JPS6162811A - Remote measuring apparatus - Google Patents

Remote measuring apparatus

Info

Publication number
JPS6162811A
JPS6162811A JP59184681A JP18468184A JPS6162811A JP S6162811 A JPS6162811 A JP S6162811A JP 59184681 A JP59184681 A JP 59184681A JP 18468184 A JP18468184 A JP 18468184A JP S6162811 A JPS6162811 A JP S6162811A
Authority
JP
Japan
Prior art keywords
support plate
core support
water seal
seal pipe
housing
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.)
Pending
Application number
JP59184681A
Other languages
Japanese (ja)
Inventor
Masahiro Kobayashi
雅弘 小林
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
Toshiba Corp
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 Toshiba Corp filed Critical Toshiba Corp
Priority to JP59184681A priority Critical patent/JPS6162811A/en
Publication of JPS6162811A publication Critical patent/JPS6162811A/en
Pending 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

  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Length Measuring Devices With Unspecified Measuring Means (AREA)

Abstract

PURPOSE:To accurately measure the height difference between a core support plate and a CRT part, by providing a water seal pipe covering a stub tube so as to pierce an upper lattice plate and the core support plate in the vessel of an atomic reactor and performing measurement by using the same pipe. CONSTITUTION:A water seal pipe 22 for discharging the water of an atomic reactor is provided on a CRD (control rod drive mechanism) housing 18 and contacted with the lower mirror inner wall surface of a pressure container 10 in a water-tight state while the upper part pierces a core support plate 13 and the lattice opening of an upper lattice plate 14 to extend upwardly. A transfer sensor 24 is attached to the outer side surface of the water seal pipe 22. The sensor 24 has a probe 25 downwardly protruding in a freely advancing and retracting state and measures the distance X from the reference point 0 of the pipe 22 to the upper surface of the core support plate. A laser measuring apparatus 20 is provided to the upper part of the pipe 22 and measures the distance Y from a laser oscillator 28 to the top part of the CRD housing 18. A counter 26 accurately calculates the height difference A between the top part of the housing 18 and the upper surface of the support plate 13 from the above mentioned measured values X, Y.

Description

【発明の詳細な説明】 〔発明の技術分野〕 本発明は、制御棒駆動機構ハウジング頂部と炉心支持板
の1−面との高低差をh1測する遠隔測定装置に係り、
特に原子炉圧力容器下鏡部のスタブチューブの取り換え
の際、新たに段重した制御n捧駆’uJIi構ハウジン
グ1n部ど炉心支持板の上面との差を遠隔にて測定する
遠隔測定装置に関づる。
[Detailed Description of the Invention] [Technical Field of the Invention] The present invention relates to a remote measuring device that measures the height difference h1 between the top of a control rod drive mechanism housing and the first plane of a core support plate.
In particular, when replacing the stub tube in the lower head of the reactor pressure vessel, a new multi-tiered control system was installed to remotely measure the difference between the upper surface of the core support plate and the lower part of the housing. Related.

〔発明の技術的費用とその問題点〕[Technical costs of inventions and their problems]

沸11i1水型原子炉の原子炉圧力容器1の下鏡には、
第3図および第1図に示すように、制御棒駆動機構ハウ
ジング(、以下、C,RDハウジングという。)2をU
1通支持J−るスタブヂコーブ3が溶接1て取付()ら
れる。このスタブヂュニブ3の溶接部あるいはその近傍
に溶接不良ににる割れヤ)応力腐蝕割れ4等がと1−し
ると、この割れ部分から炉水が外部にリークし、原子炉
の運転を停止さける必要が生じる可能v1がある。
In the lower mirror of the reactor pressure vessel 1 of the boiling water reactor 11i1,
As shown in FIGS. 3 and 1, the control rod drive mechanism housing (hereinafter referred to as C and RD housing) 2 is
A single supporting stubbed cove 3 is attached by welding 1. If cracks or stress corrosion cracks (4) occur due to poor welding at or near the welding part of this stub unit 3, reactor water will leak to the outside from this crack, preventing the reactor from shutting down. There is a possibility v1 that the need will arise.

