JPH02228593A - Installation of equipment structure in nuclear reactor - Google Patents

Installation of equipment structure in nuclear reactor

Info

Publication number
JPH02228593A
JPH02228593A JP1048506A JP4850689A JPH02228593A JP H02228593 A JPH02228593 A JP H02228593A JP 1048506 A JP1048506 A JP 1048506A JP 4850689 A JP4850689 A JP 4850689A JP H02228593 A JPH02228593 A JP H02228593A
Authority
JP
Japan
Prior art keywords
installation
reactor
recirculation pump
pump
rod drive
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
JP1048506A
Other languages
Japanese (ja)
Inventor
Takehiko Kurose
黒瀬 武彦
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 JP1048506A priority Critical patent/JPH02228593A/en
Publication of JPH02228593A publication Critical patent/JPH02228593A/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

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  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

PURPOSE:To suppress an incovenience within the minimum level in a construction of a nuclear reactor and to shorten a construction period by installing recirculation pumps after an installation of housings of control rod drive mechanisms and then by installing upper grid plates. CONSTITUTION:For a construction of a nuclear reactor, after an installation of a shroud 2 and a reactor core support plate 3 is performed by turns, installation of a housing 7 of a control rod drive mechanism, a feed water sparger 9, a piping 10 of a core spray and so on, are carried out in parallel. After that, an internal recirculation pump 5 is installed and then an upper grid plate 4 is also installed. During the installation of the recirculation pump 5, both works inside and outside a nuclear reactor pressure vessel 1 can be carried out simultaneously. For an installation of equipment structures inside the reactor, a pump opening 6 for fixing the recirculation pump 5 and a housing opening 8 for fixing the housing 7 of the control rod drive mechanism, can be effectively utilized for laying cables and hoses, and consequently a shortening of a construction period can be attained.

Description

【発明の詳細な説明】 (発明の目的) (産業上の利用分野) 本発明は、沸騰水型原子炉の建設時における原子炉内蔵
型再循環ポンプその他の各種炉内機器構造物の据付方法
に関する。
Detailed Description of the Invention (Objective of the Invention) (Industrial Application Field) The present invention provides a method for installing a recirculation pump built into a reactor and various other internal equipment structures during the construction of a boiling water reactor. Regarding.

(従来の技術) 第4図に示すような従来の外部再循環ループを有する沸
騰水型原子炉(BWR)は、再循環ノズル21を開口し
た原子炉圧力容器22内にシュラウド23を固定し、こ
のシュラウド23には、その下部に炉心支持板24を設
ける一方、その上部に上部格子板25を配置している。
(Prior Art) A boiling water reactor (BWR) having a conventional external recirculation loop as shown in FIG. This shroud 23 is provided with a core support plate 24 at its lower part, and an upper lattice plate 25 is arranged at its upper part.

また、シュラウド23の外周面と原子炉圧力容器22の
内周面との間の環状間隙にはその周方向に所要のピッチ
をおいて、複数基のジェットポンプ26を配し、さらに
、インコアモニタ及びtll till棒駆動機駆動機
構するtII III棒駆動駆動機構ハウジング2フウ
ジング開口28に貫挿固定する。そして、上部格子板2
5の上方では給水スパージャ29、コアスプレー配管3
0を原子炉圧力容器22に設けである。
In addition, a plurality of jet pumps 26 are disposed at a required pitch in the circumferential direction in the annular gap between the outer circumferential surface of the shroud 23 and the inner circumferential surface of the reactor pressure vessel 22. and tll till rod drive mechanism is inserted and fixed into the tII and III rod drive drive mechanism housing 2 housing openings 28. And upper lattice plate 2
Above the water supply sparger 29, the core spray pipe 3
0 is provided in the reactor pressure vessel 22.

こうした沸騰水型原子炉においては、第3図に示す従来
の手順に従って、上述した各種の炉内構造物の据付工事
を行なっている。
In such a boiling water reactor, the various reactor internal structures described above are installed in accordance with the conventional procedure shown in FIG.

