JPS62121396A - Hanging tool for structure in nuclear reactor - Google Patents
Hanging tool for structure in nuclear reactorInfo
- Publication number
- JPS62121396A JPS62121396A JP60259748A JP25974885A JPS62121396A JP S62121396 A JPS62121396 A JP S62121396A JP 60259748 A JP60259748 A JP 60259748A JP 25974885 A JP25974885 A JP 25974885A JP S62121396 A JPS62121396 A JP S62121396A
- Authority
- JP
- Japan
- Prior art keywords
- control rod
- reactor
- lifting
- rod assembly
- internal structure
- 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
Links
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
- Load-Engaging Elements For Cranes (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】
[産業上の利用分野コ
本発明は水冷却型原子炉に関し、特にその燃t+交換時
等に使用する原子炉炉内構造物の吊上工具に関するもの
である。DETAILED DESCRIPTION OF THE INVENTION [Field of Industrial Application] The present invention relates to a water-cooled nuclear reactor, and more particularly to a tool for lifting the internal structure of a nuclear reactor used when exchanging fuel.
[従来の技術]
周知のように、例えば加圧水型原子炉のような典型的な
水冷却型原子炉においては、原子炉容器内に炉心槽が垂
下して配設され、該炉心槽の下部炉心支持板上に多数の
燃料集合体から構成される炉心が配設されている。また
、炉心槽内には該炉心の直上に、制御棒集合体の案内筒
を持つ炉内構造物が設けられており、この炉内構造物も
原子炉容器のフランジ部に垂下支持される。制御棒集合
体は周知のように出力制御用制御棒、負荷追従用制御棒
、水排除用棒等の各種棒から構成される。[Prior Art] As is well known, in a typical water-cooled nuclear reactor such as a pressurized water reactor, a core tank is disposed hanging down within the reactor vessel, and the lower core of the core tank is A reactor core composed of a large number of fuel assemblies is disposed on a support plate. Further, a reactor internal structure having a guide tube for a control rod assembly is provided in the reactor core barrel just above the reactor core, and this reactor internal structure is also suspended and supported by the flange portion of the reactor vessel. As is well known, the control rod assembly is composed of various rods such as an output control control rod, a load following control rod, and a water removal rod.
従来、第7図及び第8図から読解されるように、制御棒
集合体1は、複数の棒1aと、該棒の頂部をねじにより
相互に結合するスパイダ4とからなっており、通常、炉
内構造物2において案内筒Za内に収納されている。ま
た、スパイダ4には駆動軸3も連結されており、該駆動
軸3が原子炉容器の上部蓋体く図示せず)に装着された
図示しない制御棒駆動装置に連絡している。Conventionally, as can be read from FIGS. 7 and 8, a control rod assembly 1 is composed of a plurality of rods 1a and a spider 4 that connects the tops of the rods to each other with screws, and usually, It is housed in a guide tube Za in the reactor internal structure 2. A drive shaft 3 is also connected to the spider 4, and the drive shaft 3 communicates with a control rod drive device (not shown) mounted on the upper lid of the reactor vessel (not shown).
このような原子炉の燃料交換時には、原子炉容器の蓋体
が取り外されると、制御棒駆動装置は駆動軸3から切り
離されるから、制御棒集合体1及び駆動軸3の連結体は
何の拘束も受けず、制御棒集り体1のスパイダ4が案内
筒2aの底板5に乗った状態となる。従って、燃料交換
時に上部炉内+14造物2が吊り上げられて移動する際
、多数の制御棒q七合体]が上部炉内構造物2の上部炉
心支持板6の下方に何のガイドもなしにぶら下がってい
る状態になる。また、原子炉から取り出された、多数密
集して垂下する制御棒集合体1は1本1本検査な行わな
ければならない。During refueling of such a reactor, when the lid of the reactor vessel is removed, the control rod drive device is separated from the drive shaft 3, so the connection between the control rod assembly 1 and the drive shaft 3 is not restrained. The spider 4 of the control rod assembly 1 is placed on the bottom plate 5 of the guide tube 2a. Therefore, when the upper reactor inner structure 2 is lifted and moved during fuel exchange, a large number of control rods q7] hang below the upper core support plate 6 of the upper reactor internal structure 2 without any guide. It will be in a state where it is. Further, the control rod assembly 1, which is taken out from the nuclear reactor and hangs down in large numbers, must be inspected one by one.
