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JPH0237557B2 - - Google Patents
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JPH0237557B2 - - Google Patents

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Publication number
JPH0237557B2
JPH0237557B2 JP56206197A JP20619781A JPH0237557B2 JP H0237557 B2 JPH0237557 B2 JP H0237557B2 JP 56206197 A JP56206197 A JP 56206197A JP 20619781 A JP20619781 A JP 20619781A JP H0237557 B2 JPH0237557 B2 JP H0237557B2
Authority
JP
Japan
Prior art keywords
plug
inspection
reactor
opening
partition
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
JP56206197A
Other languages
Japanese (ja)
Other versions
JPS58108491A (en
Inventor
Kenji Azuma
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 JP56206197A priority Critical patent/JPS58108491A/en
Publication of JPS58108491A publication Critical patent/JPS58108491A/en
Publication of JPH0237557B2 publication Critical patent/JPH0237557B2/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

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  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 (発明の技術分野) 本発明は、たとえば液体ナトリウムを冷却材に
使用する高速増殖炉の原子炉容器(以下、炉容器
と称す)内部を遠隔操作で検査できるようにした
原子炉炉内の検査装置に関する。
Detailed Description of the Invention (Technical Field of the Invention) The present invention provides a method for remotely inspecting the inside of a reactor vessel (hereinafter referred to as the reactor vessel) of a fast breeder reactor that uses liquid sodium as a coolant, for example. The present invention relates to an inspection device inside a nuclear reactor.

(発明の技術的背景とその問題点) 一般に、液体ナトリウムを冷却材に使用する高
速増殖炉では、炉容器内のほぼ中央部に炉心燃料
集合体およびブランケツト燃料集合体からなる炉
心を配置し、この炉心を炉心支持構造物により支
持している。
(Technical background of the invention and its problems) Generally, in a fast breeder reactor that uses liquid sodium as a coolant, a core consisting of a core fuel assembly and a blanket fuel assembly is placed approximately in the center of the reactor vessel. This core is supported by a core support structure.

また、この炉心支持構造物は炉容器内の下部側
壁に取付けた取付けフランジにより載置され固定
されている。
Further, this core support structure is mounted and fixed by a mounting flange attached to a lower side wall within the reactor vessel.

この取付けフランジは、仕切り板として冷却材
が流れる圧力領域を異ならしめ、フランジの下方
が高圧プレナム領域に、フランジの上方が低圧プ
レナム領域になるように維持している。
The mounting flange acts as a partition plate to differentiate the pressure areas through which the coolant flows, maintaining a high pressure plenum area below the flange and a low pressure plenum area above the flange.

そして、冷却材はそれぞれの燃料集合体内に所
定の圧力で流入するように流量配分がなされ調整
されて流れている。
The flow rate of the coolant is regulated so that it flows into each fuel assembly at a predetermined pressure.

また、炉容器内の冷却材はカバーガスで覆われ
ており、炉容器の遮蔽プラグの上面から直接炉容
器内の下部高圧領域に検査装置をアクセスさせる
ことが困難になつている。
Furthermore, the coolant inside the reactor vessel is covered with a cover gas, making it difficult to allow an inspection device to directly access the lower high-pressure region within the reactor vessel from the top surface of the shielding plug of the reactor vessel.

さらに、高速増殖炉では炉心の燃料交換を行う
場合、アンダーザプラグ方式と称する二重回転プ
ラグにより炉容器の上部から駆動機構で操作して
グリツパにより燃料集合体を握持しているために
炉容器の遮蔽プラグを容易に取りはずすことがで
きない。
Furthermore, when replacing fuel in the core of a fast breeder reactor, a double rotating plug known as the under-the-plug method is operated by a drive mechanism from the top of the reactor vessel, and grippers grip the fuel assembly. Container shielding plug cannot be easily removed.

そこで、一般に炉容器内の検査または補修作業
などは遮蔽プラグをとりはずさない状態で行なわ
れている。
Therefore, inspection or repair work inside the reactor vessel is generally performed without removing the shielding plug.

