JPS62116296A - Monitor test piece detachable device for pressure vessel of nuclear reactor - Google Patents

Monitor test piece detachable device for pressure vessel of nuclear reactor

Info

Publication number
JPS62116296A
JPS62116296A JP60257336A JP25733685A JPS62116296A JP S62116296 A JPS62116296 A JP S62116296A JP 60257336 A JP60257336 A JP 60257336A JP 25733685 A JP25733685 A JP 25733685A JP S62116296 A JPS62116296 A JP S62116296A
Authority
JP
Japan
Prior art keywords
pressure vessel
test piece
monitoring test
reactor pressure
monitoring
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
JP60257336A
Other languages
Japanese (ja)
Inventor
周作 上田
重弘 勝矢
守男 伊藤
賢治 岡田
正義 枦川
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.)
Mitsubishi Power Ltd
Original Assignee
Babcock Hitachi KK
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 Babcock Hitachi KK filed Critical Babcock Hitachi KK
Priority to JP60257336A priority Critical patent/JPS62116296A/en
Publication of JPS62116296A publication Critical patent/JPS62116296A/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)

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の監視試験片着脱装置に係り、
特に監視試験片の取付けおよび取外しを簡便化するのに
好適な原子炉圧力容器の監視試験片着脱装置に関する。
[Detailed Description of the Invention] [Field of Application of the Invention] The present invention relates to a monitoring test piece attachment/detachment device for a nuclear reactor pressure vessel.
In particular, the present invention relates to a monitoring test piece attaching/detaching device for a nuclear reactor pressure vessel suitable for simplifying the attachment and detachment of a monitoring test piece.

〔発明の背景〕[Background of the invention]

発電用軽水型原子炉圧力容器には、中性子照射による原
子炉圧力容器材料の機械的性質の変化を定期的に調査し
、評価するためのデータ採取を目的として、原子炉圧力
容器の炉心領域にある部材と同一の材料を監視試験片と
して設置することが規格に規定されている。
In light water reactor pressure vessels for power generation, the core area of the reactor pressure vessel is used for the purpose of collecting data to periodically investigate and evaluate changes in the mechanical properties of the reactor pressure vessel material due to neutron irradiation. The standard stipulates that the same material as a certain member be installed as a monitoring test piece.

所定の位置に設置された監視試験片は、あらかじめ定め
られたプログラムに基づき、一定期間経過後炉内より取
り出され、原子炉運転前の中性子照射を受けていない機
械的性質データと比較することにより、原子炉圧力容器
炉心領域材料の機械的性質の劣化の有無およびその程度
を評価している。
The monitoring test piece installed at a predetermined location is taken out from inside the reactor after a certain period of time according to a predetermined program, and is compared with mechanical property data that has not been irradiated with neutrons before reactor operation. , the existence and extent of deterioration of mechanical properties of reactor pressure vessel core area materials are being evaluated.

監視試験片は、引張試験片とシャルピー衝撃試験片とか
ら構成されている。これらの試験片は炉心領域材料の中
性子照射による機械的性質の変化をモニターするための
監視試験片と、原子炉寿命末期までの予測中性子照射量
を短時間に加速して与えるための加速試験片に分けられ
る。これらの試験片は、いずれもバスケットに収納され
て所定の位置に設置される。第9図に示すように原子炉
圧力容器1内にはドライヤ2、セパレータ3、ジェット
ポンプ5等が配置され、加速照射用監視試駒片バスケッ
ト15Aは、上部格子板16に固定され、炉壁用監視試
験片ハスケソ)15Bは炉心近傍の原子炉圧力容器内壁
付近に設置される。
The monitoring test piece consisted of a tensile test piece and a Charpy impact test piece. These test pieces are monitoring test pieces for monitoring changes in mechanical properties of core region materials due to neutron irradiation, and accelerated test pieces for accelerating the predicted neutron irradiation dose over a short period of time until the end of the reactor life. It can be divided into All of these test pieces are housed in a basket and placed in a predetermined position. As shown in FIG. 9, a dryer 2, a separator 3, a jet pump 5, etc. are arranged inside the reactor pressure vessel 1, and a monitoring sample piece basket 15A for accelerated irradiation is fixed to an upper grid plate 16, and a reactor wall The monitoring test piece 15B is installed near the inner wall of the reactor pressure vessel near the reactor core.