「発明が解決しようとする問題点]
従って、従来の技術には、上部炉内構造物の運搬に支障
を来たしたり、制御棒集合体検査時の作業性が悪いとい
った問題点があった0本発明はかかる問題点を速やかに
解決する原子炉炉内構造物の吊上工具を提供することを
目的とするものである。``Problems to be Solved by the Invention'' Therefore, the conventional technology has problems such as difficulty in transporting the upper reactor internals and poor workability during inspection of control rod assemblies. The object of the invention is to provide a tool for lifting internal structures of a nuclear reactor, which can quickly solve these problems.
[問題点を解決するための手段]
こめ目的から本発明は、制御棒集合体の案内筒を持つ原
子炉炉内ti構造物該制御棒集合体と共に吊り上げる吊
上工具であって、水平方向に延びる架台、該架台から垂
下し11汀記炉内構造物に結合できる複数の主コラム、
該主コラムに沿−)で昇降可能に支持され、前記制御棒
集合体に連結した駆動軸を多数一括して把持するつかみ
部、及び該つかみ部及び主コラムに関連して設けられつ
かみ部を上下させる昇降装置を備えるものである。[Means for Solving the Problems] For the purpose of this, the present invention is a lifting tool for lifting a reactor internal ti structure having a guide tube for a control rod assembly together with the control rod assembly. an extending pedestal, a plurality of main columns depending from the pedestal and capable of being coupled to the 11th reactor internals;
a grip part that is supported so as to be movable up and down along the main column and that collectively grips a number of drive shafts connected to the control rod assembly; and a grip part that is provided in relation to the grip part and the main column. It is equipped with a lifting device that raises and lowers it.
[作用]
原子炉容器の上部蓋体を取り除いた後、吊」二工具を吊
り下げ炉内構造物上に運搬する。次に、主コラムを炉内
構造物に固定すると共に、駆動軸つかみ部を操作して駆
動軸の」二端を把持する。しかる後、昇降装置を所望の
方向に作動ずれば、昇降装置には駆動軸つかみ部が関連
しているので、昇降装置の作動に伴って、駆動軸つかみ
部は主コラムに沿って上方へ移動する。従って、駆動軸
つかみ部に把持された駆動軸に関連した制御棒集き体も
上方に引き上げられ、炉内構造物の案内筒内に収納され
る。[Operation] After removing the upper lid of the reactor vessel, the two hanging tools are carried onto the suspended reactor internals. Next, the main column is fixed to the reactor internals, and the drive shaft gripping section is operated to grip the two ends of the drive shaft. After that, if the lifting device is operated in a desired direction, the driving shaft gripping portion is associated with the lifting device, so that the driving shaft gripping portion moves upward along the main column as the lifting device is operated. do. Therefore, the control rod assembly related to the drive shaft gripped by the drive shaft gripping portion is also pulled upward and housed in the guide cylinder of the reactor internal structure.
[実施例]
次に、本発明の好適な実施例について添1寸図面を参照
して詳細に説明するが、図中、同一符号は同−又は対応
部分を示すものとする。[Embodiments] Next, preferred embodiments of the present invention will be described in detail with reference to the accompanying drawings, in which the same reference numerals indicate the same or corresponding parts.
