JPS62233794A - Inspection device in pressure vessel for nuclear reactor - Google Patents
Inspection device in pressure vessel for nuclear reactorInfo
- Publication number
- JPS62233794A JPS62233794A JP61076588A JP7658886A JPS62233794A JP S62233794 A JPS62233794 A JP S62233794A JP 61076588 A JP61076588 A JP 61076588A JP 7658886 A JP7658886 A JP 7658886A JP S62233794 A JPS62233794 A JP S62233794A
- Authority
- JP
- Japan
- Prior art keywords
- pressure vessel
- inspection
- inspection device
- base station
- jet pump
- 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.)
- Granted
Links
- 238000007689 inspection Methods 0.000 title claims description 29
- 238000003780 insertion Methods 0.000 claims description 27
- 230000037431 insertion Effects 0.000 claims description 27
- 238000013459 approach Methods 0.000 claims description 9
- 230000003287 optical effect Effects 0.000 claims description 9
- 238000011179 visual inspection Methods 0.000 claims description 6
- 239000000446 fuel Substances 0.000 description 5
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 5
- 239000007921 spray Substances 0.000 description 4
- 238000010586 diagram Methods 0.000 description 3
- 238000000034 method Methods 0.000 description 3
- 241000270708 Testudinidae Species 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000012544 monitoring process Methods 0.000 description 1
- 230000008520 organization Effects 0.000 description 1
- 238000012360 testing method Methods 0.000 description 1
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)
- Manipulator (AREA)
Abstract
(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
〔発明の利用分野〕
本発明は、原子炉圧力容器内点検装置に係シ、沸騰水型
原子炉の原子炉圧力容器内部で特に、ジ適な原子炉圧力
容器内点検装置に関するものである。DETAILED DESCRIPTION OF THE INVENTION [Field of Application of the Invention] The present invention relates to a reactor pressure vessel internal inspection device, and particularly relates to a reactor pressure vessel internal inspection device of a boiling water reactor. This relates to inspection equipment.
従来の原子炉圧力容器内点検装置を第1図〜第3図によ
り説明する。駆動装置5に取シ付けられたテレビカメ2
6は、通常、燃料交換用に使用される燃料取替機2の燃
料つかみ装置先端のグラツプル4で吊シ下げられている
。このテレビカメラ6の横方向及び上下方向の位置制御
は、燃料取替機2の制御装置で行われ、テレビカメラ6
の姿勢及び映像の制御は、原子炉圧力容器内点検装置用
制御装置3によ)行い、これによって原子炉圧力容器l
内の肉眼検査は実施される。第1図のA部詳細図を第2
図に示す。テレビカメラ6は、直視。A conventional nuclear reactor pressure vessel internal inspection device will be explained with reference to FIGS. 1 to 3. TV camera 2 attached to drive device 5
6 is normally suspended from a grapple 4 at the tip of a fuel gripping device of a fuel exchange machine 2 used for fuel exchange. The horizontal and vertical position control of the television camera 6 is performed by the control device of the fuel exchange machine 2.
The attitude and image of the reactor pressure vessel are controlled by the reactor pressure vessel internal inspection device control device 3).
A visual inspection of the area will be performed. The detailed view of part A in Figure 1 is shown in Figure 2.
As shown in the figure. The TV camera 6 looks directly.
−伐が可能な構造とlよっておシ、エルボ機構7により
垂直状態から水平状態まで撮影方向を変えることができ
、さらに、0〜3606回転も可能な構造である。しか
し、その形状1機構の丸め、第3図に示す様なシュラウ
ド7ランジ15より下に位4&するジェットポンプ8近
俺の3會あい部に太−置を挿入する事は困難であシ、し
たがって満足出来る検査が出来なかった。- It has a structure that allows it to be rotated, and the photographing direction can be changed from a vertical position to a horizontal position using the elbow mechanism 7, and it is also capable of rotating from 0 to 3606 degrees. However, due to the rounded shape of the mechanism, it is difficult to insert a thick position into the 3 meeting area between the jet pump 8 and the jet pump 8, which is positioned below the shroud 7 flange 15 as shown in Figure 3. Therefore, a satisfactory test could not be performed.
本発明の目的は、シュラウドフランジより下に位置する
ジェットポンプ近傍の点検が可能な原子炉圧力容器内点
検装置を提供することにある。SUMMARY OF THE INVENTION An object of the present invention is to provide a reactor pressure vessel interior inspection device that can inspect the vicinity of a jet pump located below a shroud flange.
