JPH0478153B2 - - Google Patents
Info
- Publication number
- JPH0478153B2 JPH0478153B2 JP10924185A JP10924185A JPH0478153B2 JP H0478153 B2 JPH0478153 B2 JP H0478153B2 JP 10924185 A JP10924185 A JP 10924185A JP 10924185 A JP10924185 A JP 10924185A JP H0478153 B2 JPH0478153 B2 JP H0478153B2
- Authority
- JP
- Japan
- Prior art keywords
- neutron
- neutrons
- counting
- moderator
- counting section
- 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
Links
- 238000001514 detection method Methods 0.000 claims description 11
- 238000005259 measurement Methods 0.000 claims description 11
- 238000010183 spectrum analysis Methods 0.000 claims description 4
- 230000004907 flux Effects 0.000 description 8
- 239000007789 gas Substances 0.000 description 4
- 239000003638 chemical reducing agent Substances 0.000 description 3
- 238000010586 diagram Methods 0.000 description 3
- 238000001228 spectrum Methods 0.000 description 3
- 231100000987 absorbed dose Toxicity 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 description 1
- 239000004698 Polyethylene Substances 0.000 description 1
- 230000004913 activation Effects 0.000 description 1
- 230000005250 beta ray Effects 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 230000005251 gamma ray Effects 0.000 description 1
- 239000001257 hydrogen Substances 0.000 description 1
- 229910052739 hydrogen Inorganic materials 0.000 description 1
- 239000011810 insulating material Substances 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 239000002245 particle Substances 0.000 description 1
- 230000000149 penetrating effect Effects 0.000 description 1
- 229920003023 plastic Polymers 0.000 description 1
- 239000004033 plastic Substances 0.000 description 1
- -1 polyethylene Polymers 0.000 description 1
- 229920000573 polyethylene Polymers 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
Landscapes
- Measurement Of Radiation (AREA)
Description
【発明の詳細な説明】
［産業上の利用分野］
本発明は中性子測定器、特に減速材を用いて中
性子エネルギを低減させて中性子の測定を行う中
性子測定器に関する。DETAILED DESCRIPTION OF THE INVENTION [Field of Industrial Application] The present invention relates to a neutron measuring instrument, and particularly to a neutron measuring instrument that measures neutrons by reducing neutron energy using a moderator.
［従来の技術］
中性子の検出・測定はγ線の検出・測定等とは
異なり、極めて特殊な性質を有することから、一
般的な放射線検出とは相違する取扱いがなされて
いる。[Prior Art] The detection and measurement of neutrons is different from the detection and measurement of gamma rays, and has very special properties, so it is treated differently from general radiation detection.
すなわち、中性子はそれ自体電荷を有していな
いことから軌道電子や原子核のクーロン場には何
らの影響も与えず、単にγ線・β線用の検出器内
に入射させるだけでは電離電荷を発生させること
ができない。従つて、中性子検出は、中性子に発
熱的な核反応を引き起こさせその電離生成物、例
えばα粒子・陽子・γ線等を検出することによ
り、あるいは中性子の照射による放射化を利用す
ることにより行われる。 In other words, since neutrons themselves do not have an electric charge, they do not have any effect on the orbital electrons or the Coulomb field of the atomic nucleus, and simply letting them enter a gamma-ray/beta-ray detector will generate an ionizing charge. I can't do it. Therefore, neutron detection can be performed by causing exothermic nuclear reactions with neutrons and detecting their ionized products, such as alpha particles, protons, gamma rays, etc., or by using activation caused by neutron irradiation. be exposed.
また、中性子はその透過力が極めて強いことか
ら、中性子が検出器内にとどまらず、完全に通過
してしまいエネルギの高くかつ速い中性子を効率
良く検出することができない。従つて、高速ある
いは熱外中性子はポリエチレン等の含有水素物か
ら成る減速材を用いて測定可能なエネルギまで減
速させ、その中性子線量（線量当量・吸収線量な
ど）あるいは中性子束の測定を行う。 Furthermore, since neutrons have extremely strong penetrating power, the neutrons do not stay within the detector but completely pass through the detector, making it impossible to efficiently detect high-energy and fast neutrons. Therefore, high-speed or epithermal neutrons are slowed down to measurable energy using a moderator made of a hydrogen-containing substance such as polyethylene, and the neutron dose (dose equivalent, absorbed dose, etc.) or neutron flux is measured.
