JPH0159555B2 - - Google Patents
Info
- Publication number
- JPH0159555B2 JPH0159555B2 JP56005957A JP595781A JPH0159555B2 JP H0159555 B2 JPH0159555 B2 JP H0159555B2 JP 56005957 A JP56005957 A JP 56005957A JP 595781 A JP595781 A JP 595781A JP H0159555 B2 JPH0159555 B2 JP H0159555B2
- Authority
- JP
- Japan
- Prior art keywords
- lid
- drive device
- duct
- control rod
- 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.)
- Expired
Links
- 238000001816 cooling Methods 0.000 claims description 13
- 229910000831 Steel Inorganic materials 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- 230000000737 periodic effect Effects 0.000 description 1
- 230000002093 peripheral effect Effects 0.000 description 1
- 230000001681 protective effect Effects 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 239000011150 reinforced concrete Substances 0.000 description 1
- 238000000926 separation method Methods 0.000 description 1
- 239000010959 steel Substances 0.000 description 1
- 238000009423 ventilation Methods 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 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
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Description
【発明の詳細な説明】
本発明は軽水冷却型原子炉の改良に係るもので
ある。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to improvements in light water cooled nuclear reactors.
従来この種の原子炉においては、格納容器内の
空所に支持されるとともに、炉心構造部の内蔵さ
れた原子炉容器の上端開口部に締結された蓋上
に、同蓋を貫設して垂直に延びる多数の制御棒駆
動装置が林立されており、前記蓋上には前記駆動
装置を囲繞して、同蓋とは別個に製作された前記
駆動装置冷却用のリング状ダクトが配設されると
ともに、前記各駆動装置を支持する耐震サポート
と格納容器内の空所との間にタイロツドが配設さ
れ、前記制御棒駆動装置が熱及び地震力に対して
保護されている。 Conventionally, in this type of nuclear reactor, the lid is supported in a space within the containment vessel and is attached to a lid that is fastened to the upper opening of the reactor vessel in which the core structure is built. A large number of vertically extending control rod drive devices are arranged in a row, and a ring-shaped duct for cooling the drive devices is provided on the lid to surround the drive devices and is manufactured separately from the lid. In addition, tie rods are disposed between seismic supports supporting each of the drive units and cavities within the containment vessel to protect the control rod drives against heat and seismic forces.
而して前記原子炉容器の蓋は燃料交換及び定期
検査のために毎年開放される。この蓋解放作業
は、同蓋の原子炉容器に対する締結用スタツドボ
ルトの緩脱、及び格納器内固定床との連結部材の
切離しによつて行なわれるものであるが、前記制
御棒駆動装置冷却用ダクトが前記スタツドボルト
の近くに位置するため、先ずリング状ダクトの分
解から始めなくてはならない。更にまた従来は分
解式ケーブルトレイを使用しているので、先ずケ
ーブルを巻取り、次いでケーブルトレイを移動さ
せており、この作業が危険な頭上作業となるため
に、この間前記ダクトの分解作業が行なわれず、
手待ち時間が著しく増大する。更にまた前記耐震
サポート支持用のタイロツドの取外し作業が足場
が悪く重量物を取扱う危険な作業を伴ない、更に
前記蓋上の作業では、所要時間の延引と相俟つ
て、放射線の被爆量が増大するものである。 Thus, the reactor vessel lid is opened annually for fuel changes and periodic inspections. This lid release work is performed by loosening and loosening the stud bolts for fastening the lid to the reactor vessel, and by disconnecting the connecting member from the fixed bed inside the containment vessel. Since the duct is located close to the stud bolt, one must first begin by disassembling the ring-shaped duct. Furthermore, since conventionally a disassembleable cable tray is used, the cables are first wound up and then the cable tray is moved, which is dangerous overhead work, so the duct must be disassembled during this time. No,
Waiting time increases significantly. Furthermore, the removal work of the tie rods for supporting the seismic support involves dangerous work involving handling heavy objects due to poor footing, and furthermore, the work on the lid increases the amount of radiation exposure as the required time increases. It is something to do.