本発明の特徴は、圧力容器の外部に設置されオペレータ
が直接操作を行う炉外システムと、圧力容器の内部に設
置されオペレータが遠隔的に操作する炉内システムを有
し、前記炉内システムは、点検装置の動作基準となるベ
ース・ステーショント、このベース・ステーションから
ジェットポンプ近傍ヘアプローチするための挿入機構と
、この挿入機構にR諭されてアプローチ地点での基準と
なるターミナル・ステーションと、目視点検用光学ヘッ
ドをライザ・ブレースの点検箇所に誘導位置決めさせる
廻り込みm構か亀とを備えている点にめる。The present invention is characterized by having an extra-furnace system installed outside the pressure vessel and directly operated by an operator, and an in-furnace system installed inside the pressure vessel and operated remotely by an operator, wherein the in-furnace system is , a base station that serves as an operating reference for the inspection device, an insertion mechanism for approaching the vicinity of the jet pump from this base station, and a terminal station that is guided by this insertion mechanism and serves as a reference at the approach point; The optical head for visual inspection is equipped with a rotating mechanism or tortoise for guiding and positioning the optical head to the inspection point of the riser brace.
本発明は、従来シュラウド7ランジ15よシ下に位置す
るジェットポンプ8近傍の点検が、その形状9機構によ
り困難であったことに着目し、原子炉圧力容器1内に挿
入する炉内点検装置を、ジェットポンプ8近傍に挿入可
能な構造とした。すなわち本発明は、点検装置の動作基
準となるベース・ステーショント、このベース・ステー
ションからジェットポンプ8近傍ヘアプローチするため
の挿入機構と、この挿入機構に懸垂されてアプローチ地
点での基準となるターミナル・ステーションと、目視点
検用光学ヘッドをライザ・ブレースの点検箇所に誘導位
置決めさせる廻り込み機構20とにより構成される。挿
入手順としては最初に、各機構を内蔵・搭載したベース
・ステーションを挿入、設置し、次に各機構を段階的に
挿入。The present invention focuses on the fact that conventionally it was difficult to inspect the vicinity of the jet pump 8 located below the shroud 7 flange 15 due to its shape 9 mechanism, and developed an in-reactor inspection device inserted into the reactor pressure vessel 1. The structure is such that it can be inserted near the jet pump 8. That is, the present invention provides a base station that serves as an operating reference for the inspection device, an insertion mechanism for approaching the vicinity of the jet pump 8 from this base station, and a terminal that is suspended from this insertion mechanism and serves as a reference at the approach point. - Consists of a station and a turning mechanism 20 that guides and positions the visual inspection optical head to the inspection location of the riser brace. The insertion procedure involves first inserting and installing the base station with each mechanism built-in and installed, and then inserting each mechanism in stages.
固定し、前記のように3段階の接近手順で、炉外のオペ
レータが制御装置及びテレビカメラで位置確認をしなが
ら段階的に原子炉圧力容器内部の構造物等や狭あい部の
機器の点検を行う。The operator outside the reactor confirms the position using the control device and television camera, and inspects the structures inside the reactor pressure vessel and the equipment in the narrow spaces in stages using the three-step approach procedure described above. I do.
以下、本発明の具体的な一実施例を第3図〜第10図に
より説明する。A specific embodiment of the present invention will be described below with reference to FIGS. 3 to 10.
第3図は、従来までの原子炉圧力容器内点検装置では、
点検が困難であったジェットポンプ8近傍の概略図であ
る。Figure 3 shows that in the conventional reactor pressure vessel internal inspection equipment,
FIG. 2 is a schematic diagram of the vicinity of the jet pump 8, which was difficult to inspect.
ジェットポンプ8を圧力容器lに対して支持するライザ
・ブレース10と圧力容器1との溶接部11周辺の点検
が必要である。しかし、7ユラウドフラ/ジ(上リング
)15の上方に給水スパージャ12.炉心スプレィ配管
13が位置しているため、両者を避は点検箇所であるラ
イザ・ブレース溶接部11の周辺に点検装置を挿入でき
る構造とする必要がある。これに対応できる装置を第4
図から説明する。It is necessary to inspect the area around the welded part 11 between the riser brace 10 that supports the jet pump 8 with respect to the pressure vessel 1 and the pressure vessel 1. However, there is a water supply sparger 12 above the upper ring 15. Since the core spray piping 13 is located, it is necessary to avoid both of them, and to have a structure that allows the inspection device to be inserted around the riser brace welded portion 11, which is the inspection point. A fourth device that can handle this
Let's explain from the diagram.
