JPH0477874B2 - - Google Patents

Info

Publication number
JPH0477874B2
JPH0477874B2 JP59072191A JP7219184A JPH0477874B2 JP H0477874 B2 JPH0477874 B2 JP H0477874B2 JP 59072191 A JP59072191 A JP 59072191A JP 7219184 A JP7219184 A JP 7219184A JP H0477874 B2 JPH0477874 B2 JP H0477874B2
Authority
JP
Japan
Prior art keywords
nuclear reactor
measuring device
ionization chamber
signal cable
chamber case
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
Application number
JP59072191A
Other languages
Japanese (ja)
Other versions
JPS60214295A (en
Inventor
Ichiro Tai
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.)
Toshiba Corp
Original Assignee
Tokyo Shibaura Electric 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 Tokyo Shibaura Electric Co Ltd filed Critical Tokyo Shibaura Electric Co Ltd
Priority to JP59072191A priority Critical patent/JPS60214295A/en
Publication of JPS60214295A publication Critical patent/JPS60214295A/en
Publication of JPH0477874B2 publication Critical patent/JPH0477874B2/ja
Granted legal-status Critical Current

Links

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Measurement Of Radiation (AREA)
  • Inorganic Insulating Materials (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

【発明の詳細な説明】[Detailed description of the invention]

