JPS6371694A - Nuclear reactor container - Google Patents
Nuclear reactor containerInfo
- Publication number
- JPS6371694A JPS6371694A JP61215805A JP21580586A JPS6371694A JP S6371694 A JPS6371694 A JP S6371694A JP 61215805 A JP61215805 A JP 61215805A JP 21580586 A JP21580586 A JP 21580586A JP S6371694 A JPS6371694 A JP S6371694A
- Authority
- JP
- Japan
- Prior art keywords
- pressure suppression
- suppression pool
- pressure
- dry well
- pool
- 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
- 230000001629 suppression Effects 0.000 claims description 17
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 17
- 230000002040 relaxant effect Effects 0.000 claims 1
- 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 4
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 description 3
- 229910001873 dinitrogen Inorganic materials 0.000 description 3
- 239000013598 vector Substances 0.000 description 3
- 239000002826 coolant Substances 0.000 description 2
- 230000002159 abnormal effect Effects 0.000 description 1
- 239000006185 dispersion Substances 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 230000005251 gamma ray Effects 0.000 description 1
- 210000003127 knee Anatomy 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)
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) [Abstract] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
〔発明の対象〕
本発明は原子炉冷却材喪失事故によって、原子炉−次系
状外に放出された一次冷却材中の核分裂生成物を原子炉
発電所外に出さないように、原子炉及び原子炉−次系統
を格納する原子炉格納容器に関する。[Detailed Description of the Invention] [Subject of the Invention] The present invention aims to remove fission products in the primary coolant released outside the reactor system due to a loss of reactor coolant accident to the outside of the reactor power plant. The present invention relates to a reactor containment vessel for storing a nuclear reactor and a sub-reactor system.
従来の原子炉格納容器では、ドライウェルと圧力抑制プ
ールをダウンカマを介して連通させ、−次系配管破断に
よる異常加圧時、ダウンカマより流入した高温高圧蒸気
と窒素ガスがプール水中に流入するため、その体積増加
分プール水面が急激に上昇し、圧力抑制空間内に設けら
れたキャツトウオーク、ダイヤフラム床支持構造物、ダ
ウンカマ、底部ライす、配管及び配管支持構造物が水圧
による衝撃力により揺動し、大きな荷重を与えるので特
別な対策が必要であった。In conventional reactor containment vessels, the dry well and the pressure suppression pool are communicated via a downcomer, and when there is abnormal pressurization due to a rupture in the secondary system piping, high-temperature, high-pressure steam and nitrogen gas flowing from the downcomer flow into the pool water. , the water level of the pool rises rapidly due to the increase in volume, and the catwalk, diaphragm floor support structure, downcomer, bottom lie, piping, and piping support structure installed in the pressure suppression space shake due to the impact force caused by water pressure. However, since it applies a large load, special measures were required.
第３図は従来の原子炉格納容器の断面図、第４図は第３
図のＩＶ−ＩＶ矢視断面図である。Figure 3 is a cross-sectional view of a conventional reactor containment vessel, and Figure 4 is a cross-sectional view of a conventional reactor containment vessel.
It is a sectional view taken along the line IV-IV in the figure.
本発明の目的は、従来のドライウェルと圧力抑制プール
を連通ずるダウンカマ先端ノズル口に曲線部を特徴とす
る蒸気案内管を設け、かつ、ノズル口の放出位置を下部
よりプール外壁に向ってそれぞれずらし、蒸気の流出を
一点に集中させることなく、プール水を下部ドライウェ
ルを中心として回転させることにより揺動することを防
止する原子炉格納容器を提供することにある。An object of the present invention is to provide a steam guide pipe characterized by a curved part at the nozzle opening at the tip of a downcomer that communicates a conventional dry well and a pressure suppression pool, and to change the discharge position of the nozzle opening from the bottom toward the outer wall of the pool. To provide a nuclear reactor containment vessel that prevents pool water from shaking by rotating it around a lower dry well without shifting the steam and concentrating the outflow of steam at one point.
本発明は上部ドライウェルから圧力抑制プールに連絡さ
れるダウンカマの蒸気吹き出し口の上下方向の配列を上
部から気力抑制プール内壁側より順次遠ざけて配列し、
かつ、ノズル吹き出し口の方向を螺線形にしたものであ
る。In the present invention, the steam outlets of the downcomer connected from the upper dry well to the pressure suppression pool are arranged in the vertical direction so as to be sequentially away from the inner wall of the pressure suppression pool from the upper part,
Moreover, the direction of the nozzle outlet is spiral.
その結果、−次系配管破断事故の場合、ドライウェル内
の加圧蒸気及び窒素ガス等の急激な流入により圧力抑制
プール水は従来のように局部的に揺動するのでなく上・
下吹出し口の配列が異なることにより分散される。As a result, in the case of a secondary system piping rupture accident, the pressure suppression pool water does not oscillate locally due to the sudden inflow of pressurized steam and nitrogen gas in the dry well, but instead
Dispersion occurs due to the different arrangement of the lower air outlets.
