JPS62896A - reactor containment vessel - Google Patents
reactor containment vesselInfo
- Publication number
- JPS62896A JPS62896A JP60139987A JP13998785A JPS62896A JP S62896 A JPS62896 A JP S62896A JP 60139987 A JP60139987 A JP 60139987A JP 13998785 A JP13998785 A JP 13998785A JP S62896 A JPS62896 A JP S62896A
- Authority
- JP
- Japan
- Prior art keywords
- main steam
- isolation valve
- containment vessel
- equipment
- reactor containment
- 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
- 238000002955 isolation Methods 0.000 claims description 42
- 238000005192 partition Methods 0.000 claims description 2
- 238000007689 inspection Methods 0.000 description 10
- 230000000694 effects Effects 0.000 description 2
- 230000000737 periodic effect Effects 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- 238000009835 boiling Methods 0.000 description 1
- 239000004570 mortar (masonry) Substances 0.000 description 1
- 230000005855 radiation Effects 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
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j
本発明は主蒸気配管系における主蒸気隔離弁の上部機構
等の機器搬出入時の作業性を考慮した原子炉格納容器に
関するものである。DETAILED DESCRIPTION OF THE INVENTION [Field of Industrial Application] The present invention relates to a reactor containment vessel that takes into account workability during the loading and unloading of equipment such as the upper mechanism of a main steam isolation valve in a main steam piping system.
「従来技術」
原子力発電プラントにおける原子炉格納容器には、各種
の工学安全施設が設置されている。第3図に示す沸騰水
型軽水炉の原子炉格納容器の例で本スルーMLJSW力
來製1がN紬六れていX−ライウェル2と、該ドライウ
ェル2から主蒸気配管3を外部タービン室等へ導くため
の主蒸気配管用トンネル5とに主蒸気隔離弁6が配設さ
れて、原子炉冷却材の喪失事故時や原子炉格納容器の外
での主蒸気配管破断事故時等に、主蒸気を遮断して主蒸
気が外部へ直接漏れないようにしている。また、主蒸気
隔離弁6は、原子力発電プラントの定期点検時に、弁本
体を分解して各機能を点検した後、再組立を行っている
。このため、原子炉格納容器には、例えば、第4図に示
すように、本発明 □者等が特願昭59−085
920号において先に提案した主蒸気隔離弁の分解組立
装R7や、解体時に弁箱から取り出された上部機構8を
目的とする場所まで搬送するため等の迂回機器搬送路1
4、原子炉格納容器の側壁を貫通する機器振出人ハツチ
15等が設置されている。"Prior Art" Various engineering safety facilities are installed in the reactor containment vessel in a nuclear power plant. In the example of the reactor containment vessel of a boiling water type light water reactor shown in Fig. 3, this through MLJSW 1 made in Japan is connected to the A main steam isolation valve 6 is installed in the main steam piping tunnel 5 to lead the main steam piping to the main steam pipe. Steam is shut off to prevent main steam from leaking directly to the outside. Further, the main steam isolation valve 6 is reassembled after disassembling the valve body and inspecting each function during regular inspections of the nuclear power plant. For this reason, the reactor containment vessel, for example, as shown in FIG.
Detour equipment transport path 1 for transporting the main steam isolation valve disassembly and assembly equipment R7 previously proposed in No. 920, and the upper mechanism 8 taken out from the valve box during disassembly to the intended location.
