JPS6328271B2 - - Google Patents

Info

Publication number
JPS6328271B2
JPS6328271B2 JP56113128A JP11312881A JPS6328271B2 JP S6328271 B2 JPS6328271 B2 JP S6328271B2 JP 56113128 A JP56113128 A JP 56113128A JP 11312881 A JP11312881 A JP 11312881A JP S6328271 B2 JPS6328271 B2 JP S6328271B2
Authority
JP
Japan
Prior art keywords
reactor
equipment
containment vessel
loading
building
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
Application number
JP56113128A
Other languages
Japanese (ja)
Other versions
JPS5814087A (en
Inventor
Shiro Kikuchi
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 JP56113128A priority Critical patent/JPS5814087A/en
Publication of JPS5814087A publication Critical patent/JPS5814087A/en
Publication of JPS6328271B2 publication Critical patent/JPS6328271B2/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

Landscapes

  • Radiation-Therapy Devices (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 この発明は高速増殖炉等用原子力発電所におけ
る原子炉施設に係り、特に原子炉格納容器を収容
した原子炉施設に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a nuclear reactor facility in a nuclear power plant such as a fast breeder reactor, and more particularly to a nuclear reactor facility housing a reactor containment vessel.

従来、高速増殖炉等用原子力発電所において
は、原子炉補助建物内に原子炉格納容器が設けら
れ、この原子炉格納容器に原子炉圧力容器を備え
た原子炉建物が組み込まれている。原子炉格納容
器の側壁に1つの機器搬出入口が形成され、この
機器搬出入口を通じて、原子炉の定期点検時や燃
料交換時等に各種原子炉機器を搬出入している。
各種機器の搬出入時には原子炉の運転を停止して
搬出入作業が進められる。
Conventionally, in nuclear power plants for fast breeder reactors and the like, a reactor containment vessel is provided in a reactor auxiliary building, and a reactor building including a reactor pressure vessel is incorporated into this reactor containment vessel. An equipment loading/unloading port is formed in the side wall of the reactor containment vessel, and various nuclear reactor equipment is loaded/unloaded through this equipment loading/unloading port during periodic reactor inspections, fuel changes, etc.
When carrying in and out various equipment, the reactor operation is stopped and the work is carried out.

しかしながら、従来の原子炉格納容器は機器搬
出入口が1つしか形成されていないため、原子炉
機器の搬出入時に、搬出機器と搬入機器とが互い
に衝突し、搬出入作業がスムーズに行なわれなか
つたりするため、原子炉停止期間が長びく等の問
題があつた。
However, since conventional reactor containment vessels have only one equipment loading/unloading entrance, when carrying out reactor equipment, the loading/unloading equipment collides with each other, making it difficult to carry out the loading/unloading work smoothly. This caused problems such as the reactor shutdown period being prolonged.

一方、原子炉プラント建設時には、原子炉格納
容器内に収容される原子炉機器の搬入作業が多い
ため、機器搬出入口以外に仮設の搬入口を臨時に
設け、各種原子炉機器の搬入作業をスムーズに行
ない得るようにして、プラント建設期間の短縮化
を図つている。
On the other hand, during the construction of a nuclear reactor plant, there is a lot of work to bring in reactor equipment to be housed in the reactor containment vessel, so a temporary entrance was set up in addition to the equipment entrance to facilitate the work to bring in various reactor equipment. We are working to shorten the plant construction period by making it possible for the plant to be constructed as quickly as possible.

しかし、仮設の搬入口は原子炉機器搬入後には
復旧して閉塞しなければならず、かつこの閉塞作
業は複雑で長時間を要し、原子炉プラント建設期
間遅延の原因となつていた。
However, the temporary entrance had to be restored and blocked after the reactor equipment was brought in, and this blocking work was complex and took a long time, causing delays in the reactor plant construction period.

この発明は上述した点を考慮し、原子炉格納容
器の側壁に複数の機器搬出入口を形成することに
より、各種原子炉機器の搬出入に要する作業時間
を短縮し、原子炉プラントの運転稼動率を高める
とともにプラント建設時に仮設の機器搬入口を不
要にした原子炉施設を提供することを目的とす
る。
This invention takes the above-mentioned points into account, and by forming a plurality of equipment loading/unloading entrances on the side wall of the reactor containment vessel, the work time required for loading/unloading various nuclear reactor equipment is shortened, and the operational availability of the nuclear reactor plant is improved. The purpose of this project is to provide a nuclear reactor facility that increases the efficiency of nuclear power plants and eliminates the need for temporary equipment entrances during plant construction.