従来の中性子測定器は、例えば円筒状あるいは
球殻状の減速容器の中に中性子計数部、例えば
BF3、3He等のガスを用いた中性子用比例計数管
が収納された構成となつている。そして、この減
速容器にて中性子を所定のエネルギまで減速させ
て中性子の測定を行つており、中性子束あるいは
その中性子のエネルギスペクトル等の詳細な測定
を行う場合には、減速容器の厚さを異ならせた複
数個の中性子測定器を用いることにより行われ、
これら複数個の測定器から得られた計数値に基づ
いて中性子線量の正確な値が得られ、更には中性
子束あるいは中性子エネルギスペクトル等の測定
を行うことができる。 Conventional neutron measuring instruments include a neutron counting section, for example, in a cylindrical or spherical shell-shaped moderation vessel.
The structure houses a proportional counter for neutrons using gases such as BF 3 and 3 He. Neutrons are measured by decelerating neutrons to a predetermined energy in this moderation vessel, and when performing detailed measurements such as neutron flux or the energy spectrum of the neutrons, the thickness of the moderation vessel is different. This is done by using multiple neutron measuring instruments,
Accurate values of neutron dose can be obtained based on the counts obtained from these plurality of measuring instruments, and furthermore, neutron flux, neutron energy spectrum, etc. can be measured.
［発明が解決しようとする問題点］
従来技術の問題点
しかしながら、従来装置では、複数個の中性子
測定器を用いることからその取扱いが煩雑であ
り、中性子が飛来する方向に複数個の中性子測定
器を同一の条件で配置することが困難であるとい
う問題があつた。[Problems to be Solved by the Invention] Problems of the Prior Art However, the conventional device uses a plurality of neutron measuring devices, making its handling complicated. There was a problem that it was difficult to arrange the two under the same conditions.
また、中性子同時測定をする場合に一方向の中
性子束に対して複数個の中性子測定器を同一位置
に設定することができないため、測定誤差を生じ
させ易いという問題があつた。 Furthermore, when performing simultaneous neutron measurements, it is not possible to set a plurality of neutron measuring instruments at the same position for neutron flux in one direction, which causes a problem in that measurement errors are likely to occur.
発明の目的
本発明は前記従来の問題点解決のためになされ
たものであり、その目的は、取扱いが容易でかつ
中性子を検出するだけでなく中性子線量・中性子
束等の精密な測定を正確に行うことのできる中性
子測定器を提供することにある。Purpose of the Invention The present invention was made in order to solve the above-mentioned conventional problems, and its purpose is to not only detect neutrons but also to accurately measure neutron dose, neutron flux, etc. with ease of handling. The objective is to provide a neutron measuring instrument that can perform
［問題点を解決するための手段及び作用］
前記目的を達成するために、本発明は、中性子
検出のために正負電極間にガス体が充填された計
数部と中性子を減速するための所定厚さの減速体
とを交互に複数個重ねて積層し、前記減速体によ
り異なるエネルギレベルとされた中性子を各計数
部でそれぞれ別個に検出することを特徴とする。[Means and operations for solving the problems] In order to achieve the above object, the present invention provides a counting section filled with a gas between positive and negative electrodes for neutron detection, and a predetermined thickness for decelerating neutrons. The present invention is characterized in that a plurality of decelerating bodies are alternately stacked one on top of the other, and neutrons having different energy levels caused by the moderating bodies are individually detected in each counting section.
