JPH0329891A - Nuclear reactor shielding wall - Google Patents
Nuclear reactor shielding wallInfo
- Publication number
- JPH0329891A JPH0329891A JP1164002A JP16400289A JPH0329891A JP H0329891 A JPH0329891 A JP H0329891A JP 1164002 A JP1164002 A JP 1164002A JP 16400289 A JP16400289 A JP 16400289A JP H0329891 A JPH0329891 A JP H0329891A
- Authority
- JP
- Japan
- Prior art keywords
- wall
- reactor
- dry well
- piping
- nuclear reactor
- 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.)
- Granted
Links
- 230000005855 radiation Effects 0.000 abstract description 10
- 238000007689 inspection Methods 0.000 abstract description 9
- 239000003381 stabilizer Substances 0.000 abstract description 8
- 238000006073 displacement reaction Methods 0.000 abstract description 3
- 230000000149 penetrating effect Effects 0.000 abstract 1
- 230000000737 periodic effect Effects 0.000 description 6
- 230000004888 barrier function Effects 0.000 description 5
- 229910000831 Steel Inorganic materials 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 238000005516 engineering process Methods 0.000 description 2
- 230000035515 penetration Effects 0.000 description 2
- 238000010248 power generation Methods 0.000 description 2
- 239000010959 steel Substances 0.000 description 2
- 238000010586 diagram Methods 0.000 description 1
- 230000000630 rising effect 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
Description
【発明の詳細な説明】
〔産業」二の利用分野〕
本発明は、原子力発電設備の定期検査に際し、原子炉格
納容器ドライウェル内の放射線量を低減するのに好適な
原子炉じゃへい壁に関する。[Detailed Description of the Invention] [Field of Application in Industry] The present invention relates to a reactor barrier wall suitable for reducing the radiation dose in the reactor containment vessel dry well during periodic inspections of nuclear power generation equipment. .
従来の原子炉じゃへい壁を第２図の原子炉格納容器の縦
断図を用いて説明する。A conventional reactor barrier wall will be explained using the vertical cross-sectional view of the reactor containment vessel shown in FIG. 2.
図において、１は原子炉圧力容器、２はドライウェル、
３はサブレツションチェンバ、４はシールドウオール、
５は原子炉本体の基礎、６は原子炉じゃへい壁、７は主
蒸気配管、８はスタビライザである。In the figure, 1 is the reactor pressure vessel, 2 is the dry well,
3 is the subrection chamber, 4 is the shield wall,
5 is the foundation of the reactor body, 6 is the reactor wall, 7 is the main steam piping, and 8 is the stabilizer.
原子炉圧力容器工はドライウェル２の内部に設置され、
原子炉本体の基礎５に支持されている。Reactor pressure vessel engineering is installed inside Drywell 2,
It is supported by the foundation 5 of the reactor body.
定期検査時等においては、ドライウェル２の内部に作業
員が入るため、原子炉圧力容器↓からの放射線を防御し
、線量を低減させることが必要となる。このため、原子
炉圧力容器１の周囲に原子炉じゃへいＩｉ６を設けてい
る。原子炉じゃへい（ｉ％ Ｇは、鋼板とコンクリート
から或る円筒型の構造物であり、下端を原子炉本体の基
礎５に埋設されている。また、原子炉じゃへい壁６の上
端には、原子炉圧力容器１と原子炉じゃへい壁６の地震
時の相対変位を低減するために、スタビライザ８が設け
られている。スタビライザ８は、水平方向の地震荷重に
対してのみ有効に働き、鉛直方向については、運転時に
原子炉圧力容器工が高温になり熱移動するため、この変
形を妨げないよう、原子炉圧力容器１に取り付けられて
いるブラケツ１−との間にギャップを設けている。During periodic inspections, etc., workers enter the inside of the dry well 2, so it is necessary to protect them from radiation from the reactor pressure vessel ↓ and reduce the dose. For this reason, a reactor jacket Ii6 is provided around the reactor pressure vessel 1. The reactor wall (i%G) is a cylindrical structure made of steel plates and concrete, and its lower end is buried in the foundation 5 of the reactor body.In addition, the upper end of the reactor wall 6 is , a stabilizer 8 is provided in order to reduce the relative displacement between the reactor pressure vessel 1 and the reactor shielding wall 6 during an earthquake.The stabilizer 8 works effectively only against earthquake loads in the horizontal direction. In the vertical direction, a gap is provided between the reactor pressure vessel and the bracket 1- attached to the reactor pressure vessel 1 to prevent this deformation from occurring as the reactor pressure vessel heats up and transfers heat during operation. .