第]U2I及び第2図は本発明による吊上工具の第1実
施例を示す。該吊上工具は水平方向に延びる作業台又は
架台16を有し、該架台16に複数の主コラム11(実
施例では3本)が垂下し支持されている。] U2I and FIG. 2 show a first embodiment of a lifting tool according to the present invention. The lifting tool has a horizontally extending workbench or pedestal 16, from which a plurality of main columns 11 (three in the embodiment) are suspended and supported.
各主コラム11は外筒11aと、その内部の軸1 lb
とからなり、軸11bの下端が上部炉内構造物2のフラ
ンジ部に例えば螺着のような手段により着脱可能である
。この着脱操作並びに後述する駆動軸つかみ部及びつか
み部昇降装置の操作は、図示しないそれ等の操作ユニッ
トが設けられた架台16上から行うことができる。Each main column 11 has an outer cylinder 11a and an inner shaft 1 lb.
The lower end of the shaft 11b can be attached to and detached from the flange portion of the upper reactor internal structure 2 by means such as screwing. This attachment/detachment operation and the operation of the drive shaft gripping portion and the gripping portion elevating device, which will be described later, can be performed from the pedestal 16 provided with such operation units (not shown).
これ等の主コラム11には摺動ブロックlieが昇降可
能に嵌合しており、該摺動ブロックlieは吊上部15
を有するスリングブロック部14を水平状聾に支持して
いる。吊上部15の先端には吊り金具18が設けられて
おり、本発明の吊上工具を炉内構造物2に収り付は後、
図示しないクレーンによりこの吊り金具18て吊り下げ
ることがてきる。、スリングブロック部14はその下方
に、周知のように多数の駆動軸を一括して把持する駆動
軸つかみ部13を備えている。この駆動軸つかみ部13
は任意の駆動軸のラッチ及びアンラッチを行いうる型式
のものが好適である。A sliding block lie is fitted into these main columns 11 so as to be able to move up and down, and the sliding block lie is connected to the lifting section 15.
The sling block portion 14 having a horizontal shape is supported horizontally. A hanging fitting 18 is provided at the tip of the lifting part 15, and after the lifting tool of the present invention is installed in the furnace internal structure 2,
This hanging fitting 18 can be used to hang it using a crane (not shown). The sling block part 14 is provided with a drive shaft gripping part 13 below the sling block part 14, which grips a large number of drive shafts at once, as is well known. This drive shaft grip part 13
It is preferable to use a type that can latch and unlatch any drive shaft.
また、摺動ブロック部14にはつがみ部昇降装匠17が
関連している。この実施例においては、昇降装置17は
、架台16(主コラム11でもよい〉に固定された液圧
シリンダ17aと、該液圧シリンダ17aから下方に延
び下端て摺動ブロックllcに固着されるピストンロッ
ド17bとからなる液圧式である。Further, a grip part lifting device 17 is associated with the sliding block part 14. In this embodiment, the lifting device 17 includes a hydraulic cylinder 17a fixed to the pedestal 16 (which may also be the main column 11), and a piston extending downward from the hydraulic cylinder 17a and fixed at its lower end to the sliding block llc. It is a hydraulic type consisting of a rod 17b.
以上のように構成された本発明の吊上工具は次のように
作動する。第1図において、図示しない原子炉容器の上
部蓋体を取り除いた後、クレーン等により吊り金具18
で吊上工具を吊り下げ、炉内構造物2上に運搬する。次
に、架台16から1tlli111.bを操作して!l
1lllllbを炉内構造物2のフランジ部に固定する
と共に、駆動軸つかみ部13を操作して駆動1jll1
3(第7図参照)の上端と把持する。しかる後、同様に
架台16からの操作により、矢印Aて示すように水のよ
うな圧力流体を液圧シリンダ1.7a内に導入すれば、
ビス1〜ンロツド17bは上昇する。該ビス1−ンロツ
ド171)の下端には摺動ブラケットlieが固着され
ており、そして該摺動ブロック11cには駆動軸つかみ
部13を有するスリングブロック部14が設置されてい
るので、ピストンロッド17bの上昇に伴って、駆動軸
つかみ部13及び吊上部15等は第1図に鎖線で示すよ
うに主コラム11に沿って上方へ移動する。&eっで、
駆動軸つかみ部13に把持された駆動軸3に関連した制
御棒集合体1 (第7図参照)も上方に引き上げられ、
炉内構造物2の案内筒2a(第7図)内に収納される。The lifting tool of the present invention configured as described above operates as follows. In FIG. 1, after removing the upper lid of the reactor vessel (not shown), the hanging metal fitting 18 is removed using a crane or the like.