これらの試験片の設置状態を第10図〜第14図を基に
説明する。加速照射用監視試験片バスケア)15Aは、
第10図に示すように原子炉圧力容器内に1個所設置さ
れ、炉壁用監視試験片バスケソ)15Bは原子炉圧力容
器内壁イ」近に各々炉中心部から90°の角度で等間隔
に配置される。
The installation state of these test pieces will be explained based on FIGS. 10 to 14. Monitoring test piece for accelerated irradiation (bath care) 15A is
As shown in Figure 10, monitoring test pieces 15B are installed at one place inside the reactor pressure vessel, and are placed at equal intervals at an angle of 90° from the center of the reactor near the inner wall of the reactor pressure vessel. Placed.

加速照射用監視試験片バスケソ1〜15Aは第11図お
よび第12図に示すように上部格子板16にアルミ箔2
3を介してスポット溶接(23)され、一方、炉壁用監
視試験片バスケソl−15Bは第13図および第14図
に示すようにボルダ17により吊設されるブラケット1
8にバネ19により挾み込むという固定方法が採用され
ている。監視試験片は、あらかじめ定められたプログラ
ムに基づき、原子カプラントの運転期間を考慮して、原
子炉運転停止中に、原子炉圧力容器内部の所定の位置よ
り取出し作業を行う必要がある。しかし、従来の取付は
機構では、監視試験片取付は位置が炉内の高放射線環境
中であるため、監視試験片取付は位置への人の接近は極
めて困難である。このため、第15図に示すように原子
炉ウェル21付近の原子炉圧力容器のフランジ開口部上
方より、先端にフックの付いた長尺のボール20を操作
することにより、監視試験片バスケットの取出し作業を
行っている。
As shown in FIGS. 11 and 12, the accelerated irradiation monitoring test pieces Basqueso 1 to 15A have aluminum foil 2 on the upper grid plate 16.
On the other hand, the furnace wall monitoring test piece Baskeso 1-15B is spot welded (23) through the bracket 1, which is suspended by the boulder 17, as shown in FIGS. 13 and 14.
A fixing method is adopted in which the holder 8 is clamped by a spring 19. The monitoring test piece must be removed from a predetermined position inside the reactor pressure vessel during reactor shutdown, based on a predetermined program and taking into account the operating period of the nuclear couplant. However, with conventional mounting mechanisms, the monitoring test piece is installed in a high radiation environment inside the reactor, making it extremely difficult for people to access the monitoring test piece installation location. Therefore, as shown in FIG. 15, the monitoring specimen basket can be taken out by operating a long ball 20 with a hook at the tip from above the flange opening of the reactor pressure vessel near the reactor well 21. work is being done.

この監視試験片取出し作業は、炉内からの放射線を遮蔽
するため、原子炉圧力容器の内部に炉水を有する状態で
行っている。しかし作業者と監視試験片取付は位置との
間は約12〜22mと非常に離れていること、および水
中作業であるため視界が悪く、水中照明および水中テレ
ビを用いて監視試験片の位置確認をしながら作業を行っ
ており、作業性が極めて悪い。このため、監視試験片取
外し作業時には、事前に原子炉圧力容器内部の構造物を
模擬したモックアツプを用いて、作業員の訓練を行って
いる。しかし、このような訓練を行っても、万一取外し
に失敗し、監視試験片バスケットを取落してしまった場
合、炉内であるため回収は極めて困難であり、原子カプ
ラントの運転に重大な影響を与えるだけでなく原子炉圧
力容器の内部に損傷を与える可能性があり、この作業は
放射線下で細心の注意が要求される。
This monitoring test piece removal work is carried out with reactor water inside the reactor pressure vessel in order to shield radiation from inside the reactor. However, the distance between the operator and the location where the monitoring test piece is installed is approximately 12 to 22 meters, and visibility is poor because the work is underwater, so underwater lighting and underwater television are used to confirm the location of the monitoring test piece. The work is done while doing the work, and the work efficiency is extremely poor. For this reason, when removing monitoring test pieces, workers are trained in advance using a mock-up that simulates the structure inside the reactor pressure vessel. However, even with such training, if the monitoring test piece basket were to fail in its removal and fall off, it would be extremely difficult to retrieve it since it is inside the reactor, and this could have a serious impact on the operation of the nuclear couplant. This work requires extreme care under radiation conditions, as it may not only cause damage to the reactor pressure vessel but also cause damage to the inside of the reactor pressure vessel.