更にまた前記従来のものにおいては、蓋開放時
に耐震サポートを支持するタイロツドが分解され
るため、耐震サポートが不安定となり、原子炉運
転再開のため蓋を旧位に復したときの各部分の再
調整を行なわねばならず、この調整作業がまた頗
る困難である。 Furthermore, in the conventional system mentioned above, the tie rods that support the seismic support are disassembled when the lid is opened, making the seismic support unstable and making it difficult to rebuild each part when the lid is returned to its previous position in order to resume reactor operation. Adjustments must be made, and this adjustment work is also extremely difficult.
本発明はこのような欠点を除去するために提案
されたものであつて、格納容器内の空所に支持さ
れるとともに炉心構造部の内蔵された原子炉容
器、同容器の上端開口部に締結された蓋、同蓋を
貫通して鉛直方向に延びる制御棒駆動装置、同駆
動装置を囲繞して前記蓋上にこれと一体に立設さ
れた二重円筒状の制御棒駆動装置冷却用ダクト、
及び同ダクトの内側に配設され前記駆動装置を水
平方向に支持する耐震部材より構成されたことを
特徴とする軽水冷却型原子炉に係るものである。 The present invention has been proposed in order to eliminate such drawbacks, and includes a reactor vessel that is supported in a space within the containment vessel and has a core structure built therein, and a reactor vessel that is fastened to the upper end opening of the vessel. a control rod drive device that extends vertically through the cover, and a double cylindrical control rod drive cooling duct that surrounds the drive device and is erected integrally with the control rod drive device on the cover. ,
The present invention relates to a light water-cooled nuclear reactor, characterized in that the light water-cooled nuclear reactor is constructed of an earthquake-resistant member disposed inside the duct and horizontally supporting the drive device.
本発明においては前記したように原子炉容器の
蓋上に、これと一体に立設され且つ同蓋上に垂直
に延びる制御棒駆動装置を囲繞する同駆動装置の
冷却用ダクトが二重円筒状に形成されているの
で、同ダクトの強度、剛性が大であつて、前記制
御棒駆動装置の冷却用ダクトの機能を果すととも
に、同制御棒駆動装置の耐震サポートの用を果す
ものである。また前記ダクトの内側には前記制御
棒駆動装置を水平方向に支持する耐震部材が配設
されているので、同駆動装置にかかる地震水平力
は、前記耐震部材を介して前記ダクトに支持され
るものである。 In the present invention, as described above, the cooling duct for the control rod drive device, which surrounds the control rod drive device that is erected integrally with the lid of the reactor vessel and extends vertically on the lid, has a double cylindrical shape. Since the duct is formed as a duct, the duct has high strength and rigidity, and functions as a cooling duct for the control rod drive device as well as an earthquake-resistant support for the control rod drive device. Furthermore, an earthquake-resistant member that horizontally supports the control rod drive device is disposed inside the duct, so that the seismic horizontal force applied to the control rod drive device is supported by the duct via the earthquake-resistant member. It is something.
また本発明において前記ダクトが前記原子炉容
器蓋上にこれと一体的に立設された安定した構造
を有するので、蓋開放作業時における蓋の吊上
げ、移動によつても、同蓋上の機器、部材の相対
位置に狂いを生じることがなく、復旧後の位置調
整作業が一切不要となり、更に足場が悪く重量物
を取扱う前記従来のものにおける如き危険な制御
棒駆動装置の中間耐震支持用タイロツドの分離作
業が不要となる。また前記したように制御棒駆動
装置の冷却用ダクトと原子炉容器の蓋とが一体構
造となつているので、冷却用ダクトに対する接続
ダクト、或いは電源ケーブル等の切離しを要する
個所を、一体構造物である前記冷却用ダクトの上
部床に集約することにより、手待ち時間を殆んど
なくし、作業時間を短縮し、作業の安全性を向上
するとともに、作業員の放射線被爆量を低減しう
るものである等、本発明は多くの利点を有するも
のである。 In addition, in the present invention, since the duct has a stable structure that is erected integrally with the reactor vessel lid, even if the lid is lifted or moved during the lid opening operation, the equipment on the lid can be easily removed. , there is no deviation in the relative position of the members, there is no need for any position adjustment work after restoration, and the tie rod is for intermediate seismic support of the control rod drive device, which is dangerous like the conventional type mentioned above, which has poor footing and handles heavy objects. This eliminates the need for separation work. Furthermore, as mentioned above, since the cooling duct of the control rod drive device and the lid of the reactor vessel have an integral structure, the connection duct to the cooling duct or the point where the power cable needs to be disconnected can be connected to the integral structure. By concentrating the cooling ducts on the upper floor of the cooling duct, it is possible to almost eliminate waiting time, shorten working time, improve work safety, and reduce the amount of radiation exposure of workers. The present invention has many advantages.