炉心の異常状態を検査する場合、たとえば炉心
燃料集合体の冷却材による浮き上りを監視する場
合には、超音波送受波器によるナトリウム透視装
置を使用し、またカバーガス空間領域ならびに低
圧プレナム領域の表面状態を検査する場合には
ITV(産業用テレビカメラ)などが使用されてい
る。
When inspecting abnormal conditions in the reactor core, for example, when monitoring the uplift of core fuel assemblies due to coolant, a sodium fluoroscopy system with an ultrasonic transducer is used, and the cover gas space area and low pressure plenum area are inspected. When inspecting the surface condition
ITV (industrial television camera) etc. are used.

しかしながら、ITVまたはナトリウム透視装
置では、炉容器内をできるだけ隅々まで検査した
い場合その広角範囲が限定されるため容易に検査
できない不都合さがあり、とくに高圧プレナム領
域の検査が困難である。
However, ITV or sodium fluoroscopy equipment has the disadvantage that if you want to inspect every corner of the reactor vessel as much as possible, it cannot be inspected easily because its wide-angle range is limited, and inspection of the high-pressure plenum region is particularly difficult.

したがつて、炉容器内とくに高圧プレナム領域
の表面状態ならびに異常を容易に検査できる装置
が要望される。
Therefore, there is a need for an apparatus that can easily inspect the surface condition and abnormalities within the reactor vessel, particularly in the high pressure plenum region.

(本発明の目的) 本発明は上記要望を満足させるためになされた
もので、原子炉の運転中において放射化のため作
業員が接近できない炉容器の内部、とくに炉容器
の炉心支持構造物の取付けフランジより下方の高
圧プレナム領域の内面およびその周辺を遠隔操作
で容易に検査できるようにした原子炉炉心の検査
装置を提供することにある。
(Objective of the present invention) The present invention has been made to satisfy the above-mentioned needs.The present invention has been made in order to satisfy the above-mentioned needs. An object of the present invention is to provide a nuclear reactor core inspection device that allows the inner surface of a high-pressure plenum region below a mounting flange and its surroundings to be easily inspected by remote control.

(本発明の構成) 本発明は上記目的を達成するために、炉容器の
上部開口を閉塞する遮蔽プラグに貫通孔を設け、
かつ、この貫通孔に検査プラグを挿着し、この検
査プラグに仕切り機構を介して炉容器内の取付フ
ランジまで延存して開口する案内管を接続し、こ
の案内管内を任意に移動ができる炉内検出器を設
けてなることを特徴とする検査装置であり、炉内
検査時には炉容器の上部から遠隔操作で仕切り機
構を開いて専用の高圧プレナム検査装置を据付
け、高圧プレナム領域の表面およびその周辺の状
態を検査できるようにしたことにある。
(Structure of the present invention) In order to achieve the above object, the present invention provides a through hole in a shielding plug that closes the upper opening of the furnace vessel,
In addition, an inspection plug is inserted into this through hole, and a guide tube that extends and opens to a mounting flange in the furnace vessel is connected to this inspection plug via a partition mechanism, so that it can be moved arbitrarily within this guide tube. This is an inspection device that is equipped with an in-furnace detector, and when inspecting the inside of the reactor, a partition mechanism is opened remotely from the top of the reactor vessel, and a dedicated high-pressure plenum inspection device is installed to inspect the surface of the high-pressure plenum area and The purpose is to enable inspection of the surrounding conditions.

(本発明の実施例) 以下、図面を参照して本発明の一実施例を説明
する。
(Embodiment of the present invention) An embodiment of the present invention will be described below with reference to the drawings.