4. An equipment drawer hatch 15 etc. that penetrates the side wall of the reactor containment vessel is installed.
前記主蒸気隔離弁6の点検作業について、第3図に基づ
き説明すると、通常の場合は、ドライウェル2の中の主
蒸気隔離弁6を先に解体し、その後、主蒸気配管用トン
ネル5の中に位置している主蒸気隔離弁6を解体するス
ケジュールが採用される。つまり、第4図の分解組立装
置t7により主蒸気隔離弁6を分解して、その上部機構
8を迂回機器搬送路14により矢印(イ)(ロ)で示す
ように機器振出人ハツチI5まで円周方向に沿って搬送
し、該機器振出人ハツチ15から原子炉格納容器の外に
矢印(ハ)で示すように引き出して、さらに主蒸気隔離
弁用ラッピング室まで搬送して、所要の点検等が実施さ
れる。次いで、主蒸気配管用トンネル5の内部に位置し
ている上部機構8をトンネル側壁13の貫通部を経由す
る直線状の外側搬送路9によ、す、主蒸気配管用トンネ
ル5の外に引き出して、主蒸気隔離弁用ラッピング室ま
で搬送し、同様の点検を実施するのである。The inspection work for the main steam isolation valve 6 will be explained based on FIG. A schedule is adopted for dismantling the main steam isolation valve 6 located inside. That is, the main steam isolation valve 6 is disassembled by the disassembly and assembling device t7 shown in FIG. The equipment is transported along the circumferential direction, pulled out from the equipment drawer hatch 15 to the outside of the reactor containment vessel as shown by the arrow (c), and further transported to the main steam isolation valve wrapping room for necessary inspection, etc. will be implemented. Next, the upper mechanism 8 located inside the main steam piping tunnel 5 is pulled out of the main steam piping tunnel 5 through the linear outer conveyance path 9 passing through the tunnel side wall 13. Then, it is transported to the wrapping room for the main steam isolation valve, and the same inspection is carried out.
「発明が解決しようとする問題点」
しかしながら、このような主蒸気隔離弁の搬送を行なう
場合、次のような問題点が生じる。"Problems to be Solved by the Invention" However, when transporting such a main steam isolation valve, the following problems occur.
■機器搬出人ハツチは主蒸気隔離弁の搬送とともに、他
の多くの機器の搬出入に使用されるので、他の機器の搬
出入とのスケジュール調整が必要となり、相互干渉が生
じ易い。■Equipment unloader hatches are used for transporting the main steam isolation valve as well as for loading and unloading many other pieces of equipment, so it is necessary to coordinate schedules with loading and unloading of other equipment, and mutual interference is likely to occur.
■主蒸気隔離弁の搬送路と機器振出人ハツチの床レベル
とが必ずしも一致せず、機器振出人ハツチ前後のレベル
調整のために、仮設ビーム台車等を準備する作業等が必
要となる。■The conveyance path of the main steam isolation valve and the floor level of the equipment dispenser hatch do not necessarily match, and it is necessary to prepare a temporary beam truck, etc. to adjust the level before and after the equipment dispenser hatch.
■前記床レベルの相異により、機器振出人ハツチの前後
で例えばジブクレーン式モル−ル等によ゛り吊り替え作
業が発生する。(2) Due to the difference in floor level, it is necessary to rehang the equipment before and after the equipment drawer hatch using, for example, a jib crane type mortar.
■他の機器と共用される機器振出人ハツチを使用してい
るため、主蒸気隔離弁の搬送路が迂回し、作業性の低下
を招く。■Since a device drawer hatch is used that is shared with other devices, the main steam isolation valve conveyance path is detoured, resulting in a decrease in work efficiency.
■主蒸気隔離弁の上部機構を主蒸気隔離弁用ラッピング
室まで搬送する際に、原子炉格納容器の内部と主蒸気隔
離弁用トンネルとから引き出すための2つのルートが必
要である。■When transporting the main steam isolation valve upper mechanism to the main steam isolation valve wrapping room, two routes are required: one from the inside of the reactor containment vessel and the other from the main steam isolation valve tunnel.
本発明はこのような問題点を有効に解決するとともに、
定期検査時における主蒸気隔離弁及び他の機器の点検作
業性を向上させ、作業員の放射線被曝の低減を図ること
の可能な原子炉格納容器を提供することを目的とするも
のである。The present invention effectively solves these problems, and also
The purpose of the present invention is to provide a reactor containment vessel that can improve the efficiency of inspecting main steam isolation valves and other equipment during periodic inspections and reduce radiation exposure of workers.
「問題点を解決するための手段j
このような目的を達成するために、本発明は、ドライウ
ェルと主蒸気配管用トンネルとにそれぞれ主蒸気隔離弁
を配設するとともに、前記ドライウェルと主蒸気配管用
トンネルとを区画している容器側壁に、短絡搬送路を形
成する機器搬送用ハツチを設けることにより、原子炉格
納容器の中で解体された上部機構を主蒸気配管用トンネ
ルに導いて、その部分の上部機構と共通の搬送路により
、目的とするラッピング室等と最短距離で接続するよう
にしたものである。``Means for Solving the Problems j'' In order to achieve such an object, the present invention provides a main steam isolation valve in each of the dry well and the main steam piping tunnel, and also provides a connection between the dry well and the main steam piping tunnel. By providing an equipment transport hatch that forms a short-circuit transport path on the side wall of the vessel that separates it from the steam piping tunnel, the upper mechanism disassembled inside the reactor containment vessel can be guided to the main steam piping tunnel. , through a common conveyance path with the upper mechanism of that part, it is connected to the intended wrapping chamber or the like over the shortest distance.