スタブブ]−ブ3に万一・応力腐蝕割れ等が生じた場合
には、既存のスタブチューブ3を取外し、新たなスタブ
ヂコーブ3を取付IJることが1つの解決方法として考
えられる。この場合には、スタブヂコーブ3のみならず
、CRDハウジング2も同時に新しいものと交換するこ
ととなる。
If stress corrosion cracking or the like occurs in the stub tube 3, one possible solution is to remove the existing stub tube 3 and install a new stub tube 3. In this case, not only the stubbed cove 3 but also the CRD housing 2 will be replaced with a new one at the same time.

その際、CRDハウジング2の高さ位置と炉心支持板5
の高さ位置は炉心6を形成覆る重要な寸法である。特に
、CRr)ハウジング2と炉心支持板5との間には、炉
心制御用制御棒を収納覆る制御棒案内管7が取付けられ
、この案内管は、取付精度の関係から、所定の制限寸法
内に取付けられなl−Jれば(2らイ」゛い。イのため
、Iネ子炉据イ・t ll”、iにおいて、(E RD
ハウジング2取イ・1後に、炉心支J!I板5F品から
の高低差を非常に精度良く測定しくいる。
At that time, the height position of the CRD housing 2 and the core support plate 5
The height position is an important dimension for forming the reactor core 6. In particular, a control rod guide tube 7 is installed between the CRr) housing 2 and the core support plate 5 to house and cover the core control control rods, and this guide tube must be within a predetermined size limit due to installation accuracy. If l-J cannot be installed on the
After housing 2 and 1, core support J! The height difference from the I plate 5F product can be measured with very high accuracy.

したがって、CRDハウジング2を交換した場合には、
交換された新しい(CRDハウジング2の頂部と炉心支
持板5の−1−面との高低Xを、粘1!J IJく測定
覆−る必要がある。しかし、CRr)ハウジング2の交
換■、冒こは、原子炉圧力容器1内が炉水で満されてお
り、放用線肢1rIl″、r1′の環境問題から、11
業者が原子炉内に入って直接測定J゛ることは不可能で
あり、CRI’)ハウジングIC1部と炉心支持(ルの
、上面との差を精度良く測定ηることは困勤であった。
Therefore, when CRD housing 2 is replaced,
It is necessary to measure and cover the height X between the top of the replaced new (CRD housing 2 and the -1-plane of the core support plate 5. However, the replacement of the CRr) housing 2, The reason for this is that the inside of the reactor pressure vessel 1 is filled with reactor water, and due to the environmental problems of the radiation limbs 1rIl'' and r1', 11
It was impossible for a contractor to enter the reactor and directly measure it, and it was difficult to accurately measure the difference between the top surface of the IC 1 part of the CRI housing and the core support. .

。 〔発明の目的〕 本発明は上述した事情を考hu シー(、’ /7され
たもので、CRI’)ハウジング頂部と炉心支持板上面
どの高低差を遠隔にて精度良く連続的に測定でることが
でき、作采員の被曝を名しく軽減さ1!た遠隔測定装置
を提供Jることを目的どづる。
. [Objective of the Invention] Considering the above-mentioned circumstances, the present invention is to remotely and accurately measure the difference in height between the top of the CRI' housing and the top surface of the core support plate. This significantly reduces radiation exposure for production personnel! The purpose is to provide a remote measuring device.