また、従来の監視試験片バスケット取付は機構では、監
視試験片の取外しを行った後、データの再現性確認、あ
るいは原子炉圧力容器の寿命延長検討等のため、新監視
試験片の追加の必要が生じた場合でも、人の接近ができ
ないため、監視試験片の再取付けは極めて困難である。
In addition, when conventional monitoring test piece baskets are installed, after removing the monitoring test pieces, it is necessary to add new monitoring test pieces to confirm data reproducibility or to consider extending the life of the reactor pressure vessel. Even if this occurs, it is extremely difficult to reinstall the monitoring test piece because humans cannot access it.

さらに、従来の監視試験片バスケットの取付は機構では
監視試験片バスケットは、所定の位置に個別に取付けら
れているため異なる中性子照射量のデータを採取し、中
性子照射量に対する材料の機械的性質の変化量の傾向を
調査するためには、複数の監視試験片バスケットを個別
に取出す必要がある。
Furthermore, since conventional monitoring test specimen baskets are mounted individually at predetermined positions, data on different neutron irradiation doses can be collected, and the mechanical properties of the material can be determined in response to neutron irradiation doses. In order to investigate trends in the amount of change, it is necessary to individually remove multiple monitoring specimen baskets.

〔発明の目的〕[Purpose of the invention]

本発明の目的は、上記した従来技術の欠点をなくし、原
子炉圧力容器内部における監視試験片の取付け、取外し
を簡便に行うことができ、また中性子照射量の異なる位
置に配置される複数個の監視試験片バスケットを同時に
取付け、取外しできる原子炉圧力容器の監視試験片着脱
装置を提供することにある。
An object of the present invention is to eliminate the above-mentioned drawbacks of the prior art, to easily install and remove monitoring test pieces inside a reactor pressure vessel, and to easily install and remove monitoring test pieces inside a reactor pressure vessel. An object of the present invention is to provide a monitoring test piece attaching/detaching device for a nuclear reactor pressure vessel, which allows a monitoring test piece basket to be attached and removed at the same time.

〔発明の概要〕[Summary of the invention]

本発明は、原子炉圧力容器内部の上下方向に原子炉圧力
容器の内壁面付近に沿ってレールを敷設し、このレール
に監視状、験片を収納した単数又は複数個の監視試験片
バスケット移動自在に設け、監視試験片バスケットをレ
ールに沿って移動させることによって監視試験片バスケ
ットの取付け、取外しを容易なものとし、更に監視試験
片バスケットを炉心の長手方向に適切な間隔で連結する
ことによって、異なる中性子照射量の監視試験片を同時
に取り出すことができるようにしたものである。
The present invention involves laying rails in the vertical direction inside the reactor pressure vessel near the inner wall surface of the reactor pressure vessel, and moving one or more monitoring test piece baskets storing monitoring letters and test pieces on the rails. By moving the monitoring test piece basket freely along the rail, installation and removal of the monitoring test piece basket is made easy, and by connecting the monitoring test piece baskets at appropriate intervals in the longitudinal direction of the reactor core. , which allows monitoring test pieces with different neutron irradiation doses to be taken out at the same time.

