JPH0631779B2 - Nuclear reactor wall - Google Patents
Nuclear reactor wallInfo
- Publication number
- JPH0631779B2 JPH0631779B2 JP1164002A JP16400289A JPH0631779B2 JP H0631779 B2 JPH0631779 B2 JP H0631779B2 JP 1164002 A JP1164002 A JP 1164002A JP 16400289 A JP16400289 A JP 16400289A JP H0631779 B2 JPH0631779 B2 JP H0631779B2
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- wall
- pressure vessel
- dry well
- steam pipe
- 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 - Lifetime
Links
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
Description
【発明の詳細な説明】 〔産業上の利用分野〕 本発明は、原子力発電設備の定期検査に際し、原子炉格
納容器ドライウエル内の放射線量を低減するのに好適な
原子炉しやへい壁に関する。TECHNICAL FIELD The present invention relates to a nuclear reactor sheath wall suitable for reducing the radiation dose in the dry well of a nuclear reactor containment vessel at the time of periodic inspection of nuclear power generation equipment. .
従来の原子炉しやへい壁を第２図の原子炉格納容器に縦
断図を用いて説明する。A conventional reactor sheath wall will be described in the reactor containment vessel of FIG. 2 with reference to a vertical section.
図において、１は原子炉圧力容器、２はドライウエル、
３はサプレツシヨンチエンバ、４はシールドウオール、
５は原子炉本体の基礎、６は原子炉しやへい壁、７は主
蒸気配管、８はスタビライザである。In the figure, 1 is a reactor pressure vessel, 2 is a dry well,
3 is the suppression chimba, 4 is the shield wall,
Reference numeral 5 is a foundation of the reactor body, 6 is a reactor sheath wall, 7 is a main steam pipe, and 8 is a stabilizer.
原子炉圧力容器１はドライウエル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。定期検査時等に
おいては、ドライウエル２の内部に作業員が入るため、
原子炉圧力容器１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
周囲に原子炉しやへい壁６を設けている。原子炉しやへ
い壁６は、鋼板とコンクリートから成る円筒型の構造物
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、原子炉しやへい壁６の上端には、原子炉圧力容器
１と原子炉しやへい壁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１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トとの間に
ギヤツプを設けている。The reactor pressure vessel 1 is installed inside the dry well 2,
It is supported by the foundation 5 of the reactor body. At the time of regular inspection, etc., workers enter the dry well 2,
It is necessary to protect the radiation from the reactor pressure vessel 1 and reduce the dose. For this reason, a reactor wall 6 is provided around the reactor pressure vessel 1. The reactor sheath wall 6 is a cylindrical structure made of steel plate and concrete, and its lower end is embedded in the foundation 5 of the reactor body.
Further, a stabilizer 8 is provided at the upper end of the reactor sheath wall 6 to reduce relative displacement between the reactor pressure vessel 1 and the reactor sheath wall 6 during an earthquake. The stabilizer 8 works effectively only against horizontal seismic loads,
In the vertical direction, the reactor pressure vessel 1 is heated to a high temperature during operation, and heat is transferred. Therefore, a gear cap is provided between the reactor pressure vessel 1 and a bracket attached to the reactor pressure vessel 1 so as not to prevent this deformation.
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、ドライウエル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 plays a role of guiding the 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, as a device related to this kind of device, for example,
JP-A-57-80580 can be mentioned.
上記従来技術は、原子炉格納容器ドライウエル２の上部
では放射線量が下部に比べて高い構造となつているが、
低減化の要求は強くなかつた。しかし、ドライウエル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-mentioned conventional technology has a structure in which the radiation dose is higher in the upper part of the dry well 2 of the reactor containment vessel than in the lower part.
The demand for reduction has been strong. But drywell 2
There is a tendency for more regular inspection work on the upper part of the area, and reduction measures are desired.
本発明の目的は、定期検査時等のドライウエルの放射線
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 for reducing the radiation dose of a dry well at the time of periodic inspection.
上記目的は、原子炉しやへい壁をドライウエルの近くま
で上方に延長し、主蒸気配管等の大口径の貫通口に扉を
開けることにより達成される。The above object is achieved by extending the reactor sheath wall upwards near the drywell and opening a door through a large-diameter through-hole such as a main steam pipe.
原子炉しやへい壁を原子炉格納容器ドライウエルの近く
まで延長し、主蒸気配管を原子炉しやへい壁の外部に引
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エル内に入る際には扉を閉
じる。Extend the reactor sheath wall to the vicinity of the dry well of the reactor containment vessel, install a door on the large-diameter through-hole that draws out the main steam pipe to the outside of the reactor sheath wall, and workers during periodic inspections etc. Close the door when enters the dry well of the PCV.
それによつて、ドライウエ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１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. First
The figure is a vertical cross-sectional view of the main part of the reactor containment vessel, and 9 is a through-door.