「実施例」
以下、本発明の原子炉格納容器の一実施例を第1図及び
第2図に基づいて説明する。"Example" Hereinafter, an example of the reactor containment vessel of the present invention will be described based on FIGS. 1 and 2.
該−実施例においても、第1図及び第2図に示すように
、原子炉圧力容器lからドライウェル2の中を通って敷
設されている主蒸気配管3は、容器側壁4を貫通して主
蒸気配管用トンネル5に導かれ、外部のタービン室等へ
接続されている点、容器側壁4の内外の近接位置に主蒸
気隔離弁6がそれぞれ4基ずつ、計8基配設されている
点、主蒸気隔離弁6の近傍に分解組立装置7が設置され
ている点、主蒸気配管用トンネル5の中の主蒸気隔離弁
6の上部機構8を主蒸気隔離弁用ラッピング室まで搬送
するための外側搬送路9が設けられている点等について
は、第3図及び第4図の従来の原子炉格納容器の例と共
通するものであるが、次の点において大きく相異するも
のである。Also in this embodiment, as shown in FIGS. 1 and 2, the main steam pipe 3, which is laid from the reactor pressure vessel l through the dry well 2, penetrates the vessel side wall 4. A total of eight main steam isolation valves 6, four each, are installed at points leading to the main steam piping tunnel 5 and connected to an external turbine room, etc., and at positions close to the inside and outside of the vessel side wall 4. The point is that the disassembly and assembly device 7 is installed near the main steam isolation valve 6, and the upper mechanism 8 of the main steam isolation valve 6 in the main steam piping tunnel 5 is transported to the main steam isolation valve wrapping room. Although it is similar to the conventional reactor containment vessel examples shown in Figures 3 and 4 in that it is provided with an outer conveyance path 9 for transport, it differs greatly in the following points. be.
即ち、主蒸気隔離弁6の′上部機構8を運搬するための
内側搬送路10が、第3図例の迂回機器搬送路14と比
較して第1図に示すように直線状で短く、原子炉格納容
器の中を円周方向に沿う部分が省略されており、また、
内側搬送路10と外側搬送路9との間の容器側壁4に、
機器搬送用ハツチ11が設けられて、該機器搬送用ハツ
チ11を経由する直線状の短絡搬送路12を形成する構
造である。また、短絡搬送路12は、第2図に示すよう
に内外の主蒸気隔離弁6の高さのレベルが通常同レベル
もあるため、その側部位置を水平にかつ直交状態に連結
している。なお、図中符号13はトンネル側壁である。That is, the inner conveying path 10 for conveying the upper mechanism 8 of the main steam isolation valve 6 is straight and short as shown in FIG. The part along the circumference inside the reactor containment vessel is omitted, and
On the container side wall 4 between the inner conveyance path 10 and the outer conveyance path 9,
It has a structure in which a hatch 11 for transporting equipment is provided, and a linear short-circuit transport path 12 passing through the hatch 11 for transporting equipment is formed. Furthermore, as shown in FIG. 2, the heights of the inner and outer main steam isolation valves 6 are usually at the same level, so the short-circuit conveyance path 12 connects their side positions horizontally and orthogonally. . In addition, the code|symbol 13 in the figure is a tunnel side wall.
このように構成されている原子炉格納容器であると、原
子炉の運転時には機器搬送用ハツチIIを閉塞して、ド
ライウェル2と主蒸気配管用トンネル5との気密性を確
保しておくことは勿論であるが、原子炉運転開始後の定
期点検時には、機器搬送用ハツチl!を開放することに
より、この部分から作業員の出入り及び主蒸気隔離弁6
の上部機構8の搬出入を自由に行ない得ることになる。If the reactor containment vessel is configured in this way, the equipment transport hatch II must be closed during reactor operation to ensure airtightness between the dry well 2 and the main steam piping tunnel 5. Of course, during periodic inspections after the start of reactor operation, hatches for transporting equipment must be used! By opening the main steam isolation valve 6, workers can enter and exit the main steam isolation valve from this part.