第1図において、符号1は高速増殖炉の炉容器
を示すものであつて、この炉容器1内のほぼ中央
部の下方には炉心燃料集合体群とその周囲に配列
されたブランケツト集合体群とからなる炉心2が
配置されている。
In FIG. 1, reference numeral 1 indicates a reactor vessel of a fast breeder reactor, and below the approximately central portion of the reactor vessel 1 are a group of core fuel assemblies and a group of blanket assemblies arranged around the core fuel assemblies. A reactor core 2 consisting of

この炉心2は、炉心支持構造物3で支持され、
この炉心支持構造物3は炉容器1の内壁面に接続
された取付けフランジ4に載置されて固定されて
いる。
This core 2 is supported by a core support structure 3,
This core support structure 3 is mounted and fixed on a mounting flange 4 connected to the inner wall surface of the reactor vessel 1.

炉容器1の上部開口は、遮蔽プラグ、つまり大
回転プラグ5および小回転プラグ6により閉塞さ
れている。
The upper opening of the furnace vessel 1 is closed by shielding plugs, that is, a large rotation plug 5 and a small rotation plug 6.

小回転プラグ6には中央部を貫通し前記炉心2
の上方にまで達する炉心上部機構7が設けられて
いる。
The small rotating plug 6 has a central portion that penetrates through the core 2.
A core upper mechanism 7 is provided that reaches above the core.

また、炉容器1の底部には炉心2へ冷却材のナ
トリウムを流通するための冷却材入口ノズル8
が、炉容器1の側面には加熱された冷却材ナトリ
ウムを流出する出口ノズル9がそれぞれ接続され
ており、炉容器1内のナトリウム10の上部空間
11には冷却材の酸化を防止するために不活性ガ
スたとえばアルゴンガスがカバーガスとして充填
されている。
Also, at the bottom of the reactor vessel 1, there is a coolant inlet nozzle 8 for distributing sodium coolant to the reactor core 2.
However, outlet nozzles 9 for flowing out the heated sodium coolant are connected to the sides of the furnace vessel 1, and a space 11 above the sodium 10 in the furnace vessel 1 is provided with an outlet nozzle 9 to prevent the coolant from oxidizing. An inert gas such as argon gas is filled as a cover gas.

さらに、大回転プラグ5には大型の貫通孔12
が設けられており、この貫通孔12には検査プラ
グ13が挿着される。
Furthermore, the large rotation plug 5 has a large through hole 12.
is provided, and a test plug 13 is inserted into this through hole 12.

検査プラグ13には、中径の貫通孔14と、小
径の貫通孔15が設けられている。
The inspection plug 13 is provided with a medium diameter through hole 14 and a small diameter through hole 15.

中径の貫通孔14には炉内検査装置としての駆
動機構16の下部に接続した延長管17が挿入さ
れ、この延長管17には仕切り機構18a,18
bが接続されている。
An extension pipe 17 connected to the lower part of a drive mechanism 16 serving as a furnace inspection device is inserted into the medium-diameter through hole 14, and partition mechanisms 18a and 18 are inserted into this extension pipe 17.
b is connected.

仕切り機構18a,18bの下部には案内管1
9が接続されており、この案内管19は炉容器1
の内面に設けたサポート20で支持されるととも
に、案内管19の端末部は前記取付フランジ4の
開孔21に接続されている。
A guide tube 1 is provided at the bottom of the partition mechanisms 18a and 18b.
9 is connected, and this guide pipe 19 is connected to the furnace vessel 1.
The guide tube 19 is supported by a support 20 provided on the inner surface thereof, and the end portion of the guide tube 19 is connected to the opening 21 of the mounting flange 4.

案内管19内には、操作ロツド22が挿入され
ており、操作ロツド22の上部は前記駆動機構1
6に接続して上下動および回転方向に操作され
る。
An operating rod 22 is inserted into the guide tube 19, and the upper part of the operating rod 22 is connected to the drive mechanism 1.
6 and is operated in vertical and rotational directions.

また、操作ロツド22の下部には検出器23、
たとえば超音波送受波器が接続されている。
In addition, a detector 23 is located at the bottom of the operating rod 22,
For example, an ultrasonic transducer is connected.

