補償するのに好適な検出
器構造に関する。[Detailed Description of the Invention] [Industrial Application Field] The present invention relates to a radiation dosimeter using a semiconductor radiation detection element, and particularly relates to radiation dose sensitivity and absorption dose corresponding to photon energy incident on the detection element. The present invention relates to a detector structure suitable for highly accurate compensation of sensitivity characteristics.
従来の半導体放射線検出素子の入射光子エネル
ギーに対応する照射線量感度特性(以下エネルギ
ー特性という)は、特開昭59−214787号公報記載
のように、半導体検出素子の周囲を鉛もしくは鉛
を主成分とする金属シールド材で包囲し、かつ、
その金属シールド材に所定開口率の開口を設ける
構造で補償している。
The irradiation dose sensitivity characteristics (hereinafter referred to as energy characteristics) corresponding to the incident photon energy of conventional semiconductor radiation detection elements are as described in Japanese Patent Application Laid-Open No. 59-214787. surrounded by metal shielding material, and
This is compensated by a structure in which openings with a predetermined aperture ratio are provided in the metal shield material.
このエネルギー特性の補償とは、照射線量計の
場合、入射光子エネルギーに対応する感度が一定
になる様にする処置をいう。また、特開昭60−
42672号公報のように、半導体放射線検出器の出
力波形(パルス幅や波高値)をデイスクリミネー
タ等の外部回路で弁別し、各エネルギー特性に対
応した補正係数を付与する手段を設けて、その特
性を補償するものもある。この補正係数付与手段
には、各パルス毎、所定の基準発振信号と論理を
取る方法、マイクロコンピユータで計算処理を行
なう方法が取られている。 In the case of an irradiation dosimeter, compensation of this energy characteristic refers to a procedure for making the sensitivity corresponding to incident photon energy constant. Also, JP-A-60-
As in Publication No. 42672, a means is provided to discriminate the output waveform (pulse width and peak value) of a semiconductor radiation detector using an external circuit such as a discriminator, and provide a correction coefficient corresponding to each energy characteristic. Some compensate properties. This correction coefficient applying means includes a method of calculating logic with a predetermined reference oscillation signal for each pulse, and a method of performing calculation processing with a microcomputer.
上記従来技術で、鉛シールド材を用いて、その
一部に開口部を設けるエネルギー補償法は、シー
ルド材そのものが、入射する放射線との相互作用
で特性X線を放出することの配慮がなされておら
ず、各種のエネルギー特性の異なる半導体検出素
子を任意の特性に補償することが難しい。すなわ
ち、鉛シールド材のしやへい効果と開口率から設
計計算されるエネルギー特性と実測される特性を
一致させる事が難しいと云うことである。さらに
シールド材の鉛は、しやへい効果のパラメータと
なる吸収係数が90KeVのエネルギー範囲で不連
続に変化し、エネルギー補償の設計計算をきわめ
て難しいものとしている。上記、エネルギー補償
法は古くからとられているGM係数管のエネルギ
ー補償法と同一であり、実測値に基づいて開口率
やしやへい材厚を試行選択しなければならない問
題が生じる。
In the above-mentioned conventional technology, the energy compensation method using a lead shield material and providing an opening in a part takes into account the fact that the shield material itself emits characteristic X-rays when it interacts with incident radiation. Therefore, it is difficult to compensate various semiconductor detection elements having different energy characteristics to an arbitrary characteristic. In other words, it is difficult to match the energy characteristics designed and calculated from the lead shielding material's shearing effect and aperture ratio with the actually measured characteristics. Furthermore, the absorption coefficient of the lead shielding material, which is a parameter for the shielding effect, changes discontinuously in the energy range of 90 KeV, making design calculations for energy compensation extremely difficult. The energy compensation method described above is the same as the energy compensation method for GM coefficient pipes that has been used for a long time, and the problem arises that the aperture ratio and the material thickness must be selected on a trial basis based on actual measured values.
また、放射線検出信号の波形弁別手段を論じる
方法は、検出器外部にマイクロコンピユータ等の
補正係数付与手段が必要となり、ハード、ソフト
ウエアを設けなければならない問題が生じる。 Furthermore, the method of discussing the waveform discrimination means of the radiation detection signal requires correction coefficient applying means such as a microcomputer outside the detector, resulting in the problem that hardware and software must be provided.
本発明の目的は、半導体検出素子に対し、もつ
とも単純な原理で、かつ、高精度にエネルギー特
性を補償し、検出器の製作調整コストを大巾に低
減することである。 An object of the present invention is to compensate the energy characteristics of a semiconductor detection element with a very simple principle and with high precision, and to significantly reduce the manufacturing and adjustment cost of the detector.