以下本発明を図示の実施例について説明する。 The present invention will be described below with reference to the illustrated embodiments.
1は鉄筋コンクリート製格納容器2内の空所に
支持され且つ炉心構造部3の内蔵された原子炉容
器で、その上端開口部に原子炉容器蓋4がスタツ
ドボルト5を介して締結されている。 Reference numeral 1 denotes a reactor vessel which is supported in a space within a reinforced concrete containment vessel 2 and has a reactor core structure 3 built therein, and a reactor vessel lid 4 is fastened to its upper opening via stud bolts 5.
前記蓋4には複数のトラベルハウジング6が鉛
直方向に亘つて延びるように気密に貫通され、同
各ハウジング6に同ハウジング6及び原子炉容器
1内に亘つて昇降する制御棒7を制御する制御棒
駆動装置8が装架されている。 A plurality of travel housings 6 are hermetically penetrated through the lid 4 so as to extend vertically, and each housing 6 is provided with a control rod 7 that controls a control rod 7 that moves up and down within the housing 6 and the reactor vessel 1. A rod drive device 8 is mounted.
9は前記制御棒駆動装置8の冷却用ダクトで、
同心円周上に所定間隔毎に配設されたH型鋼等よ
り構成された支柱の内外両周面に内側壁板及び外
側壁板を張設した二重円筒状に形成され、その下
端部に所定間隔毎に突設されたブラケツトと、前
記蓋4上の対応位置に突設されたブラケツトとを
ピンで連結してなる連結部10を介して、蓋4上
にこれと一体に的に結合され、且つ同蓋4上に林
立する制御駆動装置8を囲繞するように立設され
ている。なお前記ダクト9にはその下部に冷却風
吸引用窓孔11が穿設され、その上部は外周に膨
出するリング状部9aに形成され、同部9aの上
部が作業床に形成されるとともに、外部ダクト1
2が連結され、且つ前記容器2の内壁との間に上
部耐震サポートタイロツド13が着脱自在に連結
されている。14,15は夫々耐震板で、前記ト
ラベルハウジング6の貫通部及び制御棒駆動装置
8の電源ケーブル16の貫通部並に冷却風通隙を
有する耐震板で、前記ダクト9の内側板に剛強に
固着された環状枠(図示せず)に接合され、前記
制御棒駆動装置8にかかる地震水平力を前記耐震
板14,15を介して前記ダクト9に支持するよ
うになつている。なお前記リング状部9aの下面
には前記蓋4を原子炉容器1に締結するスタツド
ボルト5を脱着するスタツドボルト緊解装置昇降
用ホイスト17とその環状ガイドレール18が取
付けられている。 9 is a cooling duct for the control rod drive device 8;
It is formed into a double cylindrical shape with an inner wall plate and an outer wall plate stretched on both the inner and outer peripheral surfaces of a support made of H-shaped steel etc. arranged at predetermined intervals on a concentric circumference, and a predetermined It is integrally connected to the lid 4 through a connecting portion 10 formed by connecting brackets protruding at intervals and brackets protruding at corresponding positions on the lid 4 with pins. , and are erected so as to surround the control drive device 8 standing on the lid 4. The duct 9 has a cooling air suction window 11 in its lower part, and its upper part is formed into a ring-shaped part 9a that bulges out to the outer periphery. , external duct 1
2 are connected to each other, and an upper seismic support tie rod 13 is detachably connected between the container 2 and the inner wall thereof. Reference numerals 14 and 15 are earthquake-resistant plates, respectively, which have passages for the travel housing 6 and the power cable 16 of the control rod drive device 8, as well as cooling air ventilation holes, and are rigidly attached to the inner plate of the duct 9. It is connected to a fixed annular frame (not shown), so that the seismic horizontal force applied to the control rod drive device 8 is supported by the duct 9 via the seismic plates 14 and 15. A hoist 17 for lifting and lowering the stud bolt tightening device for attaching and detaching the stud bolt 5 for fastening the lid 4 to the reactor vessel 1 and its annular guide rail 18 are attached to the lower surface of the ring-shaped portion 9a.
