JPS6146480Y2 - - Google Patents
Info
- Publication number
- JPS6146480Y2 JPS6146480Y2 JP1980119016U JP11901680U JPS6146480Y2 JP S6146480 Y2 JPS6146480 Y2 JP S6146480Y2 JP 1980119016 U JP1980119016 U JP 1980119016U JP 11901680 U JP11901680 U JP 11901680U JP S6146480 Y2 JPS6146480 Y2 JP S6146480Y2
- Authority
- JP
- Japan
- Prior art keywords
- pipe
- branch pipe
- steam cooling
- cooling device
- reaction force
- 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 23
- 238000009423 ventilation Methods 0.000 claims description 4
- 230000001629 suppression Effects 0.000 description 6
- 125000006850 spacer group Chemical group 0.000 description 5
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 4
- NJPPVKZQTLUDBO-UHFFFAOYSA-N novaluron Chemical compound C1=C(Cl)C(OC(F)(F)C(OC(F)(F)F)F)=CC=C1NC(=O)NC(=O)C1=C(F)C=CC=C1F NJPPVKZQTLUDBO-UHFFFAOYSA-N 0.000 description 2
- 238000009835 boiling Methods 0.000 description 1
- 230000005494 condensation Effects 0.000 description 1
- 238000009833 condensation Methods 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 230000003014 reinforcing effect Effects 0.000 description 1
- 238000003466 welding Methods 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
-
- 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
【考案の詳細な説明】
本考案は蒸気冷却装置の振れ止めに偉力を発揮
する支持装置に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a support device that is effective in preventing the sway of a steam cooling device.
原子炉炉心内で蒸気を発生させる方式の沸騰水
型原子力発電所においては、主蒸気逃し弁作動時
或は事故発生の際、高温の蒸気を凝縮させ、原子
炉格納容器の圧力上昇を抑制するため、一定量の
水をプールした圧力抑制室を原子炉格納容器内に
設けているが、該圧力抑制室のプール水中に設置
される蒸気冷却装置としてＴ字形の蒸気冷却装置
を用いる場合は、該蒸気冷却装置の分岐位置に蒸
気流の力が作用して振動が発生し、該振動により
蒸気冷却装置各部に損傷を与える虞れが生じる。
また蒸気冷却装置作動時は蒸気冷却装置自身が高
温となるため、直接溶接により取りつけられる一
般の支持装置にあつては、熱膨張による破損も考
えられる。 In boiling water nuclear power plants that generate steam within the reactor core, when the main steam relief valve is activated or an accident occurs, high-temperature steam is condensed to suppress the pressure rise in the reactor containment vessel. Therefore, a pressure suppression chamber with a certain amount of water pooled is provided inside the reactor containment vessel, but if a T-shaped steam cooling device is used as the steam cooling device installed in the pool water of the pressure suppression chamber, The force of the steam flow acts on the branch position of the steam cooling device to generate vibrations, which may cause damage to various parts of the steam cooling device.
Furthermore, when the steam cooling device is in operation, the steam cooling device itself reaches a high temperature, so if it is a general support device that is attached by direct welding, damage due to thermal expansion is a possibility.
本考案の原子力プラントの蒸気冷却装置用支持
装置は以上の問題を解決するためになしたもの
で、主管の一端に２本の分岐管を互いに反対方向
に延びる状態で接続し該分岐管に複数の通気孔を
設けた蒸気冷却装置を支持する装置において、主
管と分岐管との接続部における反主管側に反力受
け具を配設し、分岐管振れ止め具を分岐管の長手
方向適宜位置に配設したことを特徴とするもので
ある。 The support device for a steam cooling system in a nuclear power plant of the present invention was developed to solve the above problem.Two branch pipes are connected to one end of the main pipe in a state extending in opposite directions, and a plurality of branch pipes are connected to each other in opposite directions. In a device that supports a steam cooling device with ventilation holes, a reaction force receiver is installed on the opposite side of the main pipe at the connection between the main pipe and the branch pipe, and the branch pipe steadying device is placed at an appropriate position in the longitudinal direction of the branch pipe. It is characterized by being placed in the
以下本考案の実施例を図面により説明する。 Embodiments of the present invention will be described below with reference to the drawings.
第２図に示すように、主管２の一端に２本の分
岐管３を互いに反対方向に延びる状態で接続し該
分岐管３に多数の通気孔４を設けた蒸気冷却装置
１は、第１図に示すように分岐管３を原子炉格納
容器５の接線方向に沿う如く設け主管２を原子炉
格納容器５の半径方向に沿う如く設けて、圧力抑
制室６内に据付けられている。第１図において７
は原子炉格納容器５内の蒸気を蒸気冷却装置１に
送給する蒸気逃し配管である。 As shown in FIG. 2, the steam cooling device 1 has two branch pipes 3 connected to one end of a main pipe 2 so as to extend in opposite directions, and a large number of ventilation holes 4 are provided in the branch pipes 3. As shown in the figure, the branch pipe 3 is provided along the tangential direction of the reactor containment vessel 5, and the main pipe 2 is provided along the radial direction of the reactor containment vessel 5, and is installed in the pressure suppression chamber 6. 7 in Figure 1
is a steam relief pipe that supplies steam in the reactor containment vessel 5 to the steam cooling device 1.