以下、この発明の実施例について添付図面を参
照して説明する。
Embodiments of the present invention will be described below with reference to the accompanying drawings.

第1図および第2図は高速増殖炉等の原子力発
電所における原子炉施設を示し、図中符号10は
基礎マツト11上に建設された原子炉補助建物で
ある。この原子炉補助建物10の中央部に原子炉
格納容器12が組み込まれる。原子炉格納容器1
2内に原子炉建物13が収容され、原子炉建物1
3内の中央部に図示しない原子炉圧力容器が設け
られる。
1 and 2 show nuclear reactor facilities in a nuclear power plant such as a fast breeder reactor, and reference numeral 10 in the figures indicates a reactor auxiliary building constructed on a foundation mat 11. A reactor containment vessel 12 is installed in the center of this reactor auxiliary building 10. Reactor containment vessel 1
The reactor building 13 is housed in the reactor building 1.
A reactor pressure vessel (not shown) is provided in the center of the reactor 3.

原子炉格納容器12の側壁には2つの機器搬出
入口16,16がそれぞれ周方向に離間して形成
される。機器搬出入口16,16は原子炉建物1
3の運転操作床面Aに相当するレベルに位置され
て原子炉格納容器12の内外を連通し、原子炉補
助建物10内に形成された機器搬出入路18,1
8に通じている。この搬出入路18,18も機器
搬出入口16,16と同じ高さ位置に設けられ
る。このため、機器搬出入口16,16によつて
例えば大型の機器の搬出入を行う場合、原子炉圧
力容器によつて機器の搬出入が妨害されることは
ない。また、機器搬出入口16,16と機器搬出
入路18,18を介して建屋外と原子炉格納容器
12内との間で直接機器の搬出入を行うことがで
きる。
Two equipment loading/unloading ports 16, 16 are formed in the side wall of the reactor containment vessel 12, spaced apart from each other in the circumferential direction. Equipment loading/unloading entrances 16, 16 are in the reactor building 1
Equipment loading/unloading passages 18, 1 are located at a level corresponding to the operation floor A of No. 3, communicate the inside and outside of the reactor containment vessel 12, and are formed within the reactor auxiliary building 10.
It leads to 8. The loading/unloading passages 18, 18 are also provided at the same height position as the equipment loading/unloading entrances 16, 16. For this reason, when carrying in and out, for example, large equipment through the equipment carry-in/out ports 16, 16, the reactor pressure vessel does not obstruct the carrying in/out of the equipment. Further, equipment can be directly carried in and out between the outside of the building and the inside of the reactor containment vessel 12 via the equipment carry-in/out entrances 16, 16 and the equipment carry-in/out passages 18, 18.

原子炉格納容器12の機器搬出入口16は、第
3図に示すように、原子炉格納容器12の側壁に
溶接等で固着された筒状体20内に形成される。
筒状体20は望ましくは円筒状をなし、その軸線
は原子炉格納容器12の側壁面に直交している。
筒状体20の開口は原子炉格納容器12の内側で
蓋体21により密封可能に覆われる。蓋体21
は、蓋フランジ22を有し、このフランジ22が
筒状体20の端部に一体成形された筒状体フラン
ジ23に取付ボルト24等の取付手段で取外し可
能に取付けられ、両フランジ面はOリング等のシ
ーリング部材25により密着される。しかして、
筒状体20および両フランジ23,24は機器搬
出入口16部を補強しており、筒状体20の内部
空間が原子炉用各種機器搬出入のための有効空間
を形成している。
As shown in FIG. 3, the equipment loading/unloading port 16 of the reactor containment vessel 12 is formed in a cylindrical body 20 fixed to the side wall of the reactor containment vessel 12 by welding or the like.
The cylindrical body 20 preferably has a cylindrical shape, and its axis is perpendicular to the side wall surface of the reactor containment vessel 12.
The opening of the cylindrical body 20 is hermetically covered by a lid 21 inside the reactor containment vessel 12 . Lid body 21
has a lid flange 22, and this flange 22 is removably attached to a cylindrical body flange 23 integrally formed at the end of the cylindrical body 20 by means of attachment means such as mounting bolts 24, and both flange surfaces are O. It is closely attached by a sealing member 25 such as a ring. However,
The cylindrical body 20 and both flanges 23 and 24 reinforce the equipment loading/unloading port 16, and the internal space of the cylindrical body 20 forms an effective space for loading/unloading various nuclear reactor equipment.