上記目的は、半導体検出素子に隣接して設ける
エネルギー補償用のシールド材に、原子番号44以
下の材料を用いることにより、一挙に達成され
る。
The above objects can be achieved all at once by using a material with an atomic number of 44 or less for the energy compensation shield material provided adjacent to the semiconductor detection element.
半導体放射線検出素子の動作原理は放射線が半
導体材料に入射して光電効果やコンプトン散乱等
の相互作用を起こし、2次電子を生成する。この
2次電子が検出素子内の空乏層で電子−正孔対の
電荷を作り、放射線の検出信号となる。半導体検
出素子の空乏層厚は100〜200μm程度であり、入
射する放射線のエネルギーによつて光電効果やコ
ンプトン散乱による放射線の吸収量が大きく異な
る。低エネルギー(200KeV以下)では光電効果
を起こす割合が多く、高感度となる。高エネルギ
ーでは光電効果を起こす割合がきわめて小さく低
感度となる。また、極低エネルギー(20KeV以
下)では、検出素子P・n接合の電極(n+層、
オームコンタクトのAl電極)に吸収された不感
となる。これらの現象に基づいて、各種半導体検
出素子のエネルギー特性が決まる。一般に
20KeV以下では不感となり、50〜60KeVで感度
がもつと高くなる。これ以上のエネルギーでは
徐々に感度が低下し、1MeV以上ではコンプトン
散乱が主体でほぼ一定の感度となる。このような
エネルギー特性を持つ半導体放射線検出素子を照
射線量計に用いるためには、入射する放射線のエ
ネルギーに対応する検出感度を一定にしなければ
ならない。照射線量計のエリアモニタのJIS規格
仕様では80KeV〜3MeVの範囲で、その感度差が
±25%以下でなければならない。この特性を半導
体検出素子に設定するためには検出素子の前面に
しやへい体を設け、50〜60KeV近傍の高感度領
域の感度を低下させることによつて、エネルギー
に依存しない特性を得ることができる。
The operating principle of a semiconductor radiation detection element is that radiation enters a semiconductor material and causes interactions such as the photoelectric effect and Compton scattering to generate secondary electrons. These secondary electrons create charges of electron-hole pairs in a depletion layer within the detection element, which becomes a radiation detection signal. The depletion layer thickness of a semiconductor detection element is approximately 100 to 200 μm, and the amount of radiation absorbed by the photoelectric effect and Compton scattering varies greatly depending on the energy of the incident radiation. At low energies (below 200 KeV), a high proportion of photoelectric effects occur, resulting in high sensitivity. At high energies, the proportion of photoelectric effects occurring is extremely small, resulting in low sensitivity. In addition, at extremely low energy (20 KeV or less), the electrode of the detection element P/n junction (n + layer,
It becomes insensitive because it is absorbed by the Al electrode of the ohmic contact. Based on these phenomena, the energy characteristics of various semiconductor detection elements are determined. in general
It becomes insensitive below 20 KeV, and increases when it becomes sensitive at 50 to 60 KeV. At energies above this, the sensitivity gradually decreases, and above 1 MeV, Compton scattering is the main component and the sensitivity remains almost constant. In order to use a semiconductor radiation detection element having such energy characteristics in an irradiation dosimeter, detection sensitivity corresponding to the energy of incident radiation must be made constant. According to the JIS standard specifications for area monitors of irradiation dosimeters, the sensitivity difference must be within ±25% within the range of 80KeV to 3MeV. In order to set this characteristic to a semiconductor detection element, it is possible to obtain energy-independent characteristics by providing a shield in front of the detection element and reducing the sensitivity in the high sensitivity region around 50 to 60 KeV. can.
本発明の検出器構造は、検出素子に隣接して、
原子番号が44以下の元素を主成分とする材料を所
定厚設ける。従来の検出器では、加工性が良いと
云う理由から、鉛(原子番号82)を主体とする材
料で、このエネルギー補償を図つているのが実状
である。この従来のエネルギー補償法では、半導
体検出素子が有感となるエネルギー領域に、補償
材そのものから放出する特性X線が大きく影響す
る。 The detector structure of the present invention includes, adjacent to the detection element,
A material whose main component is an element with an atomic number of 44 or less is provided to a predetermined thickness. In conventional detectors, this energy compensation is actually achieved using a material mainly composed of lead (atomic number 82) because it is easy to process. In this conventional energy compensation method, the characteristic X-rays emitted from the compensation material itself have a large influence on the energy range in which the semiconductor detection element is sensitive.