すなわち、まず、ジェットポンプ26、シュラウド24
を原子炉圧力容器22内に据付け、次にこれらの内方に
配置される炉心支持板24を据付ける。
That is, first, the jet pump 26 and the shroud 24
are installed in the reactor pressure vessel 22, and then the reactor core support plate 24 disposed inside these is installed.

しかる債、炉心支持板24と中心位置を合致させてIl
l m線駆動機構ハウジング27を据付ける。
Align the center position with the core support plate 24, and then
l Install the m-ray drive mechanism housing 27.

一方、これらと並行して、シュラウド23の上方では、
給水スパージャ29、コアスプレー配管30の据付けを
行なう。
On the other hand, in parallel with these, above the shroud 23,
The water supply sparger 29 and core spray piping 30 are installed.

このとき、シュラウド23の上方での作業には、原子炉
圧力容器22の上部開口から作業員等がアクセスしてい
る。一方、制御棒駆動機構ハウジング27等の下部炉内
構造物据付工事には、再循環ノズル21内を出入してア
クセスしており、責機材、作業員のアクセスはもとより
、ケーブル、ホース類の引回し、更にはこれら下部炉内
構造物工事完了後に、再循環ノズル21に再循環用の外
部配管を連結していた。このように上下からの各種工事
を分担することで、工事上のアクセスの二分化を確保し
ていた。
At this time, workers and the like access the work above the shroud 23 from the upper opening of the reactor pressure vessel 22. On the other hand, the installation work for lower reactor internals such as the control rod drive mechanism housing 27 is accessed by going in and out of the recirculation nozzle 21, and not only is the equipment and workers accessed, but cables and hoses can also be accessed. Furthermore, after the construction of these lower reactor internal structures was completed, external piping for recirculation was connected to the recirculation nozzle 21. In this way, by dividing up various construction works from above and below, access for construction work was divided into two parts.

また、上部格子板25の据付けは、その工事エリアがシ
ュラウド23における上方作業のエリアと近接するため
に並行して行なえない。更には、上部格子板25を据付
けた後には炉心支持板24上面へのアクセスが困難とな
り、下部側工事ら非常に面倒になるため、これらが終了
してから取付けることとしていた。
Further, the installation of the upper lattice plate 25 cannot be carried out in parallel because its work area is close to the upper work area of the shroud 23. Furthermore, after the upper grid plate 25 is installed, it becomes difficult to access the upper surface of the core support plate 24, and the work on the lower part becomes very troublesome, so it was decided to install it after these are completed.

(発明が解決しようとする課題) ところが、原子炉内蔵型再循環ポンプ(RIP)を内蔵
した沸騰水型原子炉では、上述の再循環ノズル21がな
いために、この再循環ノズル21内を作業員が出入する
ことができない。
(Problem to be Solved by the Invention) However, in a boiling water reactor equipped with a built-in reactor recirculation pump (RIP), since there is no recirculation nozzle 21 described above, it is difficult to work inside this recirculation nozzle 21. personnel cannot enter or exit.

したがって、作業員等のアクセスは原子炉上部間口から
に限定されることは勿論のこと、■手用ケーブル、ホー
ス類の引回しルート等も太き(11服されるという課題
がある。
Therefore, access for workers is of course limited to the upper frontage of the reactor, and there is also the problem that the routes for hand cables, hoses, etc. are also thick (11).

そこで、本発明は、叙上のような従来存した諸事情に鑑
み創出されたもので、原子か内蔵型再循環ポンプを採用
した沸騰水型原子炉において発生する建設上の不都合を
最少限に抑え、建設工期を短縮することを目的としたも
のであり、各種の原子炉炉内機器構造物の最適な据付手
順を提供することにある。
Therefore, the present invention was created in view of the existing circumstances as described above, and aims to minimize the construction inconveniences that occur in boiling water reactors that employ a built-in recirculation pump. The aim is to reduce construction costs and shorten the construction period, and to provide optimal installation procedures for various types of reactor internal equipment structures.