本考案の支持装置は、第２図に示すように、分
岐管振れ止め具８と反力受け具９とを介し、蒸気
冷却装置１を圧力抑制室６の所定位置に支持して
蒸気冷却装置の振動を抑える構成である。 As shown in FIG. 2, the support device of the present invention supports the steam cooling device 1 at a predetermined position in the pressure suppression chamber 6 via the branch pipe steadying device 8 and the reaction force receiving device 9. This configuration suppresses vibrations.
分岐管振れ止め具８は第６図に示すように分岐
管３の外径より若干大き目の分岐管取付孔１０を
有するサポートブラケツト１１と、該サポートブ
ラケツト１１を固定するための台座１２とから成
るもので、前記分岐管取付孔１０に分岐管３を貫
通してサポートブラケツト１１を分岐管３の根本
部分と中間部分に配設し、分岐管３の下方におい
て分岐管３に沿い延びるサポートパイプ１３に固
定した台座１２にボルト等により前記サポートブ
ラケツト１１を取付け、分岐管取付孔１０と分岐
管３との間の隙間における円周方向適宜個所にシ
ム１４を差込んでいる。サポートパイプ１３はト
ーラス補強板１５を介して圧力抑制室６内に支持
されている。 As shown in FIG. 6, the branch pipe steady rest 8 consists of a support bracket 11 having a branch pipe attachment hole 10 slightly larger than the outer diameter of the branch pipe 3, and a pedestal 12 for fixing the support bracket 11. The branch pipe 3 is penetrated through the branch pipe attachment hole 10, and support brackets 11 are disposed at the base and intermediate portions of the branch pipe 3, and a support pipe 13 is installed below the branch pipe 3 and extends along the branch pipe 3. The support bracket 11 is attached to a pedestal 12 fixed to the base 12 with bolts or the like, and shims 14 are inserted at appropriate positions in the circumferential direction in the gap between the branch pipe attachment hole 10 and the branch pipe 3. The support pipe 13 is supported within the pressure suppression chamber 6 via a torus reinforcing plate 15.
反力受け具９は第３図〜第７図に示すように、
主管２内の水及び蒸気流によつて主管２と分岐管
３との接続部１６に生じる矢印１７方向の力の水
平方向の分力に対し作用する半径方向反力受けビ
ーム１８と、前記力の垂直方向の分力に対し作用
する垂直方向反力受けビーム１９とを主要構成要
素として成るもので、前記接続部１６における反
主管側部分と半径方向反力受けビーム１８との間
にスペーサ２０，２１を配設し、前記接続部１６
における反主管側部分と垂直方向反力受けビーム
１９との間にスペーサ２２を配設し、半径方向反
力受けビーム１８をサポートブラケツト１１に固
着し、垂直方向反力受けビーム１９をサポートパ
イプ１３に固着している。スペーサ２０，２２は
前記接続部１６に固着され、スペーサ２１は半径
方向反力受けビーム１８に固着されている。垂直
方向反力受けビーム１９とスペーサ２２との間に
はシム２３が配設されている。 As shown in FIGS. 3 to 7, the reaction force receiver 9 is
A radial reaction force receiving beam 18 that acts on a horizontal component of the force in the direction of arrow 17 generated at the connecting portion 16 between the main pipe 2 and the branch pipe 3 due to the flow of water and steam in the main pipe 2; The main component is a vertical reaction force receiving beam 19 that acts on a component force in the vertical direction of , 21 are arranged, and the connecting portion 16
A spacer 22 is disposed between the opposite side of the main pipe and the vertical reaction force receiving beam 19, the radial reaction force receiving beam 18 is fixed to the support bracket 11, and the vertical reaction force receiving beam 19 is attached to the support pipe 13. It is stuck to. Spacers 20 and 22 are fixed to the connecting portion 16, and spacer 21 is fixed to the radial reaction force receiving beam 18. A shim 23 is disposed between the vertical reaction force receiving beam 19 and the spacer 22.