なお、第1図において、符号27は作業員用エ
アーロツクであり、このエアーロツクも原子炉格
納容器12の側壁に気密に取付けられる。
In FIG. 1, reference numeral 27 indicates an air lock for workers, and this air lock is also airtightly attached to the side wall of the reactor containment vessel 12.

次に、この発明の作用について説明する。 Next, the operation of this invention will be explained.

原子炉プラントの通常運転時には、原子炉格納
容器12に形成される機器搬出入口16は蓋体2
1により気密状態に覆われ、原子炉格納容器バウ
ンダリを形成する。
During normal operation of a nuclear reactor plant, the equipment loading/unloading entrance 16 formed in the reactor containment vessel 12 is connected to the lid body 2.
1 to form a reactor containment vessel boundary.

原子炉の定期点検作業や燃料交換作業の際に
は、原子炉プラントの運転を停止させ、この運転
停止後に、取付ボルト24等の取付手段を操作し
て蓋体21を筒状体20から取外し、原子炉格納
容器12の機器搬出入口16,16を開口させ
る。この場合、原子炉格納容器12には2つの機
器搬出入口16,16が周方向に独立して配置さ
れているから、互いに独立した機器搬出入ルート
を得ることができ、一方の機器搬出入ルートを例
えば搬入用に、他方を搬出用にそれぞれ独立して
形成すれば、原子炉格納容器12からの搬出入作
業をスムーズにかつ能率的に行なうことができ
る。これにより、燃料交換作業や定期点検作業を
スムーズに短時間で行なうことができる。
During periodic inspection work or fuel exchange work on a nuclear reactor, the operation of the nuclear reactor plant is stopped, and after this operation is stopped, the lid body 21 is removed from the cylindrical body 20 by operating the attachment means such as the mounting bolts 24. , the equipment loading/unloading ports 16, 16 of the reactor containment vessel 12 are opened. In this case, since the two equipment loading/unloading ports 16, 16 are arranged independently in the circumferential direction in the reactor containment vessel 12, mutually independent equipment loading/unloading routes can be obtained, and one equipment loading/unloading route For example, by forming one for carrying in and the other for carrying out independently, the work of carrying in and out of the reactor containment vessel 12 can be carried out smoothly and efficiently. This allows fuel replacement work and periodic inspection work to be carried out smoothly and in a short time.

各種原子炉機器の搬出入作業が終了すると、原
子炉格納容器12の機器搬出入口16は蓋体21
で再び閉塞されて原子炉格納容器バウンダリが形
成され、原子炉プラントの運転再開に備えられ
る。
When the loading/unloading work of various reactor equipment is completed, the equipment loading/unloading entrance 16 of the reactor containment vessel 12 is closed to the lid 21.
The reactor containment vessel boundary is then closed again in preparation for restarting the reactor plant.

以上に述べたようにこの発明に係る原子炉施設
においては、原子炉格納容器の側壁にかつ原子炉
建物の運転操作床面に相当する位置に複数の機器
搬出入口を形成し、各機器搬出入口を密封可能な
蓋体で取外し可能に閉塞したから、原子炉運転中
は原子炉格納容器バウンダリを形成する一方、原
子炉運転停止時に実施する燃料交換作業、原子炉
機器の定期検査作業の機器搬出入取扱作業を、蓋
体を取外すことにより、各機器搬出入口を通じて
スムーズにかつ有効的に短時間で行なうことがで
き、原子炉プラントの運転稼動率を向上させるこ
とができる。
As described above, in the nuclear reactor facility according to the present invention, a plurality of equipment loading/unloading entrances are formed in the side wall of the reactor containment vessel and at positions corresponding to the operation floor surface of the reactor building, and each equipment loading/unloading entrance Since it is removably closed with a sealable lid, it forms the reactor containment vessel boundary during reactor operation, while also being used for equipment removal during refueling work and periodic inspection of reactor equipment when the reactor is shut down. By removing the lid, the loading and handling work can be carried out smoothly and effectively in a short time through each equipment loading/unloading entrance, and the operating efficiency of the nuclear reactor plant can be improved.

また、原子炉プラントの建設時には、原子炉格
納容器の各機器搬出入口を建設資材や原子炉機器
の搬出入ルートとして利用できるので、仮設の搬
入口を形成する必要がなく、原子炉プラント建設
期間の短縮化を図ることができ、建設コストの低
減を図ることができる。
In addition, during the construction of a nuclear reactor plant, the equipment entrances and exits of the reactor containment vessel can be used as transport routes for construction materials and reactor equipment, so there is no need to create temporary entrances, and during the construction period of the reactor plant. It is possible to shorten the construction period and reduce construction costs.