(発明の構成〕 (!!題を解決するための手段) 上述した目的を達成するため、本発明にあっては、原子
炉内蔵型再循環ポンプを有する沸騰水型原子炉の炉内機
器構造物〜の据付方法において、ill III棒駆動
駆動機構ハウジング付は以降に、再循環ポンプを据付け
、その後、上部格子板を据付けることを特徴としたもの
である。
(Structure of the Invention) (!!Means for Solving the Problem) In order to achieve the above-mentioned object, the present invention provides an internal equipment structure of a boiling water reactor having a reactor built-in recirculation pump. In the installation method of the article, the ill III rod drive drive mechanism with housing is characterized in that the recirculation pump is installed thereafter, and then the upper grate plate is installed.

(作用) 本発明に係る原子炉炉内機器構造物の据付方法において
、再循環ポンプを固定するポンプ開口、及び制−機部動
機構ハウジングを固定するハウジング開口を、工事用の
ケーブル、ホース類等の引回しに最も効率よく利用でき
る。
(Function) In the method for installing a nuclear reactor internal equipment structure according to the present invention, the pump opening for fixing the recirculation pump and the housing opening for fixing the control movement mechanism housing are connected to construction cables, hoses, etc. It can be used most efficiently for routing etc.

また、建設時における再循環ポンプの据付けは、作業員
のアクセス、機器相互の位置関係からも最も障害が少な
い時期にを設定できる。
Additionally, recirculation pumps can be installed during construction at a time when there will be the least disruption in terms of access for workers and the relative position of equipment.

(実施例) 以下、第1図及び第2図を参照して本発明の一実施例を
説明する。
(Example) Hereinafter, an example of the present invention will be described with reference to FIGS. 1 and 2.

第2図において示される符@1は原子炉圧力容器であり
、この原子炉圧力容器1内に同軸状に収容したシュラウ
ド2には、その軸方向中間位置に炉心支持板3を設け、
この炉心支持板3上方に上部格子板4を配しである。こ
の上部格子板4と炉心支持板3とにより図示しない複数
本の燃料集合体の上部と下部とをそれぞれ支持する。
The symbol @1 shown in FIG. 2 is a reactor pressure vessel, and a shroud 2 coaxially accommodated in the reactor pressure vessel 1 is provided with a core support plate 3 at an axially intermediate position.
An upper lattice plate 4 is arranged above this core support plate 3. The upper grid plate 4 and the core support plate 3 support the upper and lower parts of a plurality of fuel assemblies (not shown), respectively.

また、原子炉圧力容器1の内周壁とシュラウド2の外周
壁との間の環状間隙における原子炉圧力容器1の底壁に
は、原子炉内藏型再楯環ポンプ5の一部を貫挿させるが
ポンプn口6が同口され、原子か内蔵型再循環ポンプ5
のポンプ部が原子炉圧力容器1に内蔵配置される。更に
、原子炉圧力容器1底壁には、インコアモニタ及び制m
棒駆動機構を収納するill Ill棒駆機部構ハウジ
ング7をハウジング開口8にn拝することで固定しであ
る。
In addition, a part of the in-reactor trunk-type re-shield ring pump 5 is inserted through the bottom wall of the reactor pressure vessel 1 in the annular gap between the inner circumferential wall of the reactor pressure vessel 1 and the outer circumferential wall of the shroud 2. However, the pump n port 6 is the same port, and the atomic or built-in recirculation pump 5
A pump section is disposed inside the reactor pressure vessel 1. Furthermore, an in-core monitor and control are installed on the bottom wall of the reactor pressure vessel 1.
The rod drive mechanism housing 7, which houses the rod drive mechanism, is fixed by fitting it into the housing opening 8.

そして、上部格子板4上方には給水スパージv9、コア
スプレー配管1o@設けている。
A water supply sparge v9 and a core spray pipe 1o are provided above the upper grid plate 4.