以上のような構成によれば、測定対象である中
性子は減速体により順に減速されて各計数部に入
射することとなり、この各計数部ではエネルギレ
ベルの異なる中性子が同時に検出・計数され、中
性子束等の測定が迅速かつ正確に行われる。 According to the above configuration, the neutrons to be measured are sequentially decelerated by the moderator and enter each counter, and each counter simultaneously detects and counts neutrons with different energy levels, and the neutron flux etc. can be measured quickly and accurately.
［実施例］
以下、図面に基づいて本発明の好適な実施例を
説明する。[Embodiments] Hereinafter, preferred embodiments of the present invention will be described based on the drawings.
第１図には、球殻状の中性子測定器（計数処理
部は省略）が示され、これは３個の減速体と４個
の計数部から構成されている。すなわち、第１減
速体１０、第２減速体１２、第３減速体１４と第
１計数部１６、第２計数部１８、第３計数部２０
及び第４計数部２２とが球殻状に形成され、順に
重ねられている。そして、各計数部には正負電極
が配置されており、第１計数部１６には陽極とし
ての中心電極２４と第１減速体１０の内側に貼着
された陰極２６、第２計数部１８には第１減速体
１０の外側に貼着された陽極２８と第２減速体１
２の内側に貼着された陰極３０、第３計数部２０
には第２減速体１２の外側に貼着された陽極３２
と第３減速体１４の内側に貼着された陰極３４、
第４計数部２２には第３減速体１４の外側に貼着
された陽極３６と外枠体４０の内側に貼着された
陰極３８が配置されている。これら各電極は保持
体を兼ねた同軸電極部４２に接続されており、陽
極２４（中心電極）、２８，３２，３６と陰極２
６，３０，３４，３８とは絶縁材４４にて電気的
に分離されている。 FIG. 1 shows a spherical shell-shaped neutron measuring instrument (counting processing section is omitted), which is composed of three moderators and four counting sections. That is, the first deceleration body 10, the second deceleration body 12, the third deceleration body 14, the first counting section 16, the second counting section 18, and the third counting section 20.
and the fourth counting section 22 are formed in a spherical shell shape and are stacked one on top of the other. Positive and negative electrodes are arranged in each counting section, and the first counting section 16 has a center electrode 24 as an anode, the cathode 26 attached to the inside of the first moderator 10, and the second counting section 18 has a center electrode 24 as an anode and a cathode 26 attached to the inside of the first moderator 10. The anode 28 attached to the outside of the first moderator 10 and the second moderator 1
Cathode 30 affixed to the inside of 2, third counting section 20
has an anode 32 attached to the outside of the second moderator 12.
and a cathode 34 affixed to the inside of the third moderator 14,
An anode 36 attached to the outside of the third speed reducer 14 and a cathode 38 attached to the inside of the outer frame 40 are arranged in the fourth counting section 22 . Each of these electrodes is connected to a coaxial electrode section 42 which also serves as a holder, and includes an anode 24 (center electrode), 28, 32, 36 and a cathode 2.
6, 30, 34, and 38 are electrically separated by an insulating material 44.
そして、各計数部１６，１８，２０，２２には
BF3、3Heなどのガスが封入され、いわゆる比例
計数管とされている。なお、比例計数管とせずパ
ルス型電離箱あるいはプラスチツクシンチレータ
などにて各計数部を構成することもできる。 And each counting section 16, 18, 20, 22 has
It is filled with gases such as BF 3 and 3 He and is called a proportional counter tube. It should be noted that each counting section may be constructed of a pulse type ionization chamber, a plastic scintillator, or the like instead of a proportional counter.
本発明は、前述したように減速体と計数部を交
互に複数個重ねて積層したことを特徴としてお
り、第１図のように、全球殻とせず半球殻として
もよく、第２図に示されるように、平板状の減速
体１０′，１２′，１４′と平板状の計数部１６′，
１８′，２０′，２２′とを重ねて形成することも
できる。 As mentioned above, the present invention is characterized in that a plurality of deceleration bodies and counting parts are stacked alternately, and instead of being a whole spherical shell as shown in Fig. 1, it may be a hemispherical shell, and as shown in Fig. 2. In order to
18', 20', and 22' can also be formed by overlapping each other.