19は前記電源ケーブル16の接続端子をまと
めて支持する中間コネクタパネルで、第2図に示
すように前記ダクト9上または第3図に示すよう
に前記格納容器2の作業床上に配設されたケーブ
ルトレイ20に取付けられる。 Reference numeral 19 denotes an intermediate connector panel that collectively supports the connection terminals of the power cables 16, and is arranged on the duct 9 as shown in FIG. 2 or on the work floor of the containment vessel 2 as shown in FIG. It is attached to the cable tray 20.
同ケーブルトレイ20は前記作業床上に回動自
在に枢支21され前記蓋4の開放時、第4図に示
す如くケーブルトレイ20の先端に繋着したワイ
ヤロープ22を格納容器2の内壁に装着された滑
車23に架渡し、同ワイヤロープ22をウインチ
若しくは天井クレンによつて引上げるか、ケーブ
ルトレイ枢支部21の回転ピンの延長部を適当な
動力によつて回転させるようにしてもよい。なお
前記天井クレンはケーブルトレイの立上げの外
に、原子炉建屋内の重量物の吊上げ用に利用され
るので、ケーブルトレイのために余分な設備を設
ける必要がない。しかし同クレンを占有する時間
が問題となる場合、専用ウインチ等が使用される
ものである。 The cable tray 20 is rotatably supported 21 on the work floor, and when the lid 4 is opened, a wire rope 22 connected to the tip of the cable tray 20 is attached to the inner wall of the containment vessel 2 as shown in FIG. The wire rope 22 may be pulled up by a winch or an overhead crane, or the extension of the rotation pin of the cable tray pivot portion 21 may be rotated by an appropriate power. Note that since the ceiling crane is used not only for raising the cable tray but also for lifting heavy objects inside the reactor building, there is no need to provide extra equipment for the cable tray. However, if the time required to occupy the crane is a problem, a dedicated winch or the like is used.
また前記中間コネクタパネル19がダクト9側
に配設された場合は、接続端子の切離し作業はダ
クト上で、ケーブルトレイ20側に配設された場
合は同切離作業はトレイ側より行なわれるが、構
造物の安定性、及び落下の危険性を考慮した場
合、トレイ側に中間コネクタパネル19を配設し
た方が好ましい。しかしコネクタの形式、配置、
或いはケーブルの取扱いによつては必らずしもト
レイ側に設ける必要はない。 When the intermediate connector panel 19 is placed on the duct 9 side, the connection terminals are disconnected on the duct, and when the intermediate connector panel 19 is placed on the cable tray 20 side, the disconnection work is performed from the tray side. When considering the stability of the structure and the risk of falling, it is preferable to arrange the intermediate connector panel 19 on the tray side. However, the type and arrangement of the connector,
Alternatively, depending on how the cable is handled, it is not necessarily necessary to provide it on the tray side.
図示の実施例は前記のように構成されているの
で、前記外部ダクト12及びタイロツド7を取外
し、前記中間コネクタパネル19に対してコネク
タを切離して、ケーブルトレイ20を立上げると
ともに、前記蓋4の原子炉容器1に対するスタツ
ドボルト5の締結を解除して、蓋4を天井クレン
によつて引上げるものである。 Since the illustrated embodiment is constructed as described above, the external duct 12 and tie rod 7 are removed, the connector is separated from the intermediate connector panel 19, the cable tray 20 is raised, and the lid 4 is opened. The stud bolts 5 are unfastened to the reactor vessel 1, and the lid 4 is pulled up using a ceiling crane.