〔発明の概要) 上述した目的を達成するために、本発明に係る遠隔測定
装置は、原子炉圧力容器の下鏡にスタブチューブを介し
て制御棒駆動機構ハウジングを設【プたものにおいて、
上記原子炉圧力容器内に原子炉水を拮除する水シールパ
イプを、上部格子板および炉心支持板を貫い゛て前記ス
タブヂコーブを覆うように立設し、この水シールパイプ
に°炉心支持板の上面と制御棒駆動機構ハウジング頂部
との高低差を測定Jる無接触タイプの距1II11測定
装買を備えたことを特徴とするものである。
[Summary of the Invention] In order to achieve the above-mentioned object, a remote measuring device according to the present invention includes a control rod drive mechanism housing installed in the lower mirror of a reactor pressure vessel via a stub tube.
A water seal pipe for removing reactor water is installed in the reactor pressure vessel so as to pass through the upper grid plate and the core support plate and cover the stubbed cove, and this water seal pipe is connected to the core support plate. It is characterized by being equipped with a non-contact type distance measuring device for measuring the height difference between the upper surface and the top of the control rod drive mechanism housing.

〔発明の実施例〕[Embodiments of the invention]

以下、本発明に係る′遠隔測定装置の好ましい実施例に
ついて添付図面を参照して説明する。
Hereinafter, preferred embodiments of the telemetry device according to the present invention will be described with reference to the accompanying drawings.

第1図において、符号10は沸騰水型原子炉の原子炉圧
力容器を示し、この圧力容器10内には炉心11を形成
するシュラウド12が収容される。
In FIG. 1, reference numeral 10 indicates a reactor pressure vessel of a boiling water reactor, and a shroud 12 forming a reactor core 11 is accommodated within this pressure vessel 10.

シコラウド12の下部には炉心11を支持する炉心支持
板13ど炉心」一部を支える上゛部格子板14が収納さ
れており、炉心支持板13には制御棒案内管15を通J
多数のξ1通穴が穿設される5、各穴に対応する原子炉
圧力容器10の下部鏡板には、スタブヂコーブ17が溶
接にて1+7 n9され、このスタブヂコーブ17に下
部鏡板をr」通して延びる制御棒駆動(幾構ハウジング
18の」一部が溶接にて固定される。
A core support plate 13 that supports the reactor core 11 and an upper lattice plate 14 that support part of the reactor core are housed in the lower part of the shikoroud 12. The core support plate 13 has control rod guide tubes 15 inserted through it.
A number of ξ1 through holes are drilled 5, and a stubde cove 17 is welded 1+7n9 to the lower head plate of the reactor pressure vessel 10 corresponding to each hole, and the lower head plate extends through the stubde cove 17 by r''. A portion of the control rod drive (of the housing 18) is fixed by welding.

しかして、制御棒案内管15はCRDハウジング18の
頂部に乗■られて支持され、ぞのLIJは炉心支持板1
3の11通穴内に支持され、案内管頂部には炉心燃Fl
 (/I f4の燃料集合体)1つが叔Pマされる。制
御棒案内管15内には図示し41い制御棒が出し入れ自
在に収容され、この制御棒はCRDハウジング18に収
容された制御棒駆動機構(図示せず)により下方から挿
入され、原子炉出力をコントロールづ−るJ:うになっ
ている。このように炉心支持板13の高さ位置どCRO
ハウジング18の高さ位置は炉心11を形成覆る重要な
寸法であり、その高低差へは無接触タイプの距離測定装
置としてのレーザ測定装動20により遠隔にて測定され
る。
Thus, the control rod guide tube 15 is supported by riding on the top of the CRD housing 18, and the LIJ is mounted on the core support plate 1.
It is supported in the 11 through holes of 3, and the core fuel Fl
(/I f4 fuel assembly) One is removed. A control rod (41 in the figure) is housed in the control rod guide tube 15 so that it can be taken in and out. J: The sea urchin is turning. In this way, the height position of the core support plate 13
The height position of the housing 18 is an important dimension that forms and covers the reactor core 11, and the difference in height is remotely measured by a laser measuring device 20 as a non-contact type distance measuring device.