スタビライザより上方には原子炉圧力容器１に接続され
ている主蒸気配管７がある。主蒸気配管７は、原子炉圧
力容器から発生する蒸気をタービンに導く役割りを果し
ており，ドライウェル２を貫通している。Above the stabilizer is a main steam pipe 7 connected to the reactor pressure vessel 1. The main steam pipe 7 serves to guide steam generated from the reactor pressure vessel to the turbine, and penetrates the dry well 2 .
なお、この種の装置として関連するものには、例えば、
特開昭５７ − ８０５９６号公報が挙げられる。Note that related devices of this type include, for example,
JP-A-57-80596 is mentioned.
上記従来技術は、原子炉格納容器ドライウェル２の上部
では放射線量が下部に比べて高い構造となっているが、
低減化の要求は強くなかった。しかし、ドライウェル２
の上部の定検作業が多くなる傾向にあり、低減化対策が
望まれている。The above conventional technology has a structure in which the radiation dose is higher in the upper part of the reactor containment vessel dry well 2 than in the lower part.
There was no strong demand for reduction. However, Drywell 2
There is a tendency for regular inspection work to increase in the upper part of the vehicle, and measures to reduce this are desired.
本発明の目的は、定期検査時等のドライウェルの放射線
量を低減する構造を提供することにある。An object of the present invention is to provide a structure that reduces the radiation dose of a dry well during periodic inspections and the like.
〔課題を解決するための手段〕
上記目的は、原子炉じゃへい壁をドライウェルの近くま
で上方に延長し、主蒸気配管等の大口径の貫通口に扉を
設けることにより達成される。[Means for Solving the Problems] The above object is achieved by extending the reactor shroud upwards to near the dry well and providing doors at large-diameter through-holes such as main steam piping.
原子炉じゃへい壁を原子炉格納容器１くライウエルの近
くまで延長し、主蒸気配管を原子炉じゃへい壁の外部に
引き出す大口径の貫通口に扉を設け、定期検査時等に作
業員が原子炉格納容器ドライウェル内に入る際には扉を
閉しる。The reactor jacket wall was extended to the vicinity of the reactor containment vessel 1 and the reactor lye well, and a door was installed at the large-diameter through-hole that led the main steam piping to the outside of the reactor jacket wall, so that it could be easily accessed by workers during periodic inspections. Close the door when entering the reactor containment drywell.
それによって、ドライウェル上部における放射線量を低
減することができる。Thereby, the radiation dose in the upper part of the dry well can be reduced.
以下、本発明の一実施例を第ｌ図により説明する。第１
図は、原子炉格納容器の要部の縦断面図であり、９は貫
通口扉である。An embodiment of the present invention will be described below with reference to FIG. 1st
The figure is a vertical sectional view of the main part of the reactor containment vessel, and 9 is a through door.
原子炉じゃへい壁６は、鋼板とコンクリ−１・から成る
円筒型の構造物であり、原子炉圧力容器１のまわりを囲
むように設置される。この原子炉じゃへい壁６の上端は
ドライウェル２の近くまであり、この下方に耐震上の目
的によりスタビライザ８が設置される。スタビライザ８
の上側には、原子炉圧力容器１の内部で発生した蒸気を
タービンへ導く、大口径の主蒸気配管７があり、原子炉
し３ー
４ー
やへい壁６を貫通している。この貫通口は、運転時に主
蒸気配管７が原子炉圧力容器１の熱による変位と共に移
動することを考慮して、主蒸気配管７より充分に大きく
設けられるため、貫通口と主蒸気配管７との間にギャッ
プが生じる。このため、定期検査等に、原子炉じゃへい
壁６の外部における放射線量を低減するため、貫通口扉
９を設け作業員が原子炉格納容器ドライウェル２の内部
へ入る際に閉める。The reactor wall 6 is a cylindrical structure made of steel plates and concrete 1, and is installed so as to surround the reactor pressure vessel 1. The upper end of this reactor wall 6 extends close to the dry well 2, and a stabilizer 8 is installed below this for seismic purposes. stabilizer 8
On the upper side, there is a large-diameter main steam pipe 7 that guides the steam generated inside the reactor pressure vessel 1 to the turbine, and penetrates the reactor wall 3-4 and the inner wall 6. This through-hole is provided sufficiently larger than the main steam pipe 7 in consideration of the fact that the main steam pipe 7 moves with the thermal displacement of the reactor pressure vessel 1 during operation. A gap arises between them. Therefore, in order to reduce the radiation dose outside the reactor shielding wall 6 during periodic inspections and the like, a through door 9 is provided and closed when a worker enters the inside of the reactor containment vessel dry well 2.