第4図に本発明による原子炉圧力容器内点検装置の全体
図を示す。原子炉圧力容器内点検装置のシステムは、圧
力容器1の外部に設置されオペレータが直接操作を行う
炉外システムと、圧力容器1の内部に設置芒れ、オペレ
ータが遠隔的に操作する炉内システムから構成される。FIG. 4 shows an overall view of the reactor pressure vessel internal inspection device according to the present invention. The reactor pressure vessel internal inspection equipment system consists of an external system installed outside the pressure vessel 1 and operated directly by the operator, and an in-core system installed inside the pressure vessel 1 and operated remotely by the operator. It consists of
又、炉内システムは、点検装置の動作基準となるベース
・ステジョン17からジェットポンプ8近傍ヘアプロー
チするだめの挿入機構1B、挿入機構18に懸垂してア
プローチ地点での基準となるターミナル・ステー7ヨン
19、及び目視点検用光学ヘッド21をライザ・プレー
ス10の点検箇所に誘導位置決めする4D込み機構20
により構成される。The in-core system also includes an insertion mechanism 1B that approaches the vicinity of the jet pump 8 from a base station 17 that serves as an operating reference for the inspection device, and a terminal stay 7 that is suspended from the insertion mechanism 18 and serves as a reference at the approach point. 4D-included mechanism 20 that guides and positions the Yon 19 and the optical head 21 for visual inspection to the inspection location of the riser place 10.
Consisted of.
以下詳細に説明する。装置の動作(接近)手順は、大き
く3段階に分かれる。すなわち第1ステツプで、廻り込
み機構20.ターミナル・ステーション19等を搭載し
であるベース・ステーション17を建屋クレーン16等
で吊り上げ、圧力容器l内部に入れ、給水スパージャ1
2.炉心スプレィ配管13を避けなから7ユラウド・ヘ
ッドのすぐ上まで降下させる。次に、その高さのまま圧
力容器lの内壁に接近させ該内壁に沿ってさらに降下さ
せ、圧力容器lの径方向には内壁を基準とし、周方向に
はベース・ステーション17上に下向きに設置された監
視カメラ22(第5図参照)を用いて、ジェットポンプ
8の180°ベンドを基準としなから7ユラウドフラン
ジ(上リング)15上に白瓜によシ前記炉内システムを
設置する。その後、第5図に示すように、シュラウドヘ
ッドのラグ9を基準にして、ベース・ステーション17
に設置された位置決め機構24により周方向及び径方向
に位置決めを行う。第5図は、ベース・ステーション1
7の構造図を示すと共に、ベース・ステーション17が
、シュラウドフランジ(上リング)15に設置されてい
る状態を示している。This will be explained in detail below. The operation (approach) procedure of the device is roughly divided into three stages. That is, in the first step, the rotation mechanism 20. The base station 17, which is equipped with the terminal station 19, etc., is lifted up by the building crane 16, etc., and placed inside the pressure vessel l, and the water supply sparger 1 is placed inside the pressure vessel l.
2. Avoiding the core spray piping 13, it is lowered to just above the 7-Roud head. Next, it is brought close to the inner wall of the pressure vessel 1 at that height and further lowered along the inner wall, with the inner wall being the reference in the radial direction of the pressure vessel 1, and downward onto the base station 17 in the circumferential direction. Using the installed surveillance camera 22 (see Fig. 5), install the above-mentioned furnace system on the 7-round flange (upper ring) 15 using the 180° bend of the jet pump 8 as a reference. . Thereafter, as shown in FIG.
Positioning is performed in the circumferential direction and the radial direction by a positioning mechanism 24 installed at. Figure 5 shows base station 1
7 is shown, and the base station 17 is shown installed on the shroud flange (upper ring) 15.