ところで、CRCハウジングを支えるスタブヂ]−11
7は原子炉圧力容器10の下端に溶接されているが、こ
のスタブチューブ17の溶接部あるいはその近傍に、溶
接不良や応力腐蝕割れ等にJ、りひび割れが生じた場合
には、原子炉の炉水がリークゴる恐れがあるので、既存
のCRDハウジング18とスタブヂ1−ブ17を取外し
、新たなスタブチューブ17とCRDハウジング18と
に交換覆る。
By the way, the stub that supports the CRC housing]-11
7 is welded to the lower end of the reactor pressure vessel 10, but if cracks occur at or near the welded part of the stub tube 17 due to poor welding or stress corrosion, the reactor Since reactor water may leak, the existing CRD housing 18 and stub tube 17 are removed, replaced with new stub tubes 17 and CRD housing 18, and covered.

この交換作業により、新しいスタブチューブ17とCR
Dハウジング18が取着される場合、CRDハウジング
頂部と炉心支持板13の上面との高低差へは、炉心形成
上重要な寸法であり、レーザ測定装置20により測定さ
れる。
Through this replacement work, a new stub tube 17 and CR
When the D housing 18 is attached, the difference in height between the top of the CRD housing and the upper surface of the core support plate 13 is an important dimension in forming the core, and is measured by the laser measuring device 20.

この測定を行なう場合には、測定しJ:うとするCRD
ハウジング18上部の炉心燃1119や制御棒、制御棒
案内管15を取外して、l13き、新たに取イ・1けた
CRDハウジング18の十に原子炉の炉水を排除づるた
めに水シールパイプ22が立設される。水シールパイプ
22は下端が原子炉圧力容器10の下鏡内壁面に水密に
接し、イの上部は炉心支持板13のLq通穴ヤ)上部格
子板1/lの格子[1を員いて子方に延び、その上部;
は+Xi = t″″″スプラツ]−ム231ニに達し
、終端している。プラン1〜ホーム23は原子炉圧力容
器10の1部フランジ部に、そのし8部間[1を覆うに
うに11日J渡される。
When performing this measurement, the CRD to be measured is
The reactor core 1119, control rods, and control rod guide tubes 15 on the upper part of the housing 18 are removed, and a new one is installed.A water seal pipe 22 is installed in the upper part of the CRD housing 18 to remove reactor water. will be erected. The lower end of the water seal pipe 22 is in watertight contact with the inner wall surface of the lower mirror of the reactor pressure vessel 10, and the upper part of the water seal pipe 22 is in contact with the Lq through hole of the core support plate 13). extending towards the top;
+Xi = t'''''' splat] - M 231 and terminates. Plans 1 to 23 are attached to one part of the flange part of the reactor pressure vessel 10, and then eight parts to cover [1]. J was handed over on the 11th.

上記水シールパイプ22の一外周面には移送レンザ24
が取(=I ljられる。この移送レンi+ 24は炉
心支持板13の土面より少し十/iに設(]らね、下方
に突出する接触子25を進退自在に右する。。
A transfer lens 24 is provided on one outer peripheral surface of the water seal pipe 22.
is taken (=I lj. This transfer lane i+ 24 is installed at a distance of a little 10/i from the earth surface of the core support plate 13, and allows the contact 25 protruding downward to move forward and backward.

このとき、水シールパイプ22には基111点0が定め
られ、このIJ準点Oから移送はンリ“24の接触了先
喘までの距呻は予め定められている、1しかして、水シ
ールパイプ22を原子炉圧力容器10内で立設さU、炉
心支持板13の−1−面に接触子25が接することにJ
:す、接触子25は移送レン1J′24の例えば電磁コ
イル内を後退Iしめられ、その後313 B!は力「ン
ンタ26にてカラン1〜される。これにJ:す、水シー
ルパイプ22の基準点Oから炉心支持板上面までの距P
Jt Xを測定することができる。
At this time, a base 111 point 0 is determined for the water seal pipe 22, and the distance from this IJ quasi-point O to the point at which the transfer is completed is predetermined. The pipe 22 is erected in the reactor pressure vessel 10, and the contact 25 is in contact with the -1- surface of the core support plate 13.
:S, the contact 25 is retracted in the electromagnetic coil of the transfer lens 1J'24, and then 313B! The force is applied to the cylinder 26 at the 1st position.
JtX can be measured.