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

以下、本発明の実施例を図面に基づいて説明する。第1
図は、沸騰水型原子炉圧力容器に適用したときの本発明
にかかる原子炉圧力容器の監視試験片着脱装置の取付は
機構の一実施例を示す断面図である。第1図において、
原子炉圧力容器1の内部にはドライヤ2、セパレータ3
、炉内配管4およびジェットポンプ5等が配置されてい
る。そして原子炉圧力容器1内の前記各機器と干渉しな
い位置に恒久レール6が配置されている。監視試験片バ
スケット7は、この恒久レール6をガイドとして移動可
能に設置され、この監視試験片バスケット7内に監視試
験片が収納されている。このようにして監視試験片はガ
イド−に沿って移動する監視試験片バスケット7によっ
て原子炉圧力容器1内の所定の位置に取付け、かつ取下
すことができるようになっている。監視試験片バスケッ
ト7の取付け、取外しの際は、原子炉圧力容器フランジ
8の開口部より行われるが、第1図は原子炉運転中にお
ける監視試験片が設置された原子炉圧力容器1内部の状
態を示している。第2図は、監視試験片バスケットを取
付&Jおよび取外ししたときの原子炉圧力容器内部を示
し、第1図におけるドライヤ2、セパレータ3等は取り
外された状態となっている。恒久レール6は、原子炉圧
力容器1内のドライヤ支持ブラケット9等の障害物を避
ければ、原子炉圧力容器1の周方向のほぼ任意の位置に
配置できる。
Embodiments of the present invention will be described below based on the drawings. 1st
The figure is a cross-sectional view showing an embodiment of a mechanism for attaching and detaching a monitoring test piece for a reactor pressure vessel according to the present invention when applied to a boiling water reactor pressure vessel. In Figure 1,
A dryer 2 and a separator 3 are installed inside the reactor pressure vessel 1.
, furnace piping 4, jet pump 5, etc. are arranged. A permanent rail 6 is placed in the reactor pressure vessel 1 at a position where it does not interfere with each of the above-mentioned devices. The monitoring test piece basket 7 is movably installed using the permanent rail 6 as a guide, and the monitoring test piece is stored in the monitoring test piece basket 7. In this manner, the monitoring test piece can be attached to and removed from a predetermined position within the reactor pressure vessel 1 by means of the monitoring test piece basket 7 that moves along the guide. The monitoring test piece basket 7 is installed and removed through the opening of the reactor pressure vessel flange 8. Figure 1 shows the interior of the reactor pressure vessel 1 with the monitoring test piece installed during reactor operation. It shows the condition. FIG. 2 shows the inside of the reactor pressure vessel when the monitoring test piece basket is installed and removed, with the dryer 2, separator 3, etc. in FIG. 1 removed. The permanent rail 6 can be placed at almost any position in the circumferential direction of the reactor pressure vessel 1 as long as obstacles such as the dryer support bracket 9 inside the reactor pressure vessel 1 are avoided.

本実施例では、原子炉圧力容器1の周方向の中性子照射
量の分布の均一性を確認するため、恒久レール6は原子
炉圧力容器の周方向に等間隔をおいて数個所設置されて
いる。また恒久レール6は、原子炉圧力容器1内に設置
された炉内配管4との干渉を避けるためにその一部に曲
率を与えた構造となっている。
In this embodiment, in order to confirm the uniformity of the distribution of the neutron irradiation amount in the circumferential direction of the reactor pressure vessel 1, permanent rails 6 are installed at several locations at equal intervals in the circumferential direction of the reactor pressure vessel. . Further, the permanent rail 6 has a structure in which a portion thereof is curved in order to avoid interference with the in-core piping 4 installed in the reactor pressure vessel 1.

第3図は、本発明における恒久レール6の原子炉圧力容
器1への取付は状態を示す側断面図、第4図は第3図の
正面図である。第3図および第4図において、原子炉圧
力容器1の内壁面に設置されたレール支持ブラケット1
1に補強用のレールサポート10が垂直方向に所定の間
隔をおいて設けられ、このレールサポート10の両端部
にそれる。
FIG. 3 is a side sectional view showing how the permanent rail 6 is attached to the reactor pressure vessel 1 according to the present invention, and FIG. 4 is a front view of FIG. 3. 3 and 4, the rail support bracket 1 installed on the inner wall surface of the reactor pressure vessel 1
1, reinforcing rail supports 10 are provided at predetermined intervals in the vertical direction, and extend at both ends of the rail supports 10.

第7図は、恒久レール6に対し、複数個の監視試験片バ
スケット7を適切を間隔をおいて連結したものである。
FIG. 7 shows a plurality of monitoring specimen baskets 7 connected to a permanent rail 6 at appropriate intervals.