本発明は以上のような構成から成り、以下にそ
の作用を説明する。第１図において、測定器に入
射する中性子はまず減速されない状態で第４計数
部２２にて中性子が検出され、この第４計数部２
２で検出されなかつた中性子は第３減速体１４を
通過することとなるが、この時に所定エネルギだ
け減速され第３計数部２０に到達することとな
る。そして、第３計数部２０では同じように中性
子検出が行われ、ここで検出されなかつた中性子
は更に第２減速体１２を通過することとなる。こ
のようにして測定される中性子は、第１計数部１
６に到達するまでにエネルギの小さい中性子が順
に消滅することとなり、結果的に第１計数部１６
に到達する中性子は極めてエネルギの高い中性子
である。 The present invention has the above configuration, and its operation will be explained below. In FIG. 1, the neutrons incident on the measuring instrument are first detected in the fourth counting section 22 without being decelerated;
The neutrons that were not detected in step 2 pass through the third moderator 14, but at this time they are decelerated by a predetermined amount of energy and reach the third counting section 20. Then, neutron detection is performed in the same manner in the third counting section 20, and neutrons that are not detected here further pass through the second moderator 12. The neutrons measured in this way are
6, neutrons with lower energy will be annihilated in order, and as a result, the first counting section 16
The neutrons that reach the neutrons are extremely energetic neutrons.
従つて、各計数部１６，１８，２０，２２にて
エネルギレベルの異なる中性子が検出されること
となり、計数部内のガス体を通過する際に生ずる
電離電荷は、陽極２４，２８，３２，３６にて集
電され同軸電極部４２を介して計数処理回路に供
給され、中性子の計数が行われる。 Therefore, neutrons with different energy levels are detected in each counting section 16, 18, 20, 22, and the ionized charges generated when passing through the gas in the counting section are transferred to the anodes 24, 28, 32, 36. The current is collected and supplied to a counting processing circuit via the coaxial electrode section 42, where neutrons are counted.
本発明装置は、エネルギレベルの異なる中性子
を同時に検出できることから、中性子線量の正確
な測定、中性子束の測定あるいは中性子エネルギ
の測定等を行うことができ、これらの測定は、第
３図に示されるような回路にて行われる。すなわ
ち、第１計数部１６で検出される検出信号は計数
回路４６−１に供給され中性子計数が行われた後
に掛算器４８−１に供給される。同様にして第
２、第３、第４計数部１８，２０，２２で検出さ
れる検出信号はそれぞれ計数回路４６−２，４６
−３，４６−４に供給され中性子計数が行われた
後に掛算器４８−２，４８−３，４８−４に供給
される。 Since the device of the present invention can simultaneously detect neutrons with different energy levels, it can accurately measure neutron dose, neutron flux, or neutron energy, and these measurements are shown in Figure 3. This is done using a circuit like this. That is, the detection signal detected by the first counting section 16 is supplied to a counting circuit 46-1, where neutrons are counted, and then supplied to a multiplier 48-1. Similarly, the detection signals detected by the second, third, and fourth counting sections 18, 20, and 22 are respectively detected by the counting circuits 46-2 and 46-2.
-3, 46-4, and after neutron counting is performed, it is supplied to multipliers 48-2, 48-3, 48-4.
そして、この掛算器４８には各計数部に中性子
が到達するまでに通過する減速体の厚さに対応し
た重み付けが与えられ、各掛算器４８の出力は加
算部５０に供給され加算される。この加算部５０
では中性子束、総量当量あるいは吸収線量等を演
算して表示部５２に表示する。一方、計数回路４
６の出力はスペクトル分析回路５４に供給され、
中性子エネルギスペクトル分析が行われスペクト
ル表示部５６に表示される。 This multiplier 48 is given a weight corresponding to the thickness of the moderator that the neutrons pass through before reaching each counting section, and the output of each multiplier 48 is supplied to an adding section 50 and added. This addition section 50
Then, the neutron flux, total amount equivalent, absorbed dose, etc. are calculated and displayed on the display section 52. On the other hand, counting circuit 4
The output of 6 is supplied to a spectrum analysis circuit 54,
Neutron energy spectrum analysis is performed and displayed on the spectrum display section 56.