また、前記検査プラグ13の小径の貫通孔15
には開閉装置24の動作機構25が挿入され、動
作機構25の下方には、前記仕切り機構18a,
18bの側面にそれぞれ形成される開閉機構26
a,26bが設けられて前記仕切り機構18a,
18bと接合し連動する。
In addition, the small diameter through hole 15 of the inspection plug 13
An operating mechanism 25 of the opening/closing device 24 is inserted into the opening/closing device 24, and below the operating mechanism 25, the partition mechanisms 18a,
Opening/closing mechanism 26 formed on each side of 18b
a, 26b are provided and the partition mechanism 18a,
It is connected to and interlocks with 18b.

すなわち、開閉装置24を駆動することによつ
て前記仕切り機構18a,18bに設けられた図
示してないシヤツターを開閉するようになつてい
る。
That is, by driving the opening/closing device 24, shutters (not shown) provided in the partition mechanisms 18a, 18b are opened and closed.

なお、炉容器1内の取付けフランジ4を境とし
て、その下方は高圧プレナム領域HPであり、ま
たその上方は低圧プレナム領域LPである。
Note that below the mounting flange 4 in the furnace vessel 1 as a boundary is a high pressure plenum region HP, and above it is a low pressure plenum region LP.

なお、炉内検査装置としての駆動機構16、延
長管17および検出器23ならびに開閉装置2
4、動作機構25を使用しない場合には各々の貫
通孔14,15には第2図に示すごとくダミープ
ラグ27,28が挿入される。
In addition, the drive mechanism 16, extension tube 17, detector 23, and switchgear 2 as a furnace inspection device
4. When the operating mechanism 25 is not used, dummy plugs 27 and 28 are inserted into the through holes 14 and 15, respectively, as shown in FIG.

なお、必要があれば、遮蔽プラグ上の他の位置
に炉内検査装置用の貫通孔12を複数箇所に設け
て炉内検査の能力向上を計ることも可能である。
Incidentally, if necessary, it is also possible to provide multiple through-holes 12 for in-furnace inspection equipment at other positions on the shielding plug to improve the capability of in-furnace inspection.

第3図は本発明の他の実施例を示すもので、案
内管19の外面又は内面にナトリウムの温度の急
激な変化から案内管19を保護するための熱しや
へい体29を設けた例を示す。
FIG. 3 shows another embodiment of the present invention, in which a heat shielding body 29 is provided on the outer or inner surface of the guide tube 19 to protect the guide tube 19 from sudden changes in the temperature of sodium. show.

(本発明の作用) 次に上記構成の炉内検査装置を使用して原子炉
容器内の特に冷却材高圧プレナム領域の表面検査
を行なう方法について説明する。
(Effects of the Invention) Next, a method of inspecting the surface of the reactor vessel, particularly the high-pressure coolant plenum region, using the in-core inspection device configured as described above will be described.

原子炉の出力運転時には第3図に示すごとく、
大回転プラグ5上の検査プラグ13の貫通孔1
4,15にはダミープラグ27,28を挿入して
カバーガスパウンダリおよび熱・放射能しやへい
機能を果している。
During power operation of the reactor, as shown in Figure 3,
Through hole 1 of inspection plug 13 on large rotating plug 5
Dummy plugs 27 and 28 are inserted into the holes 4 and 15 to serve as a cover gas powder and to protect against heat and radiation.

また案内管19の上端部にある仕切機構18
a,18bは開閉装置24により閉じられて冷却
材は高圧プレナムHPと低圧プレナムLPとの仕切
機能を果している。
Also, a partition mechanism 18 at the upper end of the guide tube 19
a and 18b are closed by an opening/closing device 24, and the coolant serves as a partition between the high pressure plenum HP and the low pressure plenum LP.