原子炉圧力容器炉心領域において、中性子フラックスの
垂直方向の分布は、第7図中に示すように炉心中央部が
高く、それよりも上方および下方になると低くなる。し
たがって、中性子フラツクスの分布状況に応じて監視試
験片バスケット7を適切な間隔で連結すれば、各監視試
験片はそれぞれ同一試験期間で異なる中性子照射量を受
けることになり、このため連結された複数の中性子照射
量をデータ採取を行うことができる。
In the core region of the reactor pressure vessel, the vertical distribution of neutron flux is high at the center of the core, as shown in FIG. 7, and becomes low above and below the center. Therefore, if the monitoring test piece baskets 7 are connected at appropriate intervals depending on the distribution of neutron flux, each monitoring test piece will receive a different amount of neutron irradiation during the same test period. It is possible to collect data on the amount of neutron irradiation.

第8図(A)は本発明にかかる監視試験片着脱装置の他
の実施例を示す断面図、第8図(B)は第8図(A)の
要部拡大図である。
FIG. 8(A) is a sectional view showing another embodiment of the monitoring test piece attaching/detaching device according to the present invention, and FIG. 8(B) is an enlarged view of the main part of FIG. 8(A).

本実施例において、恒久レール6は炉心領域で炉心側に
近傍した位置に配置され、またこの部分に配置された恒
久レール6に複数個の監視試験片バスケット7が所定の
間隔をおいて連結されている。このような配置状態の監
視試験片バスケット7では、炉壁が受ける中性子照射量
以上の加速中性子照射を受けることができるので、中性
子照射量の大きい領域における複数の中性子照射量のデ
ータの採取が可能となる。
In this embodiment, the permanent rail 6 is placed in the core region near the core side, and a plurality of monitoring test specimen baskets 7 are connected to the permanent rail 6 placed in this area at predetermined intervals. ing. The monitoring test piece basket 7 arranged in this manner can receive accelerated neutron irradiation that is greater than the neutron irradiation amount received by the reactor wall, so it is possible to collect data on multiple neutron irradiation doses in areas with large neutron irradiation doses. becomes.

〔発明の効果〕〔Effect of the invention〕

以上のように本発明によれば、原子炉圧力容器内部に設
置される監視試験片の取外しが極めて容易となり、また
必要が生じた場合には監視試験片の新規取付けも容易と
なる。さらに複数個の監視試験片バスケットを炉心の長
手方向に適切な間隔で連結し、原子炉圧力容器内部に設
置すれば、中性子照射量の異なる複数の中性子照射量の
データが一度に採取可能となり、このため中性子照射量
の変化に対する材料の経時劣化のデータを一度に採取す
ることができる。
As described above, according to the present invention, it becomes extremely easy to remove the monitoring test piece installed inside the reactor pressure vessel, and it also becomes easy to install a new monitoring test piece when the need arises. Furthermore, by connecting multiple monitoring test piece baskets at appropriate intervals in the longitudinal direction of the reactor core and installing them inside the reactor pressure vessel, data on multiple neutron irradiation doses with different neutron irradiation doses can be collected at once. Therefore, it is possible to collect data on material deterioration over time in response to changes in neutron irradiation at one time.