本発明方法においては、このように原子炉内蔵型再循環
ポンプ5を下部に内蔵させた原子炉圧力容器1において
、その原子炉内蔵型再循環ポンプ5の一部を貫挿させて
固定するポンプ開口6、及び!1ltlll棒駆動機構
ハ機部ング7の一部を貫挿させて固定するハウジング開
口8を、工事用のケーブル、ホース類等の引回しに最も
効率よく利用するものである。また、作業員のアクセス
、機器相互の位置関係からも最も障害が少ないように、
建設時における原子炉内蔵型再循環ポンプ5の据付は時
期を設定するものである。
In the method of the present invention, in the reactor pressure vessel 1 in which the reactor built-in recirculation pump 5 is built in the lower part, a part of the reactor built-in recirculation pump 5 is inserted and fixed. Aperture 6, and! The housing opening 8 into which a part of the machine ring 7 is inserted and fixed is most efficiently used for routing cables, hoses, etc. for construction work. In addition, we designed the system to minimize obstacles in terms of worker access and the relative position of equipment.
The timing for installing the reactor built-in recirculation pump 5 at the time of construction is determined.

そこで、本実施例では第1図に示すように、シュラウド
2の据付工事、炉心支持板3の据付工事をこの順に順次
行なった後に、制御棒駆動機構ハウジング7の据付工事
と給水スパージャコアスプレー配管等の据付工事とを並
行して行なう。
Therefore, in this embodiment, as shown in FIG. 1, after the shroud 2 installation work and the core support plate 3 installation work are performed in this order, the control rod drive mechanism housing 7 installation work and the water supply sparger core spray piping work are performed. Other installation work will be carried out in parallel.

しかる後に、原子炉内蔵型再循環ポンプ5の据付工事を
行ない、その後に上部格子板4の据付工事を行なう。
After that, the reactor built-in recirculation pump 5 is installed, and then the upper lattice plate 4 is installed.

しかして、再循環内蔵型再循環ポンプ5の据付は作業に
は、原子炉圧力容器1の内側、外側両方から行なう作業
があり、これが同時に実施できることが条件である。
Therefore, the installation of the recirculation pump 5 with built-in recirculation requires work to be carried out from both the inside and outside of the reactor pressure vessel 1, and it is a condition that these can be carried out at the same time.

まず、内側作業として、シュラウド2の据付工事との関
係を検討する。
First, we will examine the relationship with the installation work of shroud 2 as internal work.

シュラウド2は、原子炉圧力容器1内部における最大の
構造物であり、原子炉圧力容器1との溶接部は原子炉内
蔵型再循環ポンプ5に近い位置にあるから、それらの並
行作業は不可能である。
The shroud 2 is the largest structure inside the reactor pressure vessel 1, and the welded part with the reactor pressure vessel 1 is located close to the reactor built-in recirculation pump 5, so it is impossible to work on these in parallel. It is.

また、原子炉内蔵型再循環ポンプ5は、シュラウド2が
設置されている状態で分解点検が実施できるように設計
されていること、原子炉内蔵型再循環ポンプ5が先に据
付けられている状態でシュラウド2を据付ける場合の再
循環ポンプ5の養生、作業足場設定の複雑化を考慮して
、シュラウド2は原子炉内蔵型再循環ポンプ5より先に
据付けることが有利である。
In addition, the reactor built-in recirculation pump 5 is designed to be able to be overhauled with the shroud 2 installed, and the reactor built-in recirculation pump 5 is installed first. It is advantageous to install the shroud 2 before the reactor built-in recirculation pump 5 in consideration of the complexity of curing the recirculation pump 5 and setting up the work scaffold when installing the shroud 2 in the reactor.

ちなみに、従来のプラントにおいては、ジェットポンプ
26の据付は後にシュラウド23の据付けを実施してい
るが、これは構造的にシュラウド23の据付は後ではジ
ェットポンプ26が据付けられないためである。
Incidentally, in conventional plants, the shroud 23 is installed after the jet pump 26 is installed, but this is because structurally speaking, the jet pump 26 cannot be installed after the shroud 23 is installed.