The upper mechanism 8 can be carried in and out freely.
この場合、容器側壁4の内方に位置している主蒸気隔離
弁6を先に解体し、その後、主蒸気配管用トンネル5の
中に位置している主蒸気隔離弁6を解体するスケジュー
ルを採用したとしても、主蒸気隔離弁6の分解・点検作
業が、他の機器と相互′干渉を生じることがない。つま
り、第4図例の分解組立装置7により、内側に位置して
いる主蒸気隔離弁6を分解して、その上部機構8を内側
搬送路9により、矢印(A)で示すように僅かにずらし
た後、機器搬送用ハツチ!1を経由する短絡搬送路I2
により外側搬送路9に矢印(B)のように合流させ、さ
らに主蒸気隔離弁用ラッピング室まで搬送して、所要の
点検等を実施するものである。In this case, the schedule is to first dismantle the main steam isolation valve 6 located inside the vessel side wall 4, and then dismantle the main steam isolation valve 6 located in the main steam piping tunnel 5. Even if adopted, the disassembly and inspection work of the main steam isolation valve 6 will not cause mutual interference with other equipment. That is, the main steam isolation valve 6 located on the inside is disassembled by the disassembly and assembly device 7 shown in FIG. After shifting, use the hatch for transporting equipment! Short-circuit conveyance path I2 via 1
Then, it joins the outer conveyance path 9 as shown by the arrow (B), and is further conveyed to the wrapping chamber for the main steam isolation valve, where necessary inspections and the like are carried out.
したがって、原子炉格納容器の内側の上部機構8の搬送
距離は、主蒸気隔離弁6の側部から主蒸気配管3と平行
に移動させるわずかなものとなり、原子゛炉格納容器内
の他の機器の点検作業等と独立した状態で実施すること
が可能である。また、主蒸気配管用トンネル5の内部に
位置している上部機構8との間においても、主蒸気隔離
弁6の側部相互間で搬送が行なわれるので、他の部分と
の干渉が生じることを少なくすることができる。Therefore, the transport distance of the upper mechanism 8 inside the reactor containment vessel is a short distance from the side of the main steam isolation valve 6 in parallel to the main steam pipe 3, and other equipment inside the reactor containment vessel is moved. This can be carried out independently from inspection work, etc. Furthermore, since the main steam isolation valve 6 is transferred between the sides of the main steam isolation valve 6 and the upper mechanism 8 located inside the main steam piping tunnel 5, interference with other parts may occur. can be reduced.
「発明の効果」
以上説明したように本発明の原子炉格納容器は、ドライ
ウェルと主蒸気配管用トンネルとを区画している容器側
壁に、機器搬送用ハツチを設けて短絡搬送路を形成する
ようにしたものであるから、次のような優れた効果を奏
することができる。"Effects of the Invention" As explained above, the reactor containment vessel of the present invention is provided with a hatch for transporting equipment on the side wall of the container that partitions the dry well and the main steam piping tunnel to form a short-circuit transport path. As a result, the following excellent effects can be achieved.
(a)容器側壁内外の主蒸気隔離弁の上部機構の搬送路
が最短距離で接続されて、原子炉格納容器内における主
蒸気隔離弁の上部機構の搬送路が主蒸気隔離弁の側部付
近のみに限定されるので、他の機器の搬出入との相互干
渉を生じることがない。(a) The conveyance path of the upper mechanism of the main steam isolation valve inside and outside the vessel side wall is connected by the shortest distance, and the conveyance path of the upper mechanism of the main steam isolation valve inside the reactor containment vessel is near the side of the main steam isolation valve. There is no possibility of mutual interference with the loading and unloading of other equipment.
(b)内外の主蒸気隔離弁の高さのレベルが同じであれ
ば、容器側壁内外でレベル差を生じることがなく、台車
等の構造が簡単になる。(b) If the height levels of the inner and outer main steam isolation valves are the same, there will be no difference in level between the inner and outer side walls of the container, and the structure of the truck etc. will be simplified.