次に、第2ステツプでは、ベース・ステーション17を
基地として、先端にターミナル・ステーション19やm
b込み機構20を懸垂している挿入機構1Bを動作させ
、圧力容器1とシュラウド14の狭い隙間を通してライ
ザ・ブレースlOの近傍まで降下させる。光学ヘッド2
1をライザ・ブレース10の点検位置に対して所定の点
検距離に設定するために、オペレータが光学ヘッド21
を通してモニタリングしながら挿入方向位置合せを行う
。次に、第6b図に示す様にターミナル・ステーション
19のクランプ機構26を作動させ、ターミナル・ステ
ーション19t″圧力容器1とシュラウド140間の空
間に固定する。Next, in the second step, the base station 17 is used as a base, and the terminal station 19 and m
The insertion mechanism 1B suspending the insertion mechanism 20 is operated to lower it through the narrow gap between the pressure vessel 1 and the shroud 14 to the vicinity of the riser brace IO. optical head 2
1 at a predetermined inspection distance with respect to the inspection position of the riser brace 10, the operator moves the optical head 21
Align the insertion direction while monitoring the Next, as shown in FIG. 6b, the clamping mechanism 26 of the terminal station 19 is actuated to fix the terminal station 19t'' in the space between the pressure vessel 1 and the shroud 140.
第6a図は、挿入機構18の収納状態を、第6b図は挿
入機構18の挿入状態をそれぞれ示している。FIG. 6a shows the insertion mechanism 18 in a stored state, and FIG. 6b shows the insertion mechanism 18 in an inserted state.
第3ステツプでは、ターミナル・ステーション19を基
点として、所定のシーケンスに基づく廻り込み機構20
の自動動作によって、先端に装着された光学ヘッド21
をライザ・ブレース10の点検位置に誘導し、この点検
映像を炉外のテレビモニタを通してオペレータが点検す
る。In the third step, starting from the terminal station 19, the turning mechanism 20 is moved in accordance with a predetermined sequence.
The optical head 21 attached to the tip is automatically operated.
is guided to the inspection position of the riser brace 10, and the operator inspects this inspection image through a television monitor outside the furnace.
このように1本発明による原子炉圧力容器内点検装置は
、3段階で接近する分散機能臘構成をもつところに特徴
がある。As described above, the reactor pressure vessel internal inspection device according to the present invention is characterized by having a distributed function structure that approaches in three stages.
次に、主要/?!r機構について詳細に説明する。Next, major/? ! The r mechanism will be explained in detail.
第5図は、ベース・ステーション17の構造図でめるが
、このうち各機構を搭載し九状態で7エラウドフランジ
15部のラグ9に対して位置決めをする位置決め機構2
4について説明する。これは、位置決めプーム25tネ
ジ送#)駆動によシ旋回させ、ラグ9t−両脇から挾み
込むようにしたものである。これVこよυベース・ステ
ーション17の圧力容器1に対する径方向及び周方向の
位置すれか、ラグ9を基準として修正される。FIG. 5 shows a structural diagram of the base station 17, of which the positioning mechanism 2 is mounted with each mechanism and is positioned with respect to the lug 9 of the 7-eraud flange 15 in the 9 state.
4 will be explained. This is configured so that the positioning poom 25t is rotated by a screw drive and the lug 9t is inserted from both sides. The position of the base station 17 in the radial and circumferential directions with respect to the pressure vessel 1 is corrected using the lug 9 as a reference.
vJ6a、6b図は、それぞれ挿入機構18の収納、押
入状態を示す。挿入機構18は、第1挿入機構18aと
第2挿入機構18bに大別される。Figures vJ6a and 6b show the insertion mechanism 18 in the retracted and pushed-in states, respectively. The insertion mechanism 18 is roughly divided into a first insertion mechanism 18a and a second insertion mechanism 18b.
第1挿入機構188は、炉心スプレィ配管13及び給水
スパージャ12を回避しながら、廻り込み機構20とタ
ーミナル・ステーション19を懸垂する第2挿入機構1
sbを最初、斜めに挿入しく第6a図参照)、挿入スト
ローク終端で垂直に設置片するもので必る(JGb図参
照)。第2挿入機構18bは、廻り込み機構20及びタ
ーミナル・ステー7ヨン19を、ジェットボン7’ 8
近傍へ挿入するものである(第6b図参照)。The first insertion mechanism 188 suspends the wrap-around mechanism 20 and the terminal station 19 while avoiding the core spray piping 13 and the water supply sparger 12.
It is necessary to insert the sb diagonally at first (see Figure 6a) and then install it vertically at the end of the insertion stroke (see Figure JGb). The second insertion mechanism 18b inserts the rotation mechanism 20 and the terminal stay 19 into the jet bong 7' 8
It is inserted into the vicinity (see Figure 6b).
第7図、第8図は、ラッチ機構の構造を示す。7 and 8 show the structure of the latch mechanism.