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

第1図はこの発明に係る原子炉施設を示す平面
図、第2図は第1図の−線に沿う断面図、第
3図は第2図に示された原子炉施設のB部の拡大
図である。 10……原子炉施設、11……基礎マツト、1
2……原子炉格納容器、13……原子炉建物、1
6……機器搬出入口、18……機器搬出入路、2
0……筒状体、21……蓋体、22,23……フ
ランジ、25……シーリング部材。
FIG. 1 is a plan view showing a nuclear reactor facility according to the present invention, FIG. 2 is a sectional view taken along the - line in FIG. 1, and FIG. 3 is an enlarged view of section B of the nuclear reactor facility shown in FIG. 2. It is a diagram. 10... Nuclear reactor facility, 11... Basic mats, 1
2...Reactor containment vessel, 13...Reactor building, 1
6...Equipment carry-in/out entrance, 18...Equipment carry-in/out entrance, 2
0... Cylindrical body, 21... Lid, 22, 23... Flange, 25... Sealing member.

Claims (1)

【特許請求の範囲】 1 原子炉格納容器内に、原子炉圧力容器を有す
る原子炉建物を収容し、この原子炉建物の上面を
運転操作床面とした原子炉施設において、上記原
子炉格納容器の側壁であつてかつ上記運転操作床
面に相当する位置に複数の機器搬送入口を形成
し、この機器搬出入口によつて建屋外に開口した
搬出入路と上記原子炉格納容器内とを連通し、各
機器搬出入口を密閉可能な蓋体で取外し可能に閉
塞したことを特徴とする原子炉施設。 2 各機器搬出入口は、原子炉格納容器の側壁
に、周方向に互いに離間するように独立して形成
された特許請求の範囲第1項に記載の原子炉施
設。 3 各機器搬出入口は原子炉格納容器の側壁に溶
接等により固着された筒状体により形成され、こ
の筒状体の一端に蓋体が取外し可能に取付けられ
た特許請求の範囲第1項に記載の原子炉施設。
[Scope of Claims] 1. In a nuclear reactor facility in which a reactor building having a reactor pressure vessel is housed in a reactor containment vessel, and the top surface of this reactor building is used as an operation floor, the above-mentioned reactor containment vessel A plurality of equipment transport entrances are formed in the side wall of the building and at positions corresponding to the operation floor surface, and these equipment transport entrances communicate the transport passageway opened to the outside of the building with the inside of the reactor containment vessel. A nuclear reactor facility characterized in that each equipment loading/unloading port is removably closed with a sealable lid. 2. The nuclear reactor facility according to claim 1, wherein each equipment loading/unloading port is formed independently in the side wall of the reactor containment vessel so as to be spaced apart from each other in the circumferential direction. 3. According to claim 1, each equipment loading/unloading port is formed by a cylindrical body fixed to the side wall of the reactor containment vessel by welding or the like, and a lid body is removably attached to one end of the cylindrical body. Nuclear reactor facility listed.
JP56113128A 1981-07-20 1981-07-20 Nuclear reactor facility Granted JPS5814087A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP56113128A JPS5814087A (en) 1981-07-20 1981-07-20 Nuclear reactor facility

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP56113128A JPS5814087A (en) 1981-07-20 1981-07-20 Nuclear reactor facility

Publications (2)

Publication Number Publication Date
JPS5814087A JPS5814087A (en) 1983-01-26
JPS6328271B2 true JPS6328271B2 (en) 1988-06-07

Family

ID=14604243

Family Applications (1)

Application Number Title Priority Date Filing Date
JP56113128A Granted JPS5814087A (en) 1981-07-20 1981-07-20 Nuclear reactor facility

Country Status (1)

Country Link
JP (1) JPS5814087A (en)

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS59206795A (en) * 1983-05-11 1984-11-22 株式会社日立製作所 Reactor building
JP2000168334A (en) 1998-12-01 2000-06-20 Sanden Corp Intake unit of air conditioner for vehicle
JP6541020B2 (en) * 2014-12-17 2019-07-10 株式会社Ihi Fuel debris recovery method and recovery apparatus

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5587092A (en) * 1978-12-26 1980-07-01 Tokyo Shibaura Electric Co Reactor containment vessel

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5587092A (en) * 1978-12-26 1980-07-01 Tokyo Shibaura Electric Co Reactor containment vessel

Also Published As

Publication number Publication date
JPS5814087A (en) 1983-01-26

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