［発明の効果］
以上説明したように、本発明によれば、計数部
と減速体とを交互に複数個重ねて積層としたの
で、エネルギレベルの異なる中性子を同時に測定
することが可能となり、中性子の正確な測定を行
うことができる。この結果、中性子測定を行う際
の繁雑な手順をなくすことができ、容易かつ迅速
な測定を行うことが可能となる。[Effects of the Invention] As explained above, according to the present invention, since a plurality of counting units and moderators are laminated alternately, it is possible to simultaneously measure neutrons with different energy levels, and the neutron Accurate measurements can be taken. As a result, it is possible to eliminate complicated procedures when performing neutron measurements, and it becomes possible to perform measurements easily and quickly.
第１図は本発明に係る中性子測定器の好適な実
施例を示す説明図、第２図は本発明の他の実施例
を示す説明図、第３図は中性子測定器の測定処理
回路を示すブロツク図である。
１０……第１減速体、１２……第２減速体、１
４……第３減速体、１６……第１計数部、１８…
…第２計数部、２０……第３計数部、２２……第
４計数部、２４……中心電極（陽極）、２８，３
２，３６……陽極、２６，３０，３４，３８……
陰極、４６……計数回路、４８……掛算器、５４
……スペクトル分析回路。
Fig. 1 is an explanatory diagram showing a preferred embodiment of a neutron measuring instrument according to the present invention, Fig. 2 is an explanatory diagram showing another embodiment of the present invention, and Fig. 3 is a measurement processing circuit of the neutron measuring instrument. It is a block diagram. 10...First speed reducer, 12...Second speed reducer, 1
4... Third deceleration body, 16... First counting section, 18...
...Second counting section, 20...Third counting section, 22...Fourth counting section, 24...Center electrode (anode), 28,3
2, 36... Anode, 26, 30, 34, 38...
Cathode, 46... Counting circuit, 48... Multiplier, 54
...Spectrum analysis circuit.
Claims (1)
填された計数部と中性子を減速するための所定厚
さの減速体とを交互に複数個重ねて積層し、前記
減速体により異なるエネルギレベルとされた中性
子を各計数部でそれぞれ別個に検出することを特
徴とする中性子測定器。 ２ 特許請求の範囲１記載の装置において、前記
計数部及び減速体は球殻状に重ねられたことを特
徴とする中性子測定器。 ３ 特許請求の範囲１記載の装置において、前記
各計数部で得られた複数の中性子検出信号に対し
て通過する減速体の厚さに対応した重み付けを与
えて中性子測定を行うことを特徴とする中性子測
定器。 ４ 特許請求の範囲１記載の装置において、前記
各計数部で得られた複数の中性子検出信号をエネ
ルギスペクトル分析回路に供給し中性子スペクト
ロメータとして用いることを特徴とする中性子測
定器。[Scope of Claims] 1. A counting unit filled with a gas between positive and negative electrodes for neutron detection and a plurality of moderators having a predetermined thickness for moderating neutrons are alternately stacked and stacked, A neutron measuring instrument characterized in that each counter separately detects neutrons with different energy levels depending on the body. 2. The neutron measuring device according to claim 1, wherein the counting section and the moderator are stacked in a spherical shell shape. 3. The apparatus according to claim 1, characterized in that neutron measurement is performed by weighting the plurality of neutron detection signals obtained by each of the counting sections in accordance with the thickness of the moderator passing through. Neutron measuring instrument. 4. A neutron measuring device according to claim 1, wherein a plurality of neutron detection signals obtained by each of the counting sections are supplied to an energy spectrum analysis circuit to be used as a neutron spectrometer.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP10924185A JPS61269089A (en) | 1985-05-23 | 1985-05-23 | Neutron measuring instrument |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP10924185A JPS61269089A (en) | 1985-05-23 | 1985-05-23 | Neutron measuring instrument |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS61269089A JPS61269089A (en) | 1986-11-28 |
| JPH0478153B2 true JPH0478153B2 (en) | 1992-12-10 |