次に、インコアモニタ(ICM)及び制御棒部111e
1構(CRD)を収納する制御棒駆動機構ハウジング7
の据付けと、原子炉内蔵型再循環ポンプ5との据付は時
期とを検討する。
Next, the in-core monitor (ICM) and control rod section 111e
Control rod drive mechanism housing 7 that houses one structure (CRD)
The timing of installation and the installation of the reactor built-in recirculation pump 5 will be considered.

制御棒駆動機構ハウジング7の据付は作業は、再循環ポ
ンプ5と同様に原子炉圧力容器1内側、外側両方から同
時に行なう必要があるから、外側からの作業は使用する
設備、エリア等が再循環ポンプ5の据付けと干渉するた
めにこれとの並行作業は不可能である。
The installation of the control rod drive mechanism housing 7 must be carried out simultaneously from both the inside and outside of the reactor pressure vessel 1, similar to the recirculation pump 5. Therefore, work from the outside will ensure that the equipment, areas, etc. to be used are recirculating. Parallel work with this pump is not possible because it interferes with the installation of the pump 5.

また、IIIWJ棒駆動機機部ウジング7の据付は作業
は、原子炉圧力容器1内側での大量の溶接作業があるた
めに、その工事用のケーブル、ホース類の段取りを行な
うことが大変な作業となっている。
In addition, the installation of the IIIWJ rod drive machine unit housing 7 involves a large amount of welding work inside the reactor pressure vessel 1, so it is a difficult task to prepare the cables and hoses for this work. It becomes.

したがって、IIJI!l棒駆動機構機部ジング7の据
付は作業は、原子炉内蔵型再循環ポンプ5の据付は作業
より先に実施し、原子炉内蔵型再循環ポンプ5のポンプ
開口6を上述のケーブル、ホース類の引回し等に利用す
るのが得策である。
Therefore, IIJI! The installation of the l-rod drive mechanism machine part 7 is carried out before the installation of the reactor built-in recirculation pump 5, and the pump opening 6 of the reactor built-in recirculation pump 5 is connected to the above-mentioned cables and hoses. It is a good idea to use it for routing etc.

この1lIJ111棒駆動機構ハウジング7の据付けに
は、炉心支持板3の据付けが完了していることが条件で
ある。そのためには、炉心支持板3を支持するシュラウ
ド2の据付けが完了している必要があるので、第1図に
示すように、シュラウド2を据付け、次いで炉心支持板
3を据付け、更に制御棒駆動機構ハウジング7を据付け
たよりも後に、原子炉内蔵型再循環ポンプ5を据付ける
ものである。
The installation of the 1lIJ111 rod drive mechanism housing 7 is conditioned on the completion of the installation of the core support plate 3. To do this, it is necessary to complete the installation of the shroud 2 that supports the core support plate 3, so as shown in Figure 1, the shroud 2 is installed, then the core support plate 3 is installed, and then the control rod drive The reactor built-in recirculation pump 5 is installed after the mechanism housing 7 is installed.

また、給水スパージャ9、コアスプレー配管10等の上
部炉壁に接して据付けられる機器については、炉内側作
業として再循環ポンプ5の据付は作業とは並行に行なう
ことはできない。ただ、制御棒駆動機構ハウジング7の
据付は作業とは並行可能であるから、これと並行して実
施することとし、再循環ポンプ5の据付は前の作業とす
る。
Furthermore, regarding equipment installed in contact with the upper furnace wall, such as the water supply sparger 9 and the core spray piping 10, the recirculation pump 5 cannot be installed in parallel with the work inside the furnace. However, since the installation of the control rod drive mechanism housing 7 can be done in parallel with this work, it will be carried out in parallel with this work, and the installation of the recirculation pump 5 will be the previous work.

最後に、上部格子板4の据付は順序を検討する。Finally, consider the installation order of the upper grid plate 4.