(c)機器の搬送路を直線あるいは直線の組み合わせと
することが容易になり、搬送路及びその付属機器の単純
化を図ることができる。(c) It becomes easy to make the equipment transport path a straight line or a combination of straight lines, and the transport path and its auxiliary equipment can be simplified.
(d)主蒸気隔離弁の搬送路が原子炉格納容器の中を迂
回しないため、各点検作業の相互干渉等により作業性が
低下することが少ない。(d) Since the conveyance path of the main steam isolation valve does not detour through the reactor containment vessel, work efficiency is less likely to be degraded due to mutual interference between inspection operations.
(e)内外の搬送路を短絡搬送路で連結しているため、
搬送ルートを単純化することができる。(e) Since the inner and outer conveyance paths are connected by a short-circuit conveyance path,
The transportation route can be simplified.
(f)ドライウェルと主蒸気配管用トンネルと、は、主
蒸気配管を収容している類似バウンダリとなっているた
め、容器側壁を貫通及び閉塞する機器搬送用ハツチの構
造を簡単にすることができる。(f) Since the dry well and the main steam piping tunnel have similar boundaries that accommodate the main steam piping, it is possible to simplify the structure of the hatch for transporting equipment that penetrates and closes the side wall of the container. can.
(g)作業性の向上が著しいため、作業員の放射線旨0
!I^kc−す、邊−ネプψし上I−セプ(g) Due to the remarkable improvement in work efficiency, there is no radiation risk for workers.
! I^kc-su、邊-nepψshi上I-sepu
第1図及び第2図は本発明の原子炉格納容器の一実施例
を示すもので、第1図は一部を省略した平面図、第2図
は一部を断面した正面図、第3図は原子炉格納容器の従
来例を示す一部を省略した平面図、第4図は主蒸気隔離
弁の分解組立装置の例を示す斜視図である。
1・・・・・・原子炉圧力容器、2・・・・・・ドライ
ウェル、3・・・・・・主蒸気配管、4・・・・・・容
器側壁、5・・・・・・主蒸気配管用トンネル、6・・
・・・・主蒸気隔離弁、7・・・・・・分解組立装置、
8・・・・・・上部機構、9・・・・・・外側搬送路、
lO・・・・・・内側搬送路、11・・・・・・機器搬
送用ハツチ、12・・・・・・短絡搬送路、I3・・・
・・・トンネル側壁。Figures 1 and 2 show an embodiment of the reactor containment vessel of the present invention. Figure 1 is a partially omitted plan view, Figure 2 is a partially sectional front view, and Figure 3 is a partially cutaway front view. The figure is a partially omitted plan view showing a conventional example of a nuclear reactor containment vessel, and FIG. 4 is a perspective view showing an example of a main steam isolation valve disassembly and assembly device. 1... Reactor pressure vessel, 2... Drywell, 3... Main steam piping, 4... Vessel side wall, 5... Main steam piping tunnel, 6...
...Main steam isolation valve, 7...Disassembly and assembly equipment,
8... Upper mechanism, 9... Outer conveyance path,
IO...Inner conveyance path, 11...Equipment conveyance hatch, 12...Short-circuit conveyance path, I3...
...Tunnel side wall.
Claims (1)
気隔離弁を配設するとともに、前記ドライウェルと主蒸
気配管用トンネルとを区画している容器側壁に、短絡搬
送路を形成する機器搬送用ハッチを設けたことを特徴と
する原子炉格納容器。A main steam isolation valve is provided in each of the dry well and the main steam piping tunnel, and an equipment transport hatch forms a short-circuit transport path on the side wall of the container that partitions the dry well and the main steam piping tunnel. A nuclear reactor containment vessel characterized by being provided with.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60139987A JPS62896A (en) | 1985-06-26 | 1985-06-26 | reactor containment vessel |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60139987A JPS62896A (en) | 1985-06-26 | 1985-06-26 | reactor containment vessel |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS62896A true JPS62896A (en) | 1987-01-06 |
Family
ID=15258299
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP60139987A Pending JPS62896A (en) | 1985-06-26 | 1985-06-26 | reactor containment vessel |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS62896A (en) |
-
1985
- 1985-06-26 JP JP60139987A patent/JPS62896A/en active Pending
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