〔発明の技術分野〕 本発明は電気的絶縁をなす電気絶縁用絶縁体に
改良を施した原子炉用計測装置に関する。 [発明の技術的背景] 例えば原子力発電所、再処理施設あるいは放射
線照射施設等の放射線利用施設において直接放射
線レベル等を計測する中性子検出器、γ線検出器
およびこれらの検出器からの検出信号を伝送する
信号ケーブルには耐放射線特性が要求されてい
る。上記各検出器の内特に炉内中性子検出器ある
いは熱電対等は最も苛酷な使用条件下におかれ、
その為これらの検出器には耐放射線性能をもたせ
るための種類の対策が施されており、炉内で長期
間安定した動作をなし得るように構成されてい
る。 以下第1図を参照して炉内中性子検出器を例に
とつて説明する。第1図は炉内中性子検出器の一
部を示す縦断面図であり、図中符号は電離箱部
を示し、また符号は信号ケーブル部を示す。上
記電離箱部は、電離箱ケース3と、この電離箱
ケース3内に間隔を有して配置された陽極4と、
上記電離箱ケース3の内周面に取り付けられた陰
極5とから構成されている。上記電離箱ケース3
は耐熱性、耐触性および耐放射性を備えた金属例
えばオーステナイト系ステンレス鋼より構成され
ている。上記陽極4はその両端を陽極支持部材7
Aおよび7Bを介して上記電離箱ケース3に支持
されている。この陽極支持部材7Aおよび7Bは
セラミツクスにより構成されており上記陽極4を
支持しているのみならず電気的絶縁をもなしてい
る。また上記セラミツクスとしては例えばアルミ
ナ(Al2O3)、マグネシア(MgO)、シリカ
(SiO2)等である。また上記電離箱ケース3内に
は不活性ガスが充填されており、絶縁シール11
Aによつてシールされている。この絶縁シール1
1Aも前記支持部材7Aおよび7B同様セラミツ
クスより構成されている。一方前記信号ケーブル
部2は上記電離箱ケース3に接続された信号ケー
ブル被覆8とこの信号ケーブル被覆8内に収容さ
れ上記陽極4に接続された信号ケーブル芯線9と
から構成されており、この信号ケーブル芯線9と
信号ケーブル被覆8との間には絶縁体10が充填
されているとともにこの絶縁体10と前記電離箱
部1側との間には絶縁シール11Bが取り付けら
れている。この絶縁シール11Bにより絶縁体1
0内への湿気の流入を防止する構成である。これ
ら絶縁体10および絶縁シール11Bも前記陽極
支持部材7Aおよび7Bと同様セラミツクスより
構成されている。上記セラミツクスは原子炉内に
おける長期間の使用に対しても十分その性能を保
持することが可能であり、よつて炉内中性子検出
器は原子炉内において長期間信頼性の高い検出を
行なうことができる。 [背景技術の問題点] 上記構成において一般に炉内では中性子照射に
よる体積膨張現象があり、上述したセラミツクス
はこの点で問題があり、よつてセラミツクスより
構成された陽極支持部材7Aおよび7B、絶縁体
10および絶縁シール11A,11Bは、永年使
用により体積が膨張してその性能を喪失する恐れ
があり特に絶縁シール11Aおよび11Bが膨張
すると亀裂が発生し、その結果充填されている不
活性ガスが流出したりあるいは絶縁体10内に湿
気が流入して検出が不能となつてしまうという不
具合があつた。 〔発明の目的〕 本発明は以上の点に基づいてなされたものでそ
の目的とするところは、長期間にわたる中性子照
射に対してもその健全性を維持することができる
電気絶縁用絶縁体を備えた原子炉用計測装置を提
供することにある。 〔発明の概要〕 すなわち本発明による原子炉用計測装置は、原
子炉において各種計測を行なう原子炉用計測装置
において、電気的絶縁をなす電気絶縁用絶縁体を
スピネル型セラミツクスにより構成したことを特
徴とするものである。 〔発明の実施例〕 以下第2図および第3図を参照して本発明の一
実施例を説明する。なお従来と同一部分には同一
符号を付して示し、その説明は省略した。本実施
例による陽極支持部材107Aおよび107B、
絶縁体110および絶縁シール111A,111
Bは、スピネル型セラミツクス例えばMgAl2O4
により構成されている。このMgAl2O4の特性を
従来のアルミナおよびマグネシアとの比較で次の
表1に示す。
[Technical Field of the Invention] The present invention relates to a nuclear reactor measuring device in which an electrically insulating insulator for electrical insulation is improved. [Technical Background of the Invention] For example, neutron detectors, gamma ray detectors, and detection signals from these detectors that directly measure radiation levels, etc. in radiation utilization facilities such as nuclear power plants, reprocessing facilities, or radiation irradiation facilities are used. Transmission signal cables are required to have radiation resistance characteristics. Of the above-mentioned detectors, in-core neutron detectors and thermocouples are used under the most severe conditions.
For this reason, these detectors are equipped with various measures to make them radiation-resistant, and are constructed so that they can operate stably for long periods of time in the reactor. Hereinafter, referring to FIG. 1, an in-core neutron detector will be explained as an example. FIG. 1 is a longitudinal sectional view showing a part of the in-core neutron detector, in which reference numeral 1 indicates an ionization chamber section, and reference numeral 2 indicates a signal cable section. The ionization chamber section 1 includes an ionization chamber case 3, an anode 4 arranged at a distance within the ionization chamber case 3,
A cathode 5 is attached to the inner peripheral surface of the ionization chamber case 3. Ionization chamber case 3 above
is made of a metal having heat resistance, corrosion resistance, and radiation resistance, such as austenitic stainless steel. The anode 4 has both ends connected to an anode support member 7.
It is supported by the ionization chamber case 3 via A and 7B. The anode support members 7A and 7B are made of ceramics, and not only support the anode 4 but also provide electrical insulation. Examples of the ceramics include alumina (Al 2 O 3 ), magnesia (MgO), and silica (SiO 2 ). In addition, the ionization chamber case 3 is filled with inert gas, and an insulating seal 11 is filled.
It is sealed by A. This insulation seal 1
Like the support members 7A and 7B, support member 1A is also made of ceramics. On the other hand, the signal cable section 2 is composed of a signal cable sheath 8 connected to the ion chamber case 3 and a signal cable core wire 9 housed within the signal cable sheath 8 and connected to the anode 4. An insulator 10 is filled between the cable core wire 9 and the signal cable sheath 8, and an insulating seal 11B is attached between the insulator 10 and the ionization chamber 1 side. This insulating seal 11B allows the insulator 1
This is a structure that prevents moisture from flowing into the interior. These insulators 10 and insulating seals 11B are also made of ceramics, like the anode support members 7A and 7B. The above-mentioned ceramics can maintain their performance sufficiently even when used in a nuclear reactor for a long period of time, so the in-reactor neutron detector can perform highly reliable detection for a long period of time in a nuclear reactor. can. [Problems in the Background Art] In the above configuration, there is generally a volumetric expansion phenomenon due to neutron irradiation in the reactor, and the above-mentioned ceramics have a problem in this respect. 10 and the insulating seals 11A and 11B may expand in volume and lose their performance after long-term use. In particular, when the insulating seals 11A and 11B expand, cracks may occur, resulting in the inert gas filled in them leaking out. Otherwise, moisture may flow into the insulator 10, making detection impossible. [Object of the Invention] The present invention has been made based on the above points, and its object is to provide an electrically insulating insulator that can maintain its integrity even under long-term neutron irradiation. The object of the present invention is to provide a nuclear reactor measurement device that has improved performance. [Summary of the Invention] That is, the nuclear reactor measuring device according to the present invention is characterized in that, in the nuclear reactor measuring device that performs various measurements in a nuclear reactor, an electrically insulating insulator for electrical insulation is made of spinel type ceramics. That is. [Embodiment of the Invention] An embodiment of the present invention will be described below with reference to FIGS. 2 and 3. Note that parts that are the same as those in the prior art are denoted by the same reference numerals, and their explanations are omitted. Anode support members 107A and 107B according to this embodiment,
Insulator 110 and insulation seals 111A, 111
B is spinel type ceramics such as MgAl 2 O 4
It is made up of. The properties of this MgAl 2 O 4 are shown in Table 1 below in comparison with conventional alumina and magnesia.

【表】【table】

〔発明の効果〕〔Effect of the invention〕

以上詳述したように本発明による原子炉用計測
装置は、原子炉において各種計測を行なう原子炉
用計測装置において、電気的絶縁をなす電気絶縁
用絶縁体をスピネル型セラミツクスにより構成し
たとを特徴するものである。 したがつて長期間にわたる中性子照射に対しも
その性能を確実に維持することができ、信頼性の
高い原子炉用計測装置を提供することが可能とな
る。
As detailed above, the nuclear reactor measuring device according to the present invention is characterized in that the electrically insulating insulator for electrically insulating the nuclear reactor measuring device that performs various measurements in a nuclear reactor is made of spinel type ceramics. It is something to do. Therefore, it is possible to reliably maintain its performance even during long-term neutron irradiation, making it possible to provide a highly reliable nuclear reactor measurement device.

