JPS5826775B2 - Neutron detector assembly - Google Patents
Neutron detector assemblyInfo
- Publication number
- JPS5826775B2 JPS5826775B2 JP52080181A JP8018177A JPS5826775B2 JP S5826775 B2 JPS5826775 B2 JP S5826775B2 JP 52080181 A JP52080181 A JP 52080181A JP 8018177 A JP8018177 A JP 8018177A JP S5826775 B2 JPS5826775 B2 JP S5826775B2
- Authority
- JP
- Japan
- Prior art keywords
- neutron detector
- neutron
- moderator
- assembly
- sensitivity
- 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
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Measurement Of Radiation (AREA)
Description
【発明の詳細な説明】
本発明は原子炉核計装用中性子検出器アセンブリーに係
り、特に中性子検出器アセンブリーの感度向上に関する
ものである。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a neutron detector assembly for nuclear instrumentation in a nuclear reactor, and more particularly to improving the sensitivity of a neutron detector assembly.
原子炉炉外核計装に用いられる中性子検出器アセンブリ
ーにおいて、線源領域のものと中間領域のものは、中性
子感度を上げるためその周囲をポリエチレン等の減速材
で取囲んだ状態で使用されている。In neutron detector assemblies used for external nuclear instrumentation of nuclear reactors, those in the source area and those in the intermediate area are surrounded by moderators such as polyethylene to increase neutron sensitivity. .
中性子検出器本体の形状は一般に円筒状であり従って減
速材の中心に円筒状の穴を設けそこに中性子検出器本体
を収納する形をとっている。The shape of the neutron detector body is generally cylindrical, and therefore a cylindrical hole is provided in the center of the moderator and the neutron detector body is housed in the hole.
この減速材A/からなるハウジングの中に収納されてい
る。It is housed in a housing made of this moderator A/.
その様子を第1図に示す。上記中性子検出器アセンブリ
ーは第4図に示すよう原子炉に配置される。The situation is shown in Figure 1. The neutron detector assembly described above is placed in a nuclear reactor as shown in FIG.
最近、これらのアセンブリーにおいて、感度向上や長寿
命化の必要性が強い。Recently, there has been a strong need for improved sensitivity and longer life in these assemblies.
まず前者の感度向上を目的とするため、2本以上の中性
子検出器本体を同一アセンブリーに挿入し、それらから
の信号を同時に計装する方法(第2図に示す)や、後者
のアセンブリーの長寿命化を目的として2本以上の中性
子検出器を同一アセンブリーに挿入して、例えば一本づ
つを使用して一本の寿命完了時点において他の中性子検
出器を使用する方法(第3図に示す)等が考えられてい
る。First, to improve the sensitivity of the former, we have developed a method of inserting two or more neutron detector bodies into the same assembly and simultaneously instrumenting the signals from them (as shown in Figure 2), and a method of increasing the length of the latter assembly. For the purpose of life extension, two or more neutron detectors are inserted into the same assembly, for example, one neutron detector is used at a time, and the other neutron detector is used at the end of the life of one (as shown in Figure 3). ) etc. are being considered.
しかしこれらの場合アセンブリー即ち減速材の外形寸法
は同一寸法であるため、中性子検出器1本当りの減速材
が少なくなるため、検出器1本当りに入射する熱中性子
が減少する他に他の中性子検出器による中性子吸収があ
るため、中性子検出器1本を挿入した物に比べ中性子検
出器1本当りの熱中性子の数が減少することになり、中
性子検出器1本当りの計数率は低下する
なお、中性子検出器アセンブリーは第4図に示すように
、炉心容器10の炉心部6から所定距離だけ離れた位置
に配置され、MIケーブル(高圧印加及び信号取出)9
を通して外部検出信号処理回路へ接続されている。However, in these cases, the external dimensions of the assembly, that is, the moderator, are the same, so there is less moderator per neutron detector, which reduces the number of thermal neutrons incident on each detector, as well as the number of other neutrons. Due to the absorption of neutrons by the detector, the number of thermal neutrons per neutron detector will decrease compared to a system with one neutron detector inserted, and the counting rate per neutron detector will decrease. As shown in FIG. 4, the neutron detector assembly is placed at a predetermined distance from the core part 6 of the reactor core vessel 10, and connected to the MI cable (high voltage application and signal extraction) 9.