一方、新たに取イ・ロブられたCRDハウジング18の
頭部に第2図に示すように反則板27が着脱自在に取イ
」けられ、前記水シールパイプ22の上部にはレーザ発
振器28が設置される。このレーザ発振器28や反射板
27、光検出器29によりレーザ測定装置20が組成さ
れる。しかして、レ−IJ”発振器28から発振された
]ヒーレントなレーザ光は、水シールパイプ22内を通
り、CRr)ハウジング頂部の反射板27に反射されて
再びレーザ発振器28に戻り、光検出器29により検出
される。この検出は発振レーザ光と反aル−ザ光の時間
遅れを検出することにj:り行なわれ、その検出信号は
例えば、チャンネルや切換スイッチ等の]ン1〜「1−
ラ30を経てカウンタ26に送られ、ここでカラン1〜
され、レーザ発振器28から反0・1板27までの距1
111 Yが測定される。
On the other hand, a fouling plate 27 is detachably attached to the head of the newly removed CRD housing 18 as shown in FIG. will be installed. A laser measurement device 20 is composed of the laser oscillator 28, the reflection plate 27, and the photodetector 29. The coherent laser beam oscillated from the laser oscillator 28 passes through the water seal pipe 22, is reflected by the reflector 27 on the top of the CRr housing, returns to the laser oscillator 28, and is sent to the photodetector. 29. This detection is carried out by detecting the time delay between the oscillating laser beam and the anti-aluminum laser beam, and the detection signal is transmitted, for example, to channels, changeover switches, etc. 1-
It is sent to the counter 26 through the line 30, where it is sent to the counter 26.
and the distance from the laser oscillator 28 to the anti-0.1 plate 27 is 1
111 Y is measured.

しかして、レーザ測定装置20により測定された距離Y
は予め測定された距111X、Zとカウンタ26にて演
算され、この演算結果(Y−X−Z)からCRDハウジ
ング18の頂部ど炉心支持板13の」−面どの高低差へ
が正確に求められろ。測定された高低差へは図示しイ1
い表示パネル等の表示器に連続的に表示させでもよい。
Therefore, the distance Y measured by the laser measuring device 20
is calculated using the pre-measured distances 111 Let it go. The measured height difference is shown in the diagram.
It may be displayed continuously on a display device such as a display panel.

この表示器はカウンタ26に接続される。This indicator is connected to counter 26.

<rお、本発明の−・実施例の説明においては、距N1
測定装置どしてレーザ光を使用したレーザ測定装置を用
いた例について説明したが、このレーザ測定装置に代え
て超音波を使用した超?゛?波測定装置などの無接触タ
イプの距1311測定装置tを使用してもJ:い。
<rO, in the description of the embodiments of the present invention, the distance N1
We have explained an example using a laser measuring device that uses a laser beam as the measuring device, but what about an ultrasonic device that uses ultrasound instead of this laser measuring device?゛? Even if a non-contact type distance measuring device such as a wave measuring device is used, it is not possible.