ラッチ機構は、挿入機構18の動作によりターミナル・
ステーション19が掘れ、圧力容WBIの炉壁に当るこ
とを防ぐためにターミナル・ステージある。本機構は、
トグル・ジヨイント機構を用い、ベース・ステーション
17本体に付設した直動カム27によシ、挿入機構18
の挿入時及び引上時に自動的に係合、解放される構造で
ある。このラッチ機構によυ、ターミナル・ステーショ
ン19を挿入機構18によシ安全に点検位置近傍まで降
下挿入することが可能になる。The latch mechanism is activated by the operation of the insertion mechanism 18.
Station 19 is excavated and there is a terminal stage to prevent it from hitting the furnace wall of the pressure vessel WBI. This organization is
Using a toggle joint mechanism, the insertion mechanism 18 is operated by a direct drive cam 27 attached to the main body of the base station 17.
It has a structure that automatically engages and releases when it is inserted and pulled out. This latch mechanism allows the terminal station 19 to be safely lowered and inserted into the insertion mechanism 18 close to the inspection position.
第9図は、クランプ機構31の構造を示す。クランプ機
構:11は、ターミナル・ステーション19本体を圧力
容器lと7ユラウド14の間に固定するためのものであ
る。このクランプ機構31は、折シ畳まれていたクラン
プアームを水平に引き上げるクランプ開閉機構26と、
クランプアームの先端それぞれ外側部分と内@部分をわ
ずかに伸長させターミナル・ステーション19の(JJ
向の概略位置決めを行う内プレフラング機構29と、外
プレクランプ機構2B、さらにはターミナル・ステーシ
ョン19を圧力容器lとシュラウド14の間に突張シ固
定するメイン・クランプ機構30s、z m rJF
−Y +>イ直^1第10図は、廻り込み機構20の各
駆動軸の構成を示す。本機慣は、ジェットポンプ8を廻
り込みながらアプローチできる折Cff1み式4リンク
(33〜:(6)と関節(39・〜41)とを有する機
構である。又、7ユラウド14側ジ工ツトポンプ8間隙
から圧力容器1側ジェットポンプ8間隙へ、あるいは反
対側に隣接するジェットポンプ8にアプローチするため
のリンク姿勢反転用補助回転軸32、廻り込み機構20
全体の位置を変えるための軸37、目視点検用光学ヘッ
ド21の回転。FIG. 9 shows the structure of the clamp mechanism 31. A clamp mechanism 11 is for fixing the main body of the terminal station 19 between the pressure vessel 1 and the 7-layer 14. This clamp mechanism 31 includes a clamp opening/closing mechanism 26 that horizontally pulls up the folded clamp arm;
Slightly extend the outer and inner parts of the clamp arm tips and attach them to terminal station 19 (JJ
The main clamp mechanism 30s, z m rJF, which tensions and fixes the inner pre-flang mechanism 29, the outer pre-clamp mechanism 2B, and the terminal station 19 between the pressure vessel l and the shroud 14.
-Y +>A straight ^1 FIG. 10 shows the configuration of each drive shaft of the rotation mechanism 20. This machine is a mechanism that has a folding Cff1 type 4 link (33~: (6)) and joints (39~41) that can be approached while going around the jet pump 8. An auxiliary rotating shaft 32 for reversing the link posture to approach the jet pump 8 gap on the pressure vessel 1 side from the jet pump 8 gap or the adjacent jet pump 8 on the opposite side, and a rotation mechanism 20
Rotation of the axis 37 and optical head 21 for visual inspection to change the overall position.
首振り軸42.43も備えている。It is also equipped with swing axes 42 and 43.
本発明によれば、原子炉圧力容器内部構造物等、特にジ
ェットポンプ周辺等の狭あい部の点検及び欠陥横歪を効
率よく行うことができる。According to the present invention, it is possible to efficiently inspect narrow spaces such as the internal structure of a reactor pressure vessel, particularly around a jet pump, and detect transverse strain defects.