この上部格子板4自体は、シュラウド2に取付けられる
機器であるから、その据付は位財基準として、炉心支持
板3の据付けが完了していることが条件である。
Since the upper lattice plate 4 itself is a device to be attached to the shroud 2, its installation is subject to the completion of the installation of the core support plate 3.

原子炉内蔵型再循環ポンプ5と上部格子板4との関係を
みると、基本的には、上部格子板4と原子炉圧力容器1
の内壁との間隔は原子炉内蔵型再循環ポンプ5の直径よ
りも小さいから、上部格子板4の外周上に、再循環ポン
プ5が通過可能な数箇所の切欠を設け、そこを通過させ
てから所定のポンプ間口6に再循環ポンプ5を配置する
構造になっている。そのため、上部格子板4の狭い切欠
部分での原子炉内蔵型再循環ポンプ5の通過が最も困難
であり、これが据付は上の難所になっているものである
。すなわち、原子炉内蔵型再循環ポンプ5の据付けを、
上部格子板4の据付けに先立って実施しておけば、上述
の狭隘部通過作業にかかる注意が軽減され、作業性が向
上できることは明らかである。
Looking at the relationship between the reactor built-in recirculation pump 5 and the upper grid plate 4, basically, the upper grid plate 4 and the reactor pressure vessel 1
Since the distance from the inner wall of the reactor to the inner wall is smaller than the diameter of the reactor built-in recirculation pump 5, several notches are provided on the outer periphery of the upper grid plate 4 through which the recirculation pump 5 can pass. The recirculation pump 5 is arranged in a predetermined pump opening 6. Therefore, it is most difficult for the reactor built-in recirculation pump 5 to pass through the narrow cutout portion of the upper grid plate 4, and this is the most difficult point in installation. In other words, the installation of the reactor built-in recirculation pump 5,
It is clear that if this is carried out prior to the installation of the upper grid plate 4, the need for the above-mentioned narrow passage work can be reduced and work efficiency can be improved.

もとより、実際運用上の取扱いに近い据付けを行なうこ
とによる定検工事性の検証は必要である。
Of course, it is necessary to verify workability during periodic inspections by performing installations similar to those used in actual operation.

また、プラント建設段階では、定検時に使用されるサー
ビス機器類も完成しておらず、さらに、定検時は水中作
業となることを考慮すれば、この段階で、上部格子板4
の通過作業を上述の検証面から条件とすることは不要で
あると考えられる。
In addition, at the plant construction stage, the service equipment used during periodic inspections has not yet been completed, and considering that work will be carried out underwater during periodic inspections, at this stage, the upper grid plate 4
It is considered unnecessary to make passing work a condition from the above-mentioned verification point of view.

以上の点から、原子炉内蔵型再循環ポンプ5の据付けは
、上部格子板4の据付は前に実施することが据付は工事
上有利である。
From the above points, it is advantageous in construction work to install the reactor built-in recirculation pump 5 before installing the upper lattice plate 4.

(発明の効果) 以上説明したような原子炉炉内機器構造物の据付方法に
よれば、工事用ケーブル、ホース類の引回しルートを最
短にすることが可能であり、仮設の工事物置の低減に寄
与するとともに、溶接工事の品質向上効果も期待できる
ものである。
(Effects of the Invention) According to the method of installing equipment structures inside a nuclear reactor as explained above, it is possible to minimize the route for wiring construction cables and hoses, and the need for temporary construction storage can be reduced. In addition to contributing to the quality of welding work, it is also expected to improve the quality of welding work.

また、定検時と異なり、−時期に全数の据付けを可能に
するという建設段階特有の工事消化に最も適った効率的
な作業を実施することが可能である。
In addition, unlike the periodic inspection, it is possible to carry out the most efficient work that is most suitable for completing the construction work, which is unique to the construction stage, by making it possible to install all the pieces in a period of -3.