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

第1図は本発明にかかる監視試験片着脱装置の原子炉運
転時における全体構成を示す断面図、第2図は本発明に
おける監視試験片バスケットを取付けおよび取外し時の
原子炉圧力容器内部を示す断面図、第3図は本発明にお
ける恒久レールの原子炉圧力容器への取イ(1け状態を
示す側断面図、第4図は第3図の正面図、第5図は監視
試験片バスケットの恒久レールへの取付は状態を示す正
面図、第6図は第5図のA−A線断面図、第7図は原子
炉圧力容器内の炉心領域における監視試験片バスケット
の取付りの状態を示す断面図、第8図(A)は本発明に
かかる監視試験片着脱装置の他の実施例を示す断面図、
第8図(B)は第8図(A)の要部拡大図、第9図は原
子炉圧力容器の全体構成図、第10図は第9図のB−B
線断面図、第11図は第9図における加速照射用監視試
験片バスケットの要部拡大図、第12図は第11図のC
矢視図、第13図は第9図における炉壁用監視試験片バ
スケットの側面図1、第14図は第13図の正面図、第
15図は従来の監視試験片バスケットの取付は状態を示
す説明図である。 ■・・・・・・原子炉圧力容器、 2・・・・・・ドライヤ、   3・・・・・・セパレ
ータ、4・・・・・・炉内配管、   5・・・・・・
ジェットポンプ、6・・・・・・恒久レール、 7・・・・・・監視試験片バスケット、8・・・・・・
フランジ、 9・・・・・・ドライヤ支持ブラケット、10・・・・
・・レールサポート、 11・・・・・・レール支持プラケット、12・・・・
・・ワイヤ、   13・・・・・・車輪、14・・・
・・・ストッパ。
FIG. 1 is a sectional view showing the overall configuration of the monitoring test piece attachment/detachment device according to the present invention during reactor operation, and FIG. 2 shows the inside of the reactor pressure vessel when the monitoring test piece basket according to the present invention is attached and removed. 3 is a side sectional view showing how the permanent rail of the present invention is installed in the reactor pressure vessel (1 piece state), FIG. 4 is a front view of FIG. 3, and FIG. 5 is a monitoring test piece basket. Fig. 6 is a cross-sectional view taken along the line A-A in Fig. 5, and Fig. 7 is a front view showing the state of attachment of the monitoring specimen basket to the permanent rail. FIG. 8(A) is a sectional view showing another embodiment of the monitoring test piece attaching/detaching device according to the present invention;
Figure 8 (B) is an enlarged view of the main parts of Figure 8 (A), Figure 9 is an overall configuration diagram of the reactor pressure vessel, and Figure 10 is B-B of Figure 9.
Line sectional view, Figure 11 is an enlarged view of the main part of the monitoring test piece basket for accelerated irradiation in Figure 9, and Figure 12 is C in Figure 11.
13 is a side view 1 of the furnace wall monitoring specimen basket in FIG. 9, FIG. 14 is a front view of FIG. 13, and FIG. 15 shows the mounting state of the conventional monitoring specimen basket. FIG. ■... Reactor pressure vessel, 2... Dryer, 3... Separator, 4... In-reactor piping, 5...
Jet pump, 6...Permanent rail, 7...Monitoring specimen basket, 8...
Flange, 9...Dryer support bracket, 10...
...Rail support, 11...Rail support placket, 12...
...Wire, 13...Wheel, 14...
...stopper.

Claims (1)

【特許請求の範囲】[Claims] 1)原子炉圧力容器の上下方向に原子炉圧力容器の内壁
面付近に沿ってレールを敷設し、監視試験片を収納した
単数または複数個の監視試験片バスケットを前記レール
に沿って移動自在に設置したことを特徴とする原子炉圧
力容器の監視試験片着脱装置。
1) Rails are laid in the vertical direction of the reactor pressure vessel near the inner wall surface of the reactor pressure vessel, and one or more monitoring test piece baskets containing monitoring test pieces are movable along the rails. A monitoring test piece attaching/detaching device for a nuclear reactor pressure vessel, which is characterized by being installed.
JP60257336A 1985-11-16 1985-11-16 Monitor test piece detachable device for pressure vessel of nuclear reactor Pending JPS62116296A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP60257336A JPS62116296A (en) 1985-11-16 1985-11-16 Monitor test piece detachable device for pressure vessel of nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP60257336A JPS62116296A (en) 1985-11-16 1985-11-16 Monitor test piece detachable device for pressure vessel of nuclear reactor

Publications (1)

Publication Number Publication Date
JPS62116296A true JPS62116296A (en) 1987-05-27

Family

ID=17304944

Family Applications (1)

Application Number Title Priority Date Filing Date
JP60257336A Pending JPS62116296A (en) 1985-11-16 1985-11-16 Monitor test piece detachable device for pressure vessel of nuclear reactor

Country Status (1)

Country Link
JP (1) JPS62116296A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN105810259A (en) * 2014-12-30 2016-07-27 中核武汉核电运行技术股份有限公司 Detection apparatus for pressure vessel of high-temperature gas-cooled reactor

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN105810259A (en) * 2014-12-30 2016-07-27 中核武汉核电运行技术股份有限公司 Detection apparatus for pressure vessel of high-temperature gas-cooled reactor

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