The lifting tool is suspended and transported onto the reactor internal structure 2. Next, from the pedestal 16, 1tlli111. Operate b! l
1lllllb to the flange part of the reactor internals 2, and operate the drive shaft grip part 13 to release the drive 1jll1.
3 (see Figure 7). After that, if a pressure fluid such as water is introduced into the hydraulic cylinder 1.7a as shown by arrow A by the same operation from the pedestal 16,
Screws 1 to 17b rise. A sliding bracket is fixed to the lower end of the screw rod 171), and a sling block portion 14 having a drive shaft gripping portion 13 is installed on the sliding block 11c, so that the piston rod 17b With the rise of the main column 11, the drive shaft gripping part 13, the lifting part 15, etc. move upward along the main column 11, as shown by chain lines in FIG. &e,
The control rod assembly 1 (see FIG. 7) associated with the drive shaft 3 gripped by the drive shaft grip part 13 is also pulled upward,
It is housed in the guide tube 2a (FIG. 7) of the reactor internals 2.
この時、吊上部15の一部と吊り金具18とは、架台1
6にある穴16aを貫いて架台16の上方へ延びている
ので、吊り金具18にクレーン等を引っ掛け、制御棒集
合体1を案内筒2aに収納した釈明で上部炉内構造物2
と共に運搬することが可能になる。At this time, a part of the hanging part 15 and the hanging fittings 18 are connected to the frame 1.
6 and extends above the pedestal 16, so that a crane or the like can be hooked to the hanging fitting 18, and the upper reactor internal structure 2 can be secured by storing the control rod assembly 1 in the guide tube 2a.
It becomes possible to transport it together.
以上の逆の手順で操作すれば吊上工具から制御棒(J、
、1>休1を解放することができる。By reversing the above steps, you can move the control rod (J,
, 1 > rest 1 can be released.
第1実施例においては昇降装置17は液圧式シリング等
から構成されていたが、その他種々の昇降+A置を用い
ることがてきる。例えば、第3図及び第4図に示すよう
に、ワイヤローブ17d、シーブ17e、ISBS上動
タ17「等からなるワイヤロープ巻」二機構17でもよ
いし、第5図及び第6図に示すように、ワイヤローブの
代わりにチェーン’1.7gを用いるヂエーン巻上機構
でもよく、これ等も第1図及び第2図に関連して説明し
た昇降装置17と実質的に同様に作動でき、且つ同様の
作用効果を奏する。In the first embodiment, the elevating device 17 was constructed from a hydraulic sill, etc., but various other elevating and lowering + A positions may be used. For example, as shown in FIGS. 3 and 4, a wire rope winding mechanism 17 consisting of a wire lobe 17d, a sheave 17e, an ISBS upper moving motor 17, etc. may be used, or as shown in FIGS. Alternatively, a chain hoisting mechanism using a 1.7g chain instead of the wire lobes may be used, which can operate substantially in the same manner as the lifting device 17 described in connection with FIGS. It has the following effects.
[発明の効果コ
本発明の吊上工具は以上のような構成及び作用を有する
ので、燃料交換等の際の上部炉内構造物運搬時に制御棒
集合体を案内筒に収納することができ、炉内構造物運搬
に支障を来たすことがない。[Effects of the Invention] Since the lifting tool of the present invention has the above configuration and function, the control rod assembly can be stored in the guide tube when transporting the upper reactor internals during fuel exchange, etc. There will be no hindrance to the transportation of reactor internals.