【図面の簡単な説明】[Brief explanation of the drawing]

第1図は従来例を示す炉内中性子検出器の一部
縦断面図、第2図および第3図は本発明の一実施
例を示す図で、第2図は炉内中性子検出器の一部
縦断面図、第3図はアルミナとMgAl2O4との体
積膨張率を比較して示す線図である。 …電離箱部、…信号ケーブル部、3…電離
箱ケース、4…陽極、5…陰極、107A,10
7B…陽極支持部材、8…信号ケーブル被覆、9
…信号ケーブル芯線、110…絶縁体、111
A,111B…絶縁シール。
FIG. 1 is a partial longitudinal sectional view of an in-core neutron detector showing a conventional example, FIGS. 2 and 3 are views showing an embodiment of the present invention, and FIG. FIG. 3 is a diagram showing a comparison of the volumetric expansion coefficients of alumina and MgAl 2 O 4 . 1 ...Ionization chamber part, 2 ...Signal cable part, 3...Ionization chamber case, 4...Anode, 5...Cathode, 107A, 10
7B...Anode support member, 8...Signal cable covering, 9
...Signal cable core wire, 110...Insulator, 111
A, 111B...Insulating seal.

Claims (1)

【特許請求の範囲】 1 原子炉において各種計測を行なう原子炉用計
測装置において、電気的絶縁をなす電気絶縁用絶
縁体をスピネル型セラミツクスにより構成したこ
とを特徴とする原子炉用計測装置。 2 上記原子炉用計測装置は中性子検出器であ
り、内周面に陰極を有する電離箱ケースとこの電
離箱ケース内に間隔を有して収容された陽極との
間をスピネル型セラミツクスよりなる支持部材に
より絶縁しかつ支持したことを特徴とする特許請
求の範囲第1項記載の原子炉用計測装置。 3 上記中性子検出器は、陽極に接続された信号
ケーブルとこの信号ケーブルの外周に電離箱ケー
スに接続されて設けられた信号ケーブル被覆を有
しており、これら信号ケーブルおよび信号ケーブ
ル被覆との間をスピネル型セラミツクスよりなる
絶縁材により絶縁したことを特徴とする特許請求
の範囲第2項記載の原子炉用計測装置。 4 前記原子炉用計測装置は、温度計測用熱電対
であることを特徴とする特許請求の範囲第1項記
載の原子炉用計測装置。 5 前記原子炉用計測装置は、流速検出用渦電流
形検出器であることを特徴とする特許請求の範囲
第1項記載の原子炉用計測装置。
[Scope of Claims] 1. A nuclear reactor measuring device for performing various measurements in a nuclear reactor, characterized in that an electrically insulating insulator for electrical insulation is made of spinel type ceramics. 2 The nuclear reactor measurement device is a neutron detector, and a support made of spinel type ceramics is used to connect an ionization chamber case having a cathode on the inner peripheral surface and an anode housed at a distance within the ionization chamber case. A nuclear reactor measuring device according to claim 1, characterized in that it is insulated and supported by a member. 3 The above neutron detector has a signal cable connected to the anode and a signal cable sheathing provided around the outer periphery of the signal cable connected to the ionization chamber case. 3. The nuclear reactor measuring device according to claim 2, wherein the reactor is insulated by an insulating material made of spinel type ceramics. 4. The nuclear reactor measuring device according to claim 1, wherein the nuclear reactor measuring device is a thermocouple for temperature measurement. 5. The nuclear reactor measuring device according to claim 1, wherein the nuclear reactor measuring device is an eddy current detector for detecting flow velocity.
JP59072191A 1984-04-11 1984-04-11 Measuring device for nuclear reactor Granted JPS60214295A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP59072191A JPS60214295A (en) 1984-04-11 1984-04-11 Measuring device for nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP59072191A JPS60214295A (en) 1984-04-11 1984-04-11 Measuring device for nuclear reactor

Publications (2)

Publication Number Publication Date
JPS60214295A JPS60214295A (en) 1985-10-26
JPH0477874B2 true JPH0477874B2 (en) 1992-12-09

Family

ID=13482072

Family Applications (1)

Application Number Title Priority Date Filing Date
JP59072191A Granted JPS60214295A (en) 1984-04-11 1984-04-11 Measuring device for nuclear reactor

Country Status (1)

Country Link
JP (1) JPS60214295A (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO1993005520A1 (en) * 1991-09-09 1993-03-18 American Technology, Inc. Spinel insulated electrical components and method for making same
JP2011117900A (en) * 2009-12-07 2011-06-16 Mitsubishi Electric Corp Structure of neutron detector

Also Published As

Publication number Publication date
JPS60214295A (en) 1985-10-26

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