It is connected to an external detection signal processing circuit through.
本発明はこれらの欠点を解消して、中性子検出器を2本
以上挿入した場合でも中性子検出器1本当りの感度低下
の少ない中性子検出器アセンブリーを提供するものであ
る。The present invention eliminates these drawbacks and provides a neutron detector assembly in which sensitivity decreases less per neutron detector even when two or more neutron detectors are inserted.
又この発明によれば中性子検出器1本を挿入したアセン
ブリーの場合には従来の物に比べて感度の高いものが得
られることができる。Furthermore, according to the present invention, in the case of an assembly in which one neutron detector is inserted, it is possible to obtain a higher sensitivity than the conventional one.
以下第5図に示すこの発明の一実施例について説明する
。An embodiment of the present invention shown in FIG. 5 will be described below.
この実施例では、減速材2の中心7より離れた位置に中
性子検出器挿入孔3の中心8を設は中性子検出器4を設
置する。In this embodiment, the center 8 of the neutron detector insertion hole 3 is located at a position away from the center 7 of the moderator 2, and the neutron detector 4 is installed.
すなわち、減速材2の厚みを中性子の入射側(炉心側)
に比べ反対側)を大きく構成している。In other words, the thickness of the moderator 2 is set to the neutron incident side (core side).
compared to the opposite side).
この場合、当該中性子検出器アセンブリー5を原子炉に
据付ける場合、原子炉中心6、中性子検出器挿入孔の中
心8(即ち中性子検出器4)減速材の中心7の順序で一
直線上に設ける。In this case, when the neutron detector assembly 5 is installed in a nuclear reactor, the reactor center 6, the center 8 of the neutron detector insertion hole (ie, the neutron detector 4), and the center 7 of the moderator are arranged in a straight line in this order.
その時従来の第1図の配置における感度に比べ約1.5
倍の感度が得られる。At that time, the sensitivity was about 1.5 compared to the conventional arrangement shown in Figure 1.
Double the sensitivity.
以下に本発明の作用を従来品と比べ説明する。The effects of the present invention will be explained below in comparison with conventional products.
従来の中性子検出器アセンブリーの配置は第1図の様に
なっており、中性子検出器アセンブリー5の中心軸に対
し直角のいずれの方向から入ってくる中性子ビームに対
しても同じ割合で減速させ熱中性子に変換したものを中
性子検出器4において1°B(nα)’Li核分裂反応
により中性子を計測しようとするものであった。The arrangement of a conventional neutron detector assembly is as shown in Figure 1, where neutron beams entering from any direction perpendicular to the central axis of the neutron detector assembly 5 are decelerated and heated at the same rate. The idea was to measure the neutrons converted into neutrons through a 1°B(nα)'Li nuclear fission reaction in the neutron detector 4.
しかし、原子炉の炉外核計装付近の中性子束は速中性子
と熱中性子が約1=1の割合で入ってくること、又、当
該検出器アセンブリーの据付けられている位置での中性
ビームは平行ビームであり炉心方向から入射して来る割
合が非常に高い。However, the neutron flux near the ex-core nuclear instrumentation of a nuclear reactor is composed of fast neutrons and thermal neutrons at a ratio of approximately 1=1, and the neutral beam at the location where the detector assembly is installed is It is a parallel beam, and a very high percentage of it comes from the direction of the core.
以上の事から本発明の中性子検出器アセンブリーは中性
子検出器を一様な肉厚の減速材で囲むよりも、中性子ビ
ーム入射側の減速材を簿くし、入射して(る熱中性子束
の反射減衰を少なくする一方、ビーム入射後方側の減速
材を厚くすることにより、速中性子束を減速反射させ検
出器に入射する熱中性子を増加させる様にしたものであ
って一実施例では従来のものに比べ1.5倍の感度を得
ることが出来た。Based on the above, the neutron detector assembly of the present invention reduces the moderator on the neutron beam incident side, rather than surrounding the neutron detector with a moderator of uniform thickness, and reduces the reflection of the incident thermal neutron flux. While reducing attenuation, by thickening the moderator on the rear side of the beam incidence, the fast neutron flux is decelerated and reflected, increasing the number of thermal neutrons that enter the detector. We were able to obtain 1.5 times the sensitivity compared to the conventional method.