iA1図は従来の原子炉圧力容器内点検装置を示す全体
図、第2図は第1図のA部詳細図、第3図はジェットポ
ンプ近傍の概略図、6!S4図は本発明による原子炉圧
力容器内点検装置の全体図、第5図ハベース・ステーシ
ョンの正面図、第6a図は挿入機構の収納状態を示す正
面図、第6b図は挿入機構の挿入状態を示す正面図、第
7図、第8図はラッチ機構の構造を示す正面図、第9図
はクランプ機構の構造を示す正面図、第10図は廻り込
み機構の各駆動軸の構成を示す斜視図である。
l・・・原子炉圧力容器、2・・・燃料取替機、12・
・・給水スパージャ、13・・・炉心スプレィ配[,1
4・・・7ユラウド、16・・・建fflりL/−7%
17・・・ヘース・ステーション、18・・・挿入
機構、19・・・ターミナル・ステーション、25・・
・位置決メアーム、26・・・クランプ開閉機構、27
・・・自動カム、28・・・外プレクランプ機構、29
・・・内プレクランプ機構、30・・・メイン・クラン
プ機構、31・・・クランプ機構。
(〕
竿4図Figure iA1 is an overall view of a conventional reactor pressure vessel internal inspection system, Figure 2 is a detailed view of section A in Figure 1, Figure 3 is a schematic view of the vicinity of the jet pump, and 6! Figure S4 is an overall view of the reactor pressure vessel internal inspection device according to the present invention, Figure 5 is a front view of the Habase station, Figure 6a is a front view showing the insertion mechanism in the retracted state, and Figure 6b is the inserted state of the insertion mechanism. Figures 7 and 8 are front views showing the structure of the latch mechanism, Figure 9 is a front view showing the structure of the clamp mechanism, and Figure 10 shows the configuration of each drive shaft of the rotation mechanism. FIG. l... Reactor pressure vessel, 2... Fuel exchange machine, 12.
... Water supply sparger, 13 ... Core spray distribution [,1
4... 7 euros, 16... construction fflli L/-7%
17... Heath station, 18... Insertion mechanism, 19... Terminal station, 25...
・Positioning arm, 26... Clamp opening/closing mechanism, 27
...Automatic cam, 28...Outer pre-clamp mechanism, 29
...Inner pre-clamp mechanism, 30... Main clamp mechanism, 31... Clamp mechanism. () Rod figure 4
Claims (1)
を行う炉外システムと、圧力容器の内部に設置されオペ
レータが遠隔的に操作する炉内システムとを有し、前記
炉内システムは、点検装置の動作基準となるベース・ス
テーションと、このベース・ステーションからジェット
ポンプ近傍へアプローチするための挿入機構と、この挿
入機構に懸垂されてアプローチ地点での基準となるター
ミナル・ステーションと、目視点検用光学ヘッドをライ
ザ・ブレースの点検箇所に誘導位置決めさせる廻り込み
機構とを備えていることを特徴とする原子炉圧力容器内
点検装置。1. It has an extra-furnace system that is installed outside the pressure vessel and is directly operated by an operator, and an in-furnace system that is installed inside the pressure vessel and is remotely operated by an operator, and the in-furnace system is inspected. A base station that serves as a reference for the operation of the device, an insertion mechanism for approaching the vicinity of the jet pump from this base station, a terminal station that is suspended from this insertion mechanism and serves as a reference at the approach point, and a terminal station for visual inspection. A nuclear reactor pressure vessel interior inspection device comprising: a rotation mechanism for guiding and positioning an optical head to an inspection location on a riser brace.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP61076588A JPS62233794A (en) | 1986-04-04 | 1986-04-04 | Inspection device in pressure vessel for nuclear reactor |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP61076588A JPS62233794A (en) | 1986-04-04 | 1986-04-04 | Inspection device in pressure vessel for nuclear reactor |
Publications (2)
Publication Number | Publication Date |
---|---|
JPS62233794A true JPS62233794A (en) | 1987-10-14 |
JPH0366638B2 JPH0366638B2 (en) | 1991-10-18 |
Family
ID=13609455
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP61076588A Granted JPS62233794A (en) | 1986-04-04 | 1986-04-04 | Inspection device in pressure vessel for nuclear reactor |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS62233794A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2017504496A (en) * | 2014-01-30 | 2017-02-09 | ヴェリシュミラー エンジニアリング ゲーエムベーハー | Device having a manipulator unit |
Citations (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS5983093A (en) * | 1982-11-04 | 1984-05-14 | 東京電力株式会社 | Device for monitoring inside of nuclear pressure vessel |
-
1986
- 1986-04-04 JP JP61076588A patent/JPS62233794A/en active Granted
Patent Citations (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS5983093A (en) * | 1982-11-04 | 1984-05-14 | 東京電力株式会社 | Device for monitoring inside of nuclear pressure vessel |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2017504496A (en) * | 2014-01-30 | 2017-02-09 | ヴェリシュミラー エンジニアリング ゲーエムベーハー | Device having a manipulator unit |
Also Published As
Publication number | Publication date |
---|---|
JPH0366638B2 (en) | 1991-10-18 |
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