これによって、ドライウェル２の上部における放射線量
を低減することができる。Thereby, the radiation dose in the upper part of the dry well 2 can be reduced.
また、運転時は、貫通口扉９を開けておくことにより、
主蒸気配管７との干渉を避けることができる。In addition, by keeping the penetration door 9 open during operation,
Interference with the main steam pipe 7 can be avoided.
ここで、運転時に貫通口扉９を開放しておくのは、原子
炉じゃへいＭ６内での主蒸気配管７の破断を想定した場
合に原子炉じゃへい壁６の内部が圧力」二昇するのを避
けるためである。Here, the reason why the penetration door 9 is left open during operation is to prevent the pressure inside the reactor barrier wall 6 from rising by 2' in the event that the main steam pipe 7 in the reactor barrier M6 is ruptured. This is to avoid
本発明によれば、原子力発電設備の定期検査等で、ドラ
イウェル内の放射線量を低減することができて作業員の
安全上効果がある。According to the present invention, it is possible to reduce the radiation dose in a dry well during periodic inspections of nuclear power generation equipment, etc., and this is effective in terms of safety for workers.
第１図は、本発明の原子炉じゃへい壁の一実施例を表わ
す縦断面図、第２図は従来の原子炉格納容器の部分断面
図である。
１・・・原子炉圧力容器、２・・・ドライウェル、３・
・・サブレツションチェンバ、４・・・シールドウオー
ル、５・・・基礎，６・・・原子炉しやへい壁、７・・
・主蒸気配第
１
図
！
第
２
図
ＩFIG. 1 is a longitudinal sectional view showing one embodiment of the reactor barrier wall of the present invention, and FIG. 2 is a partial sectional view of a conventional reactor containment vessel. 1...Reactor pressure vessel, 2...Dry well, 3.
...Subrection chamber, 4...Shield wall, 5...Foundation, 6...Reactor shield wall, 7...
・Main steam distribution diagram 1! Figure 2 I
Claims (1)
い壁において、 上部をドライウェル壁の近くまで延長し、主蒸気配管を
原子炉しゃへい壁の外部へ引き出すために設ける大口径
の貫通孔に扉を設けたことを特徴とする原子炉しゃへい
壁。[Claims] 1. A cylindrical shield wall provided around the reactor pressure vessel, the upper part of which extends close to the dry well wall, and is provided to draw the main steam pipe to the outside of the reactor shield wall. A nuclear reactor shielding wall characterized by having a door installed in a large-diameter through hole.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1164002A JPH0631779B2 (en) | 1989-06-28 | 1989-06-28 | Nuclear reactor wall |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1164002A JPH0631779B2 (en) | 1989-06-28 | 1989-06-28 | Nuclear reactor wall |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH0329891A true JPH0329891A (en) | 1991-02-07 |
| JPH0631779B2 JPH0631779B2 (en) | 1994-04-27 |
Family
ID=15784893
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1164002A Expired - Lifetime JPH0631779B2 (en) | 1989-06-28 | 1989-06-28 | Nuclear reactor wall |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0631779B2 (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH03277992A (en) * | 1990-03-28 | 1991-12-09 | Toshiba Corp | Apparatus for shielding top part of shielding wall of nuclear reactor |
Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS57125395A (en) * | 1981-01-27 | 1982-08-04 | Ishikawajima Harima Heavy Ind | Earthquake-proof device for nuclear reactor container |
| JPS5971195U (en) * | 1982-11-04 | 1984-05-15 | 石川島播磨重工業株式会社 | Reactor shield wall shield plug locking device |
| JPS61173191A (en) * | 1985-01-28 | 1986-08-04 | 株式会社日立製作所 | Container for nuclear reactor |
| JPS6392296U (en) * | 1986-12-05 | 1988-06-15 |
-
1989
- 1989-06-28 JP JP1164002A patent/JPH0631779B2/en not_active Expired - Lifetime
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS57125395A (en) * | 1981-01-27 | 1982-08-04 | Ishikawajima Harima Heavy Ind | Earthquake-proof device for nuclear reactor container |
| JPS5971195U (en) * | 1982-11-04 | 1984-05-15 | 石川島播磨重工業株式会社 | Reactor shield wall shield plug locking device |
| JPS61173191A (en) * | 1985-01-28 | 1986-08-04 | 株式会社日立製作所 | Container for nuclear reactor |
| JPS6392296U (en) * | 1986-12-05 | 1988-06-15 |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH03277992A (en) * | 1990-03-28 | 1991-12-09 | Toshiba Corp | Apparatus for shielding top part of shielding wall of nuclear reactor |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0631779B2 (en) | 1994-04-27 |
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