原子炉しやへい壁６は、鋼板とコンクリートから成る円
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。この原子炉しやへい壁６の上端はド
ライウエル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
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との間にギヤツ
プが生じる。このため、定期検査等に、原子炉しやへい
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エル２の内部
へ入る際に閉める。The reactor sheath wall 6 is a cylindrical structure made of steel plate and concrete, and is installed so as to surround the reactor pressure vessel 1. The upper end of the reactor wall 6 is close to the dry well 2, and a stabilizer 8 is installed below this for the purpose of earthquake resistance. Above the stabilizer 8, 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 sheath 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 along with the displacement of the reactor pressure vessel 1 due to heat during operation. There is a gear gap between them. For this reason, in order to reduce the amount of radiation outside the reactor sheath wall 6 for periodic inspections and the like, the through-door 9 is provided and closed when an operator enters the dry well 2 of the reactor containment vessel.
これによつて、ドライウエル２の上部における放射線量
を低減することができる。As a result, the radiation dose above 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 opening the through-door 9 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
炉しやへい壁６内での主蒸気配管７の破断を想定した場
合に原子炉しやへい壁６の内部が圧力上昇するのを避け
るためである。Here, the opening of the through-door 9 during operation is to increase the pressure inside the reactor wall 6 when the main steam pipe 7 is assumed to be broken in the reactor wall 6. This is to avoid doing.
本発明によれば、原子力発電設備の定期検査等で、ドラ
イウエ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 the dry well during the periodic inspection of the nuclear power generation facility and the like, which is effective for the safety of the worker.
第１図は、本発明の原子炉しや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…ドライウエル、３…サプレツ
シヨンチエンバ、４…シールドウオール、 ５…基礎、６…原子炉しやへい壁、７…主蒸気配管、８
…スタビライザ、９…貫通口扉。FIG. 1 is a vertical sectional view showing an embodiment of the reactor sheath 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 ... Suppression chamber, 4 ... Shield wall, 5 ... Foundation, 6 ... Reactor sheath wall, 7 ... Main steam pipe, 8
... stabilizer, 9 ... through door.
Claims (1)
のしやへい壁において、 上部をドライウエル壁の近くまで延長し、主蒸気配管を
原子炉しや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やへい
壁。1. A cylindrical sheath wall provided around a reactor pressure vessel, the upper part of which extends close to the drywell wall and the main steam pipe is drawn out of the reactor sheath wall. A large-diameter through-hole is provided with a door, which is a reactor wall.
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 JPH0329891A (en) | 1991-02-07 |
| JPH0631779B2 true 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) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2624866B2 (en) * | 1990-03-28 | 1997-06-25 | 株式会社東芝 | Reactor shielding device |
Citations (2)
| 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 |
| JPS61173191A (en) * | 1985-01-28 | 1986-08-04 | 株式会社日立製作所 | Container for nuclear reactor |
Family Cites Families (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| 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 |
| JPS6392296U (en) * | 1986-12-05 | 1988-06-15 |
-
1989
- 1989-06-28 JP JP1164002A patent/JPH0631779B2/en not_active Expired - Lifetime
Patent Citations (2)
| 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 |
| JPS61173191A (en) * | 1985-01-28 | 1986-08-04 | 株式会社日立製作所 | Container for nuclear reactor |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0329891A (en) | 1991-02-07 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US5225150A (en) | Integrated head package for top mounted nuclear instrumentation | |
| CN103871496A (en) | Integrated reactor roof structure for pressurized water reactor | |
| US11848115B2 (en) | Dismantling method of radioactive structures of heavy water reactor facilities | |
| CN113299411A (en) | Radiation shielding heat preservation device and design method and application thereof | |
| CN1041573C (en) | Low activated incore instrument | |
| JP6577014B2 (en) | Method of pulling out the in-core instrument from the core of a pressurized water reactor | |
| JPH0631779B2 (en) | Nuclear reactor wall | |
| CN111627575A (en) | Shielding assembly for reactor and shielding structure thereof | |
| JP6129656B2 (en) | Method for carrying out fuel debris and working house system in boiling water nuclear power plant | |
| US5392326A (en) | Boiling water reactor | |
| JP6253444B2 (en) | Method for carrying out in-furnace equipment and fuel carrying out method in boiling water nuclear power plant | |
| US3086931A (en) | Neutron shielding for nuclear reactors | |
| JPS6355496A (en) | Nuclear reactor | |
| US4118277A (en) | Steel containment for nuclear reactor installations | |
| JP3456783B2 (en) | How to replace core shroud | |
| GB2565887A (en) | Moving method of shroud head, upper guide rod, and suspension tool | |
| JP3265116B2 (en) | Control rod shielding device in reactor | |
| US3048533A (en) | Neutronic reactor manipulating device | |
| JPS601593A (en) | Pit cover for upper section of reactor | |
| JPH0225993Y2 (en) | ||
| JPS646427B2 (en) | ||
| JP2008039403A (en) | Nuclear reactor containment installation and nuclear reactor building | |
| KR830000825B1 (en) | New arrangement in nuclear reactor measurement equipment room | |
| JPH0446397B2 (en) | ||
| CN203043721U (en) | Integrated water filtering device in nuclear power plants |