また、これに波及して、制御棒集き体検査時の作業性を
向上することもできる他、吊上工具に制御棒!a会合体
昇降装置を内蔵するため、制御棒集合体昇降用の特別な
リフトクレーン設備を別途設ける必要もない。This also extends to improving workability when inspecting control rod assemblies, and also allows control rods to be used as lifting tools! Since the assembly lifting device is built-in, there is no need to separately provide special lift crane equipment for lifting and lowering the control rod assembly.
第1図は本発明による吊上工具の第1実施例の左半分を
示す側面図、第2図は第1図の平面図、第3図及び第4
図は本発明の第2実施例の第1図及び第2図に相当する
図、第5図及び第6図は本発明の第3実施例の第1図及
び第2図に11当する図、第7(2Iは従来の上部炉内
構造物の運搬態様を説明する断面図、第80は第7図に
楕円形で示した領域■の拡大断面図である。
1 制御棒集合体 2・・・炉内構造物2a・・案内
筒 3・・駆動軸11−主コラム 13
・・・つかみ部16・架台 17・昇降装置
2−斗IFIG. 1 is a side view showing the left half of the first embodiment of the lifting tool according to the present invention, FIG. 2 is a plan view of FIG. 1, and FIGS.
The figures correspond to FIGS. 1 and 2 of the second embodiment of the present invention, and FIGS. 5 and 6 correspond to FIGS. 1 and 2 of the third embodiment of the present invention. , No. 7 (2I is a cross-sectional view illustrating the transportation mode of conventional upper reactor internals, No. 80 is an enlarged cross-sectional view of the area ■ shown in an oval shape in FIG. 7. 1 Control rod assembly 2. ...Furnace internals 2a...Guide tube 3...Drive shaft 11-Main column 13
...Gripping part 16, pedestal 17, lifting device 2-Dou I
Claims (1)
棒集合体と共に吊り上げる吊上工具であつて、水平方向
に延びる架台、該架台から垂下し前記炉内構造物に結合
できる複数の主コラム、該主コラムに沿って昇降可能に
支持され、前記制御棒集合体に連結した駆動軸を多数一
括して把持するつかみ部、該つかみ部及び主コラムに関
連して設けられつかみ部を上下させる昇降装置、を備え
る原子炉炉内構造物の吊上工具。A lifting tool for lifting a nuclear reactor internal structure having a guide tube for a control rod assembly together with the control rod assembly, the lifting tool comprising a horizontally extending pedestal, and a plurality of units that hang down from the pedestal and can be coupled to the reactor internal structure. a main column, a grip part that is supported so as to be movable up and down along the main column and that collectively grips a large number of drive shafts connected to the control rod assembly, and a grip part that is provided in relation to the grip part and the main column. A lifting tool for a nuclear reactor internal structure, comprising a lifting device for raising and lowering a reactor.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP60259748A JPS62121396A (en) | 1985-11-21 | 1985-11-21 | Hanging tool for structure in nuclear reactor |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP60259748A JPS62121396A (en) | 1985-11-21 | 1985-11-21 | Hanging tool for structure in nuclear reactor |
Publications (1)
Publication Number | Publication Date |
---|---|
JPS62121396A true JPS62121396A (en) | 1987-06-02 |
Family
ID=17338400
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP60259748A Pending JPS62121396A (en) | 1985-11-21 | 1985-11-21 | Hanging tool for structure in nuclear reactor |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS62121396A (en) |
Citations (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS50121693A (en) * | 1974-03-01 | 1975-09-23 |
-
1985
- 1985-11-21 JP JP60259748A patent/JPS62121396A/en active Pending
Patent Citations (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS50121693A (en) * | 1974-03-01 | 1975-09-23 |
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