本発明で用いる原子番号44以下の材料から放出
される特性X線は20KeV以下であり、半導体検
出素子への影響を皆無にできる。また、この低原
子番号の材料の吸収係数は入射する放射線のエネ
ルギーに対し不連続がなく、照射線量計のエネル
ギー特性仕様範囲である80KeV〜3KeVのエネル
ギー補償設計(しやへい効果の計算)を精密に実
行できる。 The characteristic X-ray emitted from the material with an atomic number of 44 or less used in the present invention is 20 KeV or less, and can have no effect on the semiconductor detection element. In addition, the absorption coefficient of this low atomic number material has no discontinuity with respect to the energy of incident radiation, making it possible to design energy compensation (calculation of the Shiyahei effect) for the energy characteristic specification range of 80 KeV to 3 KeV of the irradiation dosimeter. Can be executed with precision.
以上のように、本発明を用いることによつて、
照射線量計や吸収線量計に不可欠なエネルギー特
性を任意に設計実現することができる。 As described above, by using the present invention,
Energy characteristics essential to irradiation dosimeters and absorption dosimeters can be designed and realized as desired.
以下、本発明の一実施例を第1図により説明す
る。半導体検出素子1をフラツドベース基材(導
電体)2に装着し、逆バイアスの印加電極をボン
デイングワイヤ3、ハーメツクシール4を介して
外部に引き出す。検出素子1の外側に原子番号44
以下のしやへい材料5たとえばアルミナ(Al2
O3)やアルミニウム(Al)を設け、全体を鉄
(Fe)やステンレス(SUS)のプローブケース6
に収納して検出部を構成する。第2図に、その立
体図を示す。検出素子1としやへい材のアルミナ
5を支持ポール7で支持し、プローブケース6の
外部に放射線検出信号を取り出す信号線8を引き
出す。第3図には半導体検出素子1の断面図を示
す。この半導体検出素子はp型シリコンを用いた
素子構造である。陽電極(アルミニウム)10に
逆バイアスを印加するとn+層11の下部に、放
射線有感部となる空乏層12が広がる。陽電極ア
ルミニウム10とn+層11および素子の表面保
護膜(SiO2等)は放射線の不感層となる。これ
らの不感領域によつて検出素子の放射線感度は
20KeV以下で急激に感度が劣化する。エネルギ
ー補償を図るしやへい材から放出する特性X線の
エネルギーが20KeV以下であれば、その影響は
全く無視できることになる。
An embodiment of the present invention will be described below with reference to FIG. A semiconductor detection element 1 is mounted on a flat base substrate (conductor) 2, and a reverse bias application electrode is led out via a bonding wire 3 and a hermetic seal 4. Atomic number 44 on the outside of detection element 1
The following hard materials 5 For example, alumina (Al 2
O 3 ) and aluminum (Al), and the entire probe case 6 is made of iron (Fe) or stainless steel (SUS).
The detector is configured by storing the detector in the detector. Fig. 2 shows its three-dimensional view. A detecting element 1 and alumina 5 made of a ceramic material are supported by a support pole 7, and a signal line 8 for extracting a radiation detection signal is drawn out of the probe case 6. FIG. 3 shows a sectional view of the semiconductor detection element 1. This semiconductor detection element has an element structure using p-type silicon. When a reverse bias is applied to the positive electrode (aluminum) 10, a depletion layer 12, which becomes a radiation-sensitive portion, expands below the n + layer 11. The positive electrode aluminum 10, the n + layer 11, and the surface protective film (SiO 2 etc.) of the element serve as radiation insensitive layers. These dead areas reduce the radiation sensitivity of the detection element.
Sensitivity deteriorates rapidly below 20KeV. If the energy of the characteristic X-rays emitted from the shielding material used for energy compensation is less than 20 KeV, its influence can be completely ignored.
次に特性X線の発生機構について述べる。入射
する放射線と相互作用によつて原子の軌道電子が
正規の位置から外された場合、原子は励起状態と
なる。その後、単時間(nsecかそれ以下の時間)
で軌道電子の空孔をその外側の軌道電子や自由電
子が埋めて、原子が基底状態に戻る。このとき特
性X線を放出する。このエネルギーはK殻の軌道
から放出するものが最大である。このエネルギー
は元素の原子番号に依存し、規則的に増大する。
第4図にK殻の特性X線エネルギーと原子番号の
関係を示す。この関係から、明らかなように特性
X線のエネルギーが20KeV以下となる原子番号
は44と云うことになる。 Next, the generation mechanism of characteristic X-rays will be described. When an atom's orbital electrons are displaced from their normal positions by interaction with incident radiation, the atom becomes excited. Then a single time (nsec or less time)
The vacancies of the orbital electrons are filled by the outer orbital electrons and free electrons, and the atom returns to the ground state. At this time, characteristic X-rays are emitted. The maximum amount of this energy is released from the orbit of the K shell. This energy depends on the atomic number of the element and increases regularly.