一方、原子炉停止後炉内検査時には原子炉モー
ドをメンテナンスモードに切換えた後、第1図に
示すごとくダミープラグ28を引抜いた後、開閉
装置24、動作機構25を検査プラグ13に据付
けてから動作機構25の先端を開閉機構26a,
26bの駆動部分と機械的に結合後、開閉機構2
6a,26bの動作を介して仕切り機構18a,
18bを開状態にする。
On the other hand, when inspecting the reactor interior after reactor shutdown, the reactor mode is switched to maintenance mode, the dummy plug 28 is pulled out as shown in FIG. An opening/closing mechanism 26a at the tip of the operating mechanism 25,
After mechanically coupling with the drive part of 26b, the opening/closing mechanism 2
The partition mechanism 18a, through the operation of 6a, 26b.
18b is opened.

その後、検査プラグ13の他の貫通孔14より
ダミープラグ27を引抜き炉内検査装置の駆動装
置16、延長管17、検出器23を据付ける。
Thereafter, the dummy plug 27 is pulled out from the other through hole 14 of the inspection plug 13, and the drive device 16, extension tube 17, and detector 23 of the furnace inspection device are installed.

駆動装置16の動作により延長管17を延ばし
下端の検出器23を炉心支持構造物3の取付フラ
ンジ4から下方空間に位置させ、所望の方位に検
出器23を位置決めして、高圧プレナム領域HP
にある対象物の表面検査を行なう。
The extension tube 17 is extended by the operation of the drive device 16, and the detector 23 at the lower end is positioned in the space below from the mounting flange 4 of the core support structure 3, and the detector 23 is positioned in a desired direction, and the detector 23 is positioned in the high pressure plenum area HP.
Perform surface inspection of objects located in

検査作業終了後上記の逆の手順を経て第2図の
状態に戻せば再び原子炉の出力運転を始めること
ができる。
After the inspection work is completed, the reactor can restart its output operation by reversing the above procedure to return to the state shown in Figure 2.

複数の開閉機構26a,26bは、例えば第4
図の如き平面配置にしておき1台の動作機構25
によつて確実に動作させることが可能である。な
お、第4図において符号30a,30bは、動作
機構25の先端部を挿入される連結部を示してい
る。
The plurality of opening/closing mechanisms 26a, 26b are, for example, a fourth opening/closing mechanism 26a, 26b.
One operating mechanism 25 is arranged in a plane as shown in the figure.
It is possible to operate reliably by In FIG. 4, reference numerals 30a and 30b indicate connecting portions into which the distal end portion of the operating mechanism 25 is inserted.

(本発明の効果) 以上説明したように、本発明に係る原子炉炉内
検査装置は次の如き効果を奏する。
(Effects of the present invention) As explained above, the nuclear reactor internal inspection apparatus according to the present invention has the following effects.

ナトリウム冷却型高速増殖炉で使用されてい
るアンダザプラグ概念のまま、炉心支持構造物
や原子炉容器等の冷却材高圧プレナムを形成す
る機器の表面検査を、完全に遠隔操作のままで
高被曝を伴なう作業なしに行うことができる。
Using the under-the-plug concept used in sodium-cooled fast breeder reactors, surface inspections of equipment that forms the high-pressure coolant plenum, such as core support structures and reactor vessels, can be performed completely remotely and with high radiation exposure. It can be done without any additional work.

高圧プレナム領域に連通孔を設けているにも
かかわらず高圧の冷却材の漏洩を確実に防止で
き、検査したい時には炉上部より比較的容易に
高圧低圧プレナム仕切り部材に機器貫通孔を開
けることができるため、原子炉の性能、機能を
何ら損なうことなく高圧プレナム形成機器の表
面検査ができる。
Despite having communication holes in the high-pressure plenum area, leakage of high-pressure coolant can be reliably prevented, and when inspection is desired, equipment through-holes can be drilled into the high-pressure and low-pressure plenum partition members relatively easily from the top of the furnace. Therefore, surface inspection of high-pressure plenum forming equipment can be performed without any loss in reactor performance or functionality.