〔発明の効宋〕[Efficacy of invention Song Dynasty]

以上に述べたように本発明に係る遠隔’JI’I定装z
jは、原子炉圧力容器内に原子炉水をIJI除りる水シ
ールパイプを、上部格子板おJ:び炉心支持板をvlい
て前記スタブチューブを覆うように立設し、この水シー
ルパイプ炉心支持板の上面と制御棒駆動機構ハウジング
10部どの高低差を測定Jる距H1測定装買を設けたか
ら、この距離1測定装買にj、り炉心支持板の1−面か
ら制御棒駆動機構ハウジング((i部までの距離を遠隔
にて連続的に測定することができる。したがって、制御
棒駆動機構ハウジングが溶接途上であり、刻々高さ変化
がある場合でら連続して測定することが可能である。
As described above, the remote 'JI'I fixed installation according to the present invention
j is a water seal pipe for removing reactor water IJI installed in the reactor pressure vessel so as to cover the stub tube with the upper lattice plate and core support plate vl, and this water seal pipe Since a distance H1 measuring device was installed to measure the height difference between the upper surface of the core support plate and the control rod drive mechanism housing 10, this distance H1 measuring device was used to measure the height difference between the upper surface of the core support plate and the control rod drive mechanism housing 10. The distance to the mechanism housing ((i) can be measured remotely and continuously. Therefore, even if the control rod drive mechanism housing is in the process of being welded and the height changes from moment to moment, continuous measurement is possible. is possible.

ざらに、無接触タイプの距離測定装冒により炉心支持板
−1面と制御棒駆動機構ハウジング頂部との距#1を、
被測定物に直接接触させることなく、非接触にて遠隔か
ら測定できるので、測定作業中の放射線の被曝を著しく
軽減させることができる。。
Roughly, distance #1 between the core support plate-1 surface and the top of the control rod drive mechanism housing is determined using a non-contact type distance measuring device.
Since measurement can be performed remotely without direct contact with the object to be measured, exposure to radiation during measurement work can be significantly reduced. .

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

第1図は本発明に係る遠隔測定装置を組み込lυだ沸騰
水型原子炉の炉内状態を示す断面図、第2図はレーザ発
振器と移送センサとを取付けた水シールパイプを示す図
、第3図は沸騰水型原子炉の炉内状態を示す断面図、第
4図は原子炉圧力容器下鏡に設けられるスタブチューブ
の想定される割れ状態を示す図である。 10・・・原子炉圧力容器、11・・・炉心、12・・
・シコラウド、13・・・炉心支持板、1/l・・・上
部格子板、15・・・制御棒案内管、17・・・スタブ
チューブ、18・・・制御棒駆動+ff +1”rハウ
ジング、20・・・レーリ゛測定装胃、22・・・水シ
ールパイプ、2A・・・移送Pン1ノ、26・・・カウ
ンタ、27・・・反則1反、28・・・1ノ一ザ発振器
、29・・・光検出器。
FIG. 1 is a sectional view showing the internal state of a boiling water reactor incorporating a remote measuring device according to the present invention, and FIG. 2 is a diagram showing a water seal pipe to which a laser oscillator and a transfer sensor are attached. FIG. 3 is a cross-sectional view showing the internal state of a boiling water reactor, and FIG. 4 is a diagram showing an assumed cracked state of a stub tube provided in the lower mirror of the reactor pressure vessel. 10...Reactor pressure vessel, 11...Reactor core, 12...
・Shikoroud, 13... Core support plate, 1/l... Upper grid plate, 15... Control rod guide tube, 17... Stub tube, 18... Control rod drive +ff +1"r housing, 20...Ray measurement device, 22...Water seal pipe, 2A...Transfer Pn1, 26...Counter, 27...1 foul, 28...1 nozzle Oscillator, 29... photodetector.