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

第1図及び第2図は本発明の実施例を示し、第1図は据
付手順を説明する作業工程図、第2図は原子炉炉内機器
構造物の据付配置図であり、第3図及び第4図は従来例
を示し、第3図はその据付手順の縮図、第4図はその原
子炉炉内機器構造物の据付配置図である。 1・・・圧力容器、2・・・シュラウド、3・・・炉芯
支持板、4・・・上部格子板、5・・・再循環ポンプ、
6・・・ポンプ開口、7・・・制御棒駆動機構ハウジン
グ、8・・・ハウジング開口、9・・・給水スパージャ
、10・・・コアスプレー配管、21・・・再循環ノズ
ル開口、22・・・圧力容器、2.3・・・・炉心支持
板、24・・・シュラウド、25・・・上部格子板、2
6・・・ジェットポンプ、27・・・制御棒駆動機構ハ
ウジング、28・・・ハウジング開口、29・・・給水
スパージャ、30・・・コアスプレー配管。 第1図 代理人弁理士  則 近  憲 缶 周        第  子  丸   健第3図 第 図 第 図
1 and 2 show an embodiment of the present invention, FIG. 1 is a work process diagram explaining the installation procedure, FIG. 2 is an installation layout diagram of the equipment structure inside the reactor, and FIG. 4 shows a conventional example, FIG. 3 is a microcosm of its installation procedure, and FIG. 4 is an installation layout diagram of the internal equipment structure of the nuclear reactor. DESCRIPTION OF SYMBOLS 1... Pressure vessel, 2... Shroud, 3... Core support plate, 4... Upper grid plate, 5... Recirculation pump,
6... Pump opening, 7... Control rod drive mechanism housing, 8... Housing opening, 9... Water supply sparger, 10... Core spray piping, 21... Recirculation nozzle opening, 22... ... Pressure vessel, 2.3 ... Core support plate, 24 ... Shroud, 25 ... Upper grid plate, 2
6... Jet pump, 27... Control rod drive mechanism housing, 28... Housing opening, 29... Water supply sparger, 30... Core spray piping. Figure 1 Representative Patent Attorneys Nori Chika Ken Shu Ken Komaru Figure 3 Figure Figure 3

Claims (1)

【特許請求の範囲】[Claims] 原子炉内蔵型再循環ポンプを内蔵する沸騰水型原子炉の
炉内機器構造物の据付方法において、制御棒駆動機構ハ
ウジングの据付け以降に、再循環ポンプを据付け、その
後、上部格子板を据付けることを特徴とした原子炉炉内
機器構造物の据付方法。
In the method for installing the reactor equipment structure of a boiling water reactor with a built-in recirculation pump, the recirculation pump is installed after the control rod drive mechanism housing is installed, and then the upper grate plate is installed. A method for installing equipment structures inside a nuclear reactor, characterized by:
JP1048506A 1989-03-02 1989-03-02 Installation of equipment structure in nuclear reactor Pending JPH02228593A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1048506A JPH02228593A (en) 1989-03-02 1989-03-02 Installation of equipment structure in nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP1048506A JPH02228593A (en) 1989-03-02 1989-03-02 Installation of equipment structure in nuclear reactor

Publications (1)

Publication Number Publication Date
JPH02228593A true JPH02228593A (en) 1990-09-11

Family

ID=12805263

Family Applications (1)

Application Number Title Priority Date Filing Date
JP1048506A Pending JPH02228593A (en) 1989-03-02 1989-03-02 Installation of equipment structure in nuclear reactor

Country Status (1)

Country Link
JP (1) JPH02228593A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2010066216A (en) * 2008-09-12 2010-03-25 Hitachi-Ge Nuclear Energy Ltd Installation method of incore equipment of natural circulation type boiling water reactor

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2010066216A (en) * 2008-09-12 2010-03-25 Hitachi-Ge Nuclear Energy Ltd Installation method of incore equipment of natural circulation type boiling water reactor
JP4684324B2 (en) * 2008-09-12 2011-05-18 日立Geニュークリア・エナジー株式会社 How to install in-reactor equipment of natural circulation boiling water reactor

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