Figure 4 shows the relationship between the characteristic X-ray energy and atomic number of the K shell. From this relationship, it is clear that the atomic number at which the characteristic X-ray energy is 20 KeV or less is 44.
第5図には、シリコン検出器に、本発明を用い
た照射線量計のエネルギー特性を示す。この図中
Aで示した実線が第1図のしやへい材(アルミ
ナ)5とプローブケース6がない場合のエネルギ
ー補償前データである。同図にBで示した実験点
が、プローブケース6の厚さが1.5mm、しやへい
材アルミナ5の厚さを12mmにしたときのエネルギ
ー特性である。この特性のエネルギー補償性能は
±15%であり、照射線量計のJIS規格を十分満足
するものである。このエネルギー補償法は検出器
を機械的な衝撃から保護する目的のプローブケー
ス6の厚さや、検出素子そのものの特性に合わせ
て、任意に設計できる。プローブケース6の厚さ
が1.5mmより薄くなる場合は、その吸収層の減少
割合と同一分だけ、アルミナ材の厚さを厚くする
ことで同じ特性が得られる。このときに設計基準
は放射線のエネルギー(E)=80KeVの線吸収係
数μ(E)を用いたしやへい計算が良く一致する。
すなわち、プローブケース6の材料を鉄(Fe)
とし、その薄くした厚さをt(Fe)とすると、放
射線吸収の減
少割合はe-〓(Fe FIG. 5 shows the energy characteristics of an irradiation dosimeter using the present invention in a silicon detector. The solid line indicated by A in this figure is the data before energy compensation in the case where the stiffening material (alumina) 5 and the probe case 6 shown in FIG. 1 are not present. The experimental point indicated by B in the figure is the energy characteristic when the thickness of the probe case 6 is 1.5 mm and the thickness of the alumina material 5 is 12 mm. The energy compensation performance of this characteristic is ±15%, which fully satisfies the JIS standard for irradiation dosimeters. This energy compensation method can be arbitrarily designed according to the thickness of the probe case 6 intended to protect the detector from mechanical impact and the characteristics of the detection element itself. When the thickness of the probe case 6 becomes thinner than 1.5 mm, the same characteristics can be obtained by increasing the thickness of the alumina material by the same amount as the reduction rate of the absorption layer. At this time, the design standard is based on the linear absorption coefficient μ(E) of radiation energy (E) = 80 KeV, and the calculation results in good agreement.
In other words, the material of the probe case 6 is iron (Fe).
If the reduced thickness is t(Fe), the rate of decrease in radiation absorption is e - 〓 (Fe
Claims (1)
定器において、検出素子にもつとも近い位置に、
原子番号44以下の元素を主成分とする材料を配置
した放射線線量測定器。 2 請求項1記載の線量測定器において、入射す
る光子エネルギーに依存する線量検出感度が、生
体の吸収線量等量のエネルギー依存性に、相対的
に一致する放射線線量測定器。 3 半導体放射線検出素子を用いる放射線線量測
定器において、エネルギ補償用のシールド材とし
て原子番号44以下の元素を主成分とする材料を用
た放射線線量測定器。[Claims] 1. In a radiation dosimeter using a semiconductor radiation detection element, at a position closest to the detection element,
A radiation dosimeter equipped with a material whose main component is an element with an atomic number of 44 or less. 2. The radiation dosimeter according to claim 1, wherein the dose detection sensitivity depending on incident photon energy is relatively equal to the energy dependence of absorbed dose equivalent in a living body. 3. A radiation dosimeter that uses a semiconductor radiation detection element and uses a material whose main component is an element with an atomic number of 44 or less as a shielding material for energy compensation.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63053520A JPH01227983A (en) | 1988-03-09 | 1988-03-09 | Radiation dose measuring instrument |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63053520A JPH01227983A (en) | 1988-03-09 | 1988-03-09 | Radiation dose measuring instrument |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH01227983A JPH01227983A (en) | 1989-09-12 |
| JPH0574029B2 true JPH0574029B2 (en) | 1993-10-15 |
Family
ID=12945097
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP63053520A Granted JPH01227983A (en) | 1988-03-09 | 1988-03-09 | Radiation dose measuring instrument |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH01227983A (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2873270B2 (en) * | 1994-05-17 | 1999-03-24 | アロカ株式会社 | Radiation detector |
| US6013916A (en) * | 1997-07-23 | 2000-01-11 | The Regents Of The University Of Michigan | Flat panel dosimeter |
-
1988
- 1988-03-09 JP JP63053520A patent/JPH01227983A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPH01227983A (en) | 1989-09-12 |
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