Family
ID=14505187
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP10924185A Granted JPS61269089A (en) | 1985-05-23 | 1985-05-23 | Neutron measuring instrument |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS61269089A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102866416A (en) * | 2012-09-10 | 2013-01-09 | 中国科学院合肥物质科学研究院 | Continuous neutron spectrum real-time detection system |
Families Citing this family (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2552414B2 (en) * | 1992-03-16 | 1996-11-13 | アロカ株式会社 | Neutron measuring device |
| JP4670068B2 (en) * | 2001-08-24 | 2011-04-13 | 独立行政法人 日本原子力研究開発機構 | Moderator structure of moderator neutron spectrometer |
| JP2007071602A (en) * | 2005-09-05 | 2007-03-22 | Kyoto Univ | Radiation detector |
| EP2293114B1 (en) * | 2009-09-02 | 2017-09-06 | 3833364 Canada Inc. (operating as DETEC) | Neutron energy spectrometer |
| JP6004662B2 (en) * | 2012-02-03 | 2016-10-12 | 三菱重工業株式会社 | Neutron measuring device |
| EP2708918A1 (en) | 2012-09-12 | 2014-03-19 | Paul Scherrer Institut | Energy-sensitive fast neutron imaging detector and method for energy-sensitive fast neutron detection |
| JP6143162B2 (en) * | 2013-03-06 | 2017-06-07 | 三菱重工業株式会社 | Neutron measuring device |
-
1985
- 1985-05-23 JP JP10924185A patent/JPS61269089A/en active Granted
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102866416A (en) * | 2012-09-10 | 2013-01-09 | 中国科学院合肥物质科学研究院 | Continuous neutron spectrum real-time detection system |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS61269089A (en) | 1986-11-28 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN103698801B (en) | The multilayer scintillation detector of high energy proton and neutron spectrum measurement and measuring method | |
| JP3908788B2 (en) | Object detection device using single energy neutrons | |
| CN109799527A (en) | A kind of neutron spectrum measurement device and bonner sphere spectrometer system | |
| CN114740521A (en) | Detection system and method based on beta-gamma coincidence | |
| JPH0478153B2 (en) | ||
| JPH0434829A (en) | Detector for neutron in wide energy range | |
| JP2552414B2 (en) | Neutron measuring device | |
| RU2102775C1 (en) | Neutron flux recorder | |
| JPH0282188A (en) | Neutron detector for fast neutron | |
| RU2222818C1 (en) | Aid for neutron detection and spectrometry | |
| JPH0434828A (en) | Gamma-ray compensated neutron detector | |
| JPH06258449A (en) | Neutron measuring equipment | |
| RU2658097C1 (en) | High-intensity pulsed neutron radiation spectrometer | |
| JPH01100493A (en) | Nuclear fission type neutron detector | |
| JPH0247581A (en) | Neutron detector | |
| JPH052113B2 (en) | ||
| RU2819778C1 (en) | Spectrometer of high-intensity pulsed neutron radiation, not sensitive to accompanying gamma radiation | |
| Buchtela | Gas ionization detectors | |
| Belz et al. | A compact beam stop for a rare kaon decay experiment | |
| JPH09318760A (en) | Neutron detector and its using method | |
| US5164149A (en) | Nuclide separation type of precipitator system | |
| KR20250080428A (en) | Bonner sphere device for measuring energy spectrum of neutron | |
| JPH07153418A (en) | Ventilated ion chamber | |
| JPH09318759A (en) | Apparatus for measuring neutron | |
| Kumpiranon et al. | The current status of the Gas Electron Multiplier (GEM) research at Kasetsart University, Thailand |