この際前記ダクト9及び耐震板14、15より
なる制御棒駆動装置8の保護装置が蓋4上に一体
構造物として取付けられているので、前記のよう
に外部ダクト或いは電源ケーブル等の切離しを要
する個所を前記ダクト9の上部床にまとめること
によつて作業時間を短縮し、また作業時の被爆放
射線量を低減しうるものである。 At this time, since the protection device for the control rod drive device 8 consisting of the duct 9 and seismic plates 14 and 15 is attached as an integral structure on the lid 4, it is necessary to disconnect the external duct or power cable as described above. By consolidating the parts on the upper floor of the duct 9, it is possible to shorten the working time and reduce the radiation dose during working.
また復旧作業は前記と逆の手順で行なわれる
が、前記保護装置が蓋上に剛な一体構造物として
取付けられているので、機器の相対移動が生起せ
ず、再調整作業が不要となる。 The restoration work is carried out in the reverse order, but since the protective device is mounted as a rigid integral structure on the lid, no relative movement of the equipment occurs and readjustment work is not necessary.
以上本発明を実施例について説明したが、本発
明は勿論このような実施例にだけ局限されるもの
ではなく、本発明の精神を逸脱しない範囲内で
種々の設計の改変を施しうるものである。 Although the present invention has been described above with reference to embodiments, the present invention is, of course, not limited to such embodiments, and can be modified in various ways without departing from the spirit of the present invention. .
第1図は本発明に係る軽水冷却型原子炉の一実
施例を示す縦断面図、第2図及び第3図は夫々ケ
ーブルトレイ及び中間コネクタパネルの取付部の
各実施例を示す側面図、第4図はケーブルトレイ
の立上げ部の側面図である。
1……原子炉容器、2……原子炉格納容器、3
……炉心構造部、4……蓋、5……スタツドボル
ト、8……制御棒駆動装置、9……制御棒駆動装
置冷却用ダクト、14,15……耐震板。
FIG. 1 is a longitudinal cross-sectional view showing one embodiment of a light water-cooled nuclear reactor according to the present invention, FIGS. 2 and 3 are side views showing respective embodiments of the mounting portion of the cable tray and the intermediate connector panel, FIG. 4 is a side view of the upright portion of the cable tray. 1...Reactor vessel, 2...Reactor containment vessel, 3
... Core structure section, 4 ... Lid, 5 ... Stud bolt, 8 ... Control rod drive device, 9 ... Control rod drive device cooling duct, 14, 15 ... Earthquake-resistant plate.
Claims (1)
構造部の内蔵された原子炉容器、同容器の上端開
口部に締結された蓋、同蓋を貫通して鉛直方向に
延びる制御棒駆動装置、同駆動装置を囲繞して前
記蓋上にこれと一体に立設された二重円筒状の制
御棒駆動装置冷却用ダクト、及び同ダクトの内側
に配設され前記駆動装置を水平方向に支持する耐
震部材より構成されたことを特徴とする軽水冷却
型原子炉。1. A reactor vessel supported in a space within the containment vessel and containing a reactor core structure, a lid fastened to the upper opening of the vessel, a control rod drive device extending vertically through the lid, A double cylindrical control rod drive device cooling duct surrounds the drive device and is erected integrally with it on the lid, and is disposed inside the duct to support the drive device in the horizontal direction. A light water-cooled nuclear reactor characterized by being constructed from earthquake-resistant materials.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56005957A JPS57120888A (en) | 1981-01-20 | 1981-01-20 | Light water cooled reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56005957A JPS57120888A (en) | 1981-01-20 | 1981-01-20 | Light water cooled reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS57120888A JPS57120888A (en) | 1982-07-28 |
| JPH0159555B2 true JPH0159555B2 (en) | 1989-12-18 |
Family
ID=11625365
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP56005957A Granted JPS57120888A (en) | 1981-01-20 | 1981-01-20 | Light water cooled reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS57120888A (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4828789A (en) * | 1984-02-03 | 1989-05-09 | Westinghouse Electric Corp. | Reactor vessel head permanent shield |
| JP2016077300A (en) * | 2014-10-09 | 2016-05-16 | 株式会社東芝 | Rotating body cable supply device and particle beam therapy device including the same |
-
1981
- 1981-01-20 JP JP56005957A patent/JPS57120888A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS57120888A (en) | 1982-07-28 |
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