Claims (1)

【特許請求の範囲】 1、原子炉圧力容器の下鏡にスタブチューブを介して制
御棒駆動機構ハウジングを設けたものにおいて、上記原
子炉圧力容器内に原子炉水を排除する水シールパイプを
、上部格子板および炉心支持板を貫いて前記スタブチュ
ーブを覆うように立設し、この水シールパイプに炉心支
持板の上面と制御棒駆動機構ハウジング頂部との高低差
を測定する無接触タイプの距離測定装置を備えたことを
特徴とする遠隔測定装置。 2、距離測定装置は、レーザ測定装置であり、このレー
ザ測定装置は、水シールパイプの上部に設けられたレー
ザ発振器と、このレーザ発振器からの発振レーザ光を反
射させる制御棒駆動機構ハウジング頂部に形成された反
射板と、この反射板からの反射レーザ光を検出する光検
出器とを有し、この光検出器で検出された反射レーザ光
の時間遅れからレーザ発振器から反射板までの距離を測
定する特許請求の範囲第1項に記載の遠隔測定装置。 3、水シールパイプの外周に移送センサが設けられ、こ
の移送センサは水シールパイプを立設したとき、炉心支
持板の上面に接触する接触子を進退自在に有し、前記水
シールパイプから移送センサの接触子先端までの距離が
予め定められた特許請求の範囲第1項に記載の遠隔測定
装置。
[Claims] 1. A control rod drive mechanism housing is provided on the lower mirror of the reactor pressure vessel via a stub tube, and a water seal pipe for discharging reactor water into the reactor pressure vessel, A non-contact type distance is installed to penetrate the upper grid plate and core support plate and cover the stub tube, and this water seal pipe measures the height difference between the top surface of the core support plate and the top of the control rod drive mechanism housing. A remote measuring device comprising a measuring device. 2. The distance measuring device is a laser measuring device, and this laser measuring device includes a laser oscillator installed at the top of the water seal pipe and a control rod drive mechanism housing top that reflects the oscillated laser light from the laser oscillator. The distance from the laser oscillator to the reflector is determined from the time delay of the reflected laser light detected by the photodetector. A telemetry device according to claim 1 that performs measurement. 3. A transfer sensor is provided on the outer periphery of the water seal pipe, and this transfer sensor has a contact that can move forward and backward in contact with the upper surface of the core support plate when the water seal pipe is erected. The telemetry device according to claim 1, wherein the distance to the tip of the contact of the sensor is predetermined.
JP59184681A 1984-09-05 1984-09-05 Remote measuring apparatus Pending JPS6162811A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP59184681A JPS6162811A (en) 1984-09-05 1984-09-05 Remote measuring apparatus

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP59184681A JPS6162811A (en) 1984-09-05 1984-09-05 Remote measuring apparatus

Publications (1)

Publication Number Publication Date
JPS6162811A true JPS6162811A (en) 1986-03-31

Family

ID=16157503

Family Applications (1)

Application Number Title Priority Date Filing Date
JP59184681A Pending JPS6162811A (en) 1984-09-05 1984-09-05 Remote measuring apparatus

Country Status (1)

Country Link
JP (1) JPS6162811A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN106767281A (en) * 2016-12-28 2017-05-31 郑州飞龙汽车部件有限公司 Water seal assembly height measurement method and realize the measurement apparatus of the method
CN107305116A (en) * 2016-04-14 2017-10-31 上海卡姆南洋医疗器械股份有限公司 A kind of Novel B ultrasonic probe is apart from display circuit device
CN111462928A (en) * 2020-03-09 2020-07-28 岭东核电有限公司 Laser measurement method, system, equipment and medium for nuclear power station thermal sleeve flange abrasion

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN107305116A (en) * 2016-04-14 2017-10-31 上海卡姆南洋医疗器械股份有限公司 A kind of Novel B ultrasonic probe is apart from display circuit device
CN106767281A (en) * 2016-12-28 2017-05-31 郑州飞龙汽车部件有限公司 Water seal assembly height measurement method and realize the measurement apparatus of the method
CN106767281B (en) * 2016-12-28 2023-10-13 郑州飞龙汽车部件有限公司 Water seal assembly height measurement method and measurement device for realizing same
CN111462928A (en) * 2020-03-09 2020-07-28 岭东核电有限公司 Laser measurement method, system, equipment and medium for nuclear power station thermal sleeve flange abrasion

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