以上の構成において、主蒸気逃し弁が作動し或
は事故が発生すると、高温の蒸気は配管７から蒸
気冷却装置１に流れ込み、凝縮作用の働らきによ
つて気泡荷重は減少する。この際、蒸気冷却装置
１に発生する矢印１７方向の大きな力は、半径方
向反力受けビーム１８と垂直方向反力受けビーム
１９等から成る反力受け具９を介してサポートパ
イプ１３に伝わるので、主管２軸方向の大きな振
動が蒸気冷却装置に生ずることを制限できる。又
以上の蒸気冷却装置作動時に分岐管３に発生する
小さな振動は、分岐管振れ止め具８により吸収さ
れる。 In the above configuration, when the main steam relief valve operates or an accident occurs, high-temperature steam flows into the steam cooling device 1 from the pipe 7, and the bubble load is reduced by the action of condensation. At this time, the large force generated in the steam cooling device 1 in the direction of the arrow 17 is transmitted to the support pipe 13 via the reaction force receiver 9 consisting of the radial reaction force receiving beam 18, the vertical reaction force receiving beam 19, etc. , it is possible to limit the occurrence of large vibrations in the two axial directions of the main pipe in the steam cooling device. Furthermore, the small vibrations generated in the branch pipe 3 during operation of the steam cooling device described above are absorbed by the branch pipe steadying device 8.
なお前記した実施例においては、主管と分岐管
との接続部に掛る蒸気流の力を２方向から支持す
るよう構成したが、１方向乃至多数方向から支持
するようにしてもよく、その他本考案の要旨を逸
脱しない範囲で種々変更を加え得ること、等は勿
論である。 In the above embodiment, the force of the steam flow applied to the connection between the main pipe and the branch pipe is supported from two directions, but it may be supported from one direction or from multiple directions. Of course, various changes may be made without departing from the spirit of the invention.
本考案は前記した構成であるので、蒸気冷却装
置に生ずる振動をなくし蒸気冷却装置の健全性を
保つことができる。 Since the present invention has the above-described configuration, vibrations occurring in the steam cooling device can be eliminated and the integrity of the steam cooling device can be maintained.
第１図は蒸気冷却装置の据付状態を示す平面
図、第２図は本考案に係る支持装置の全体の構成
を示す平面図（第１図のＡ部拡大図）、第３図は
第２図のＢ部拡大図、第４図は第３図のＣ−Ｃ矢
視図、第５図は第３図のＤ−Ｄ矢視図、第６図は
第５図のＥ−Ｅ矢視図、第７図は第５図のＦ−Ｆ
矢視図である。
１……蒸気冷却装置、２……主管、３……分岐
管、４……通気孔、５……原子炉格納容器、６…
…圧力抑制室、８……分岐管振れ止め具、９……
反力受け具、１３……サポートパイプ、１４，２
３……シム、１６……主管と分岐管との接続部、
１８……半径方向反力受けビーム、１９……垂直
方向反力受けビーム、２０，２１，２２……スペ
ーサ。
Fig. 1 is a plan view showing the installed state of the steam cooling device, Fig. 2 is a plan view showing the overall configuration of the support device according to the present invention (enlarged view of section A in Fig. 1), and Fig. 3 is the plan view showing the installation state of the steam cooling device. An enlarged view of part B in the figure, FIG. 4 is a view taken along the line C-C in FIG. 3, FIG. Figure 7 is F-F of Figure 5.
It is an arrow view. 1... Steam cooling device, 2... Main pipe, 3... Branch pipe, 4... Ventilation hole, 5... Reactor containment vessel, 6...
...Pressure suppression chamber, 8... Branch pipe steadying device, 9...
Reaction force receiver, 13...Support pipe, 14,2
3...Shim, 16...Connection part between main pipe and branch pipe,
18... Radial reaction force receiving beam, 19... Vertical reaction force receiving beam, 20, 21, 22... Spacer.
Claims (1)
延びる状態で接続し該分岐管に複数の通気孔を設
けた蒸気冷却装置を支持する装置において、主管
と分岐管との接続部における反主管側に反力受け
具を配設し、分岐管振れ止め具を分岐管の長手方
向適宜位置に配設したことを特徴とする原子力プ
ラントの蒸気冷却装置用支持装置。 In a device for supporting a steam cooling device in which two branch pipes are connected to one end of the main pipe so as to extend in opposite directions, and the branch pipes are provided with a plurality of ventilation holes, the anti-main pipe at the connection part between the main pipe and the branch pipe. 1. A support device for a steam cooling system in a nuclear power plant, characterized in that a reaction force receiving device is disposed on the side, and a branch pipe steadying device is disposed at an appropriate position in the longitudinal direction of the branch pipe.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1980119016U JPS6146480Y2 (en) | 1980-08-22 | 1980-08-22 |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1980119016U JPS6146480Y2 (en) | 1980-08-22 | 1980-08-22 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5742998U JPS5742998U (en) | 1982-03-09 |
| JPS6146480Y2 true JPS6146480Y2 (en) | 1986-12-27 |
Family
ID=29479685
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1980119016U Expired JPS6146480Y2 (en) | 1980-08-22 | 1980-08-22 |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6146480Y2 (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0427729Y2 (en) * | 1985-03-01 | 1992-07-03 |
-
1980
- 1980-08-22 JP JP1980119016U patent/JPS6146480Y2/ja not_active Expired
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5742998U (en) | 1982-03-09 |
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