なお、以上は中性子検出器1本組の場合について説明し
たが、この発明はこれに限らず中性子検出器2本組の場
合でも第6図の様な配置で使用しても良い。Although the above description has been made regarding the case of a set of one neutron detector, the present invention is not limited to this, and may be used in the case of a set of two neutron detectors arranged as shown in FIG. 6.
さらに低感度で使用したい場合は第7図の様な配置に本
発明を応用できる。If it is desired to use the device with even lower sensitivity, the present invention can be applied to an arrangement as shown in FIG.
この場合中性子の入射側で減速材の厚みを大きくして熱
中性子の吸収を促進させることにより感度を低く制御す
ることができる。In this case, the sensitivity can be controlled to be low by increasing the thickness of the moderator on the neutron incident side to promote absorption of thermal neutrons.
以上の様に本発明に係る中性子検出器では減速材内にお
ける中性子検出器の配置を変えることによって、高感度
の中性子検出器が得られることはもちろん、必要に応じ
て低感度の中性子検出器を得ることもできる。As described above, in the neutron detector according to the present invention, by changing the arrangement of the neutron detector in the moderator, it is possible to obtain a high-sensitivity neutron detector, and if necessary, a low-sensitivity neutron detector can be obtained. You can also get it.
第1図は、従来の中性子検出器アセンブリーの断面図、
第2図は従来の中性子検出器として2本以上の中性子検
出器を同一ハウジング内に入れ高感度化をはかったアセ
ンブリーの断面図、第3図は従来の中性子検出器として
2本以上の中性子検出器を同一ハウジング内に入れ長寿
命をはかったアセンブリーの断面図、第4図は原子炉の
炉心付近を示す構成図、第5図は、本発明の一実施例を
示す構成図、第6図、第7図は本発明の他の実施例を示
す構成図である。
図中1はハウジング、2は減速材、3は中性子検出器挿
入孔、4は中性子検出器、5は中性子検出器アセンブリ
ーである。
なお、図中同一符号は同−又は相当部分を示す。FIG. 1 is a cross-sectional view of a conventional neutron detector assembly;
Figure 2 is a cross-sectional view of a conventional neutron detector in which two or more neutron detectors are placed in the same housing to increase sensitivity, and Figure 3 is a conventional neutron detector that detects two or more neutrons. FIG. 4 is a configuration diagram showing the vicinity of the core of a nuclear reactor; FIG. 5 is a configuration diagram showing an embodiment of the present invention; FIG. 6 , FIG. 7 is a block diagram showing another embodiment of the present invention. In the figure, 1 is a housing, 2 is a moderator, 3 is a neutron detector insertion hole, 4 is a neutron detector, and 5 is a neutron detector assembly. Note that the same reference numerals in the figures indicate the same or equivalent parts.
Claims (1)
減速材の厚みを上記中性子の入射側と反射側とで異なら
せて成る中性子検出器アセンブリー1. A neutron detector assembly comprising a neutron detector and a moderator surrounding it, the thickness of the moderator being different between the neutron incident side and the reflection side.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP52080181A JPS5826775B2 (en) | 1977-07-04 | 1977-07-04 | Neutron detector assembly |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP52080181A JPS5826775B2 (en) | 1977-07-04 | 1977-07-04 | Neutron detector assembly |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5414291A JPS5414291A (en) | 1979-02-02 |
| JPS5826775B2 true JPS5826775B2 (en) | 1983-06-04 |
Family
ID=13711180
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP52080181A Expired JPS5826775B2 (en) | 1977-07-04 | 1977-07-04 | Neutron detector assembly |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5826775B2 (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0292868U (en) * | 1988-12-28 | 1990-07-24 | ||
| JPH0883473A (en) * | 1995-10-09 | 1996-03-26 | Hitachi Ltd | Carriage support device for magnetic disk device |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR20220092608A (en) * | 2019-11-08 | 2022-07-01 | 프라마톰 인크. | Self-powered off-furnace detector device for measuring flux in a nuclear reactor core |
-
1977
- 1977-07-04 JP JP52080181A patent/JPS5826775B2/en not_active Expired
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0292868U (en) * | 1988-12-28 | 1990-07-24 | ||
| JPH0883473A (en) * | 1995-10-09 | 1996-03-26 | Hitachi Ltd | Carriage support device for magnetic disk device |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5414291A (en) | 1979-02-02 |
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