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

第1図は本発明に係る原子炉炉内の検査装置の
一実施例を設置した原子炉を一部側面で示す概略
断面図、第2図は第1図における原子炉の出力運
転時の状態を説明するための要部のみを示す部分
断面図、第3図は本発明の他の実施例を左半分の
み示す概略断面図、第4図は第2図の−方向
矢視図である。 1……炉容器、4……取付けフランジ、5……
大回転プラグ、6……小回転プラグ、13……検
査プラグ、17……延長管、18……仕切機構、
19……案内管、23……検出器、24……開閉
装置、25……動作機構、26……開閉機構、2
9……熱遮蔽体。
FIG. 1 is a schematic sectional view partially showing a side view of a nuclear reactor in which an embodiment of the inspection device for a nuclear reactor according to the present invention is installed, and FIG. 2 is a state of the reactor during power operation in FIG. 1. FIG. 3 is a schematic sectional view showing only the left half of another embodiment of the present invention, and FIG. 4 is a view taken in the - direction arrow of FIG. 2. 1...Furnace vessel, 4...Mounting flange, 5...
Large rotation plug, 6... Small rotation plug, 13... Inspection plug, 17... Extension tube, 18... Partition mechanism,
19... Guide tube, 23... Detector, 24... Switching device, 25... Operating mechanism, 26... Opening/closing mechanism, 2
9...Heat shield.

Claims (1)

【特許請求の範囲】 1 炉容器の上部開口を閉塞する遮蔽プラグに挿
着された検査プラグと、該検査プラグに設けた複
数の貫通孔と、該貫通孔に挿入した延長管と、前
記貫通孔に挿入した動作機構と、前記検査プラグ
の上部に設けられ前記延長管に連結した駆動機構
と、該駆動機構に隣接して前記動作機構に連結し
た開閉装置と、前記延長管に仕切り機構を介しか
つ端末部が前記炉容器内の下方に取着された取付
けフランジに開口して接続された案内管と、この
案内管内に挿入された上下動し得る炉内検出器
と、カバーガス領域に配置された前記仕切機構と
該仕切機構に接合され、且つ前記動作機構の下端
に接続自在に設けられた開閉機構とからなること
を特徴とする原子炉炉内の検査装置。 2 案内管は、外周面に熱遮蔽体を有してなるこ
とを特徴とする特許請求の範囲第1項記載の原子
炉炉内の検査装置。
[Claims] 1. An inspection plug inserted into a shielding plug that closes the upper opening of the furnace vessel, a plurality of through holes provided in the inspection plug, an extension tube inserted into the through holes, and the through holes. an operating mechanism inserted into the hole; a drive mechanism provided at the top of the test plug and connected to the extension tube; an opening/closing device adjacent to the drive mechanism and connected to the operation mechanism; and a partition mechanism attached to the extension tube. a guide tube whose end portion is open and connected to a mounting flange mounted below in the furnace vessel; an in-furnace detector inserted into the guide tube and movable up and down; An inspection device for a nuclear reactor, comprising: the partition mechanism arranged therein; and an opening/closing mechanism connected to the partition mechanism and connectably provided to a lower end of the operating mechanism. 2. The inspection device for a nuclear reactor according to claim 1, wherein the guide tube has a heat shield on its outer peripheral surface.
JP56206197A 1981-12-22 1981-12-22 Inspection device for inside of reactor Granted JPS58108491A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP56206197A JPS58108491A (en) 1981-12-22 1981-12-22 Inspection device for inside of reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP56206197A JPS58108491A (en) 1981-12-22 1981-12-22 Inspection device for inside of reactor

Publications (2)

Publication Number Publication Date
JPS58108491A JPS58108491A (en) 1983-06-28
JPH0237557B2 true JPH0237557B2 (en) 1990-08-24

Family

ID=16519397

Family Applications (1)

Application Number Title Priority Date Filing Date
JP56206197A Granted JPS58108491A (en) 1981-12-22 1981-12-22 Inspection device for inside of reactor

Country Status (1)

Country Link
JP (1) JPS58108491A (en)

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5071700U (en) * 1973-11-01 1975-06-24

Also Published As

Publication number Publication date
JPS58108491A (en) 1983-06-28

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