又、従来は中心から放射状に吹き呂していたものがプー
ル水を旋回させる方向に流出するので、不特定なベクト
ルを持つ衝撃力はプール水の回転エネルギに変換され、
水面の急激な上昇が緩和される。In addition, the water that traditionally flows radially from the center flows out in a direction that makes the pool water swirl, so the impact force with an unspecified vector is converted into rotational energy of the pool water.
Rapid rise in water level will be alleviated.
以下、本発明の一実施例を第１図及び第２図を用いて説
明する。An embodiment of the present invention will be described below with reference to FIGS. 1 and 2.
本実施例のようなタイプの原子炉格納容器９は上部に上
部ドライウェル２と下部に下部ドライウェル３と圧力抑
制プール室４から構成され、その間はダイヤフラム床１
２により仕切られている。The reactor containment vessel 9 of the type of this embodiment is composed of an upper dry well 2 at the top, a lower dry well 3 at the bottom, and a pressure suppression pool chamber 4, with a diaphragm floor 1 between them.
It is divided by 2.
その中心に原子炉圧力容器１が設置されその周囲を囲む
ようにガンマ−線遮蔽壁５が設けられている。ガンマ−
線遮蔽壁５の下部は原子が圧力容器１の支持サポートに
なっており、それを円筒形のＲＰＶペデスタル１３が支
持している。ＲＰＶベデイタル１３の中には、上部ドラ
イウェル２と圧力抑制室４を連絡するダウンカマ６と吹
出しロアにより連絡さ九でいる。A reactor pressure vessel 1 is installed in the center, and a gamma ray shielding wall 5 is provided surrounding it. Gamma
The lower part of the line shielding wall 5 serves as a support for the pressure vessel 1, which is supported by a cylindrical RPV pedestal 13. Inside the RPV bed 13, the upper dry well 2 and the pressure suppression chamber 4 are connected to each other by a downcomer 6 and a blowout lower.
圧力抑制室４には水が水面８のレベルになるまで貯えら
れ、一次系配管破断時の加熱蒸気を冷却する役目をする
。上部ドライウェル２には機器搬入用としてのハツチ１
０がある。Water is stored in the pressure suppression chamber 4 until it reaches the level of the water surface 8, and serves to cool the heated steam when the primary system piping breaks. There is a hatch 1 in the upper dry well 2 for carrying in equipment.
There is 0.
本発明の目的はダウンカマ６の下部に設置される吹き出
しロアの構造を従来のように圧力容器中心からＲＰＶペ
デスタルの軸直角方向へ放出するノズル向で、かつ、ペ
デスタル中心から同一半径の位置で吹き出す構造になっ
ていたものを、ノズルロアの位置を下側より原子炉格納
容器９側に近づけ、順次、吹き出し半径を違えることに
より、水中への吹出し位置を集中させるのでなく、プー
ル室４全体に分散させる構造を提供することにある。The object of the present invention is to change the structure of the blowout lower installed at the lower part of the downcomer 6 so that the nozzle directs the blowout from the center of the pressure vessel in the direction perpendicular to the axis of the RPV pedestal, and blows out the air at the same radius from the center of the pedestal. By moving the nozzle lower closer to the reactor containment vessel 9 side from the bottom and gradually changing the blowout radius, the blowout position is not concentrated into the water, but is distributed throughout the pool room 4. The goal is to provide a structure that allows
その際、ノズルの吹出しロアは螺線形を取ることにより
、一次系配管破断時の上部ドライウェル２内に充満した
高温高圧の蒸圧と窒素ガスはダウンカマ６を介してこの
ノズルロアにより流出する際、圧力抑制プール水を一定
方向へ回転させるエネルギとなる。そのため、従来のよ
うにベクトルの異なる衝撃力により、プール全体が揺動
するのでなく、プール水が旋回することにより揺動を防
止し、水面の急激な上昇を緩和することができる。At this time, the blowout lower of the nozzle takes a spiral shape, so that when the high temperature and high pressure vapor pressure and nitrogen gas that filled the upper dry well 2 at the time of the primary system pipe rupture flow out by this nozzle lower via the downcomer 6, It becomes the energy that rotates the pressure suppression pool water in a fixed direction. Therefore, instead of the entire pool swinging due to impact forces with different vectors as in the past, the pool water swirls to prevent swinging and alleviate a sudden rise in the water level.
本発明によれば、プール水の揺動で不特定のベクトルを
持つ衝撃力は回転エネルギに変換されるので、圧力抑制
プール内の圧力容器ペデスタル。According to the invention, a pressure vessel pedestal in a pressure suppression pool, since an impact force with an unspecified vector due to the rocking of the pool water is converted into rotational energy.
ダイヤフラム床の支持構造物、底部ライナ、キャツトウ
オーク、配管、及び配管支持構造物へ与える荷重の軽減
が可能である。It is possible to reduce the load on the diaphragm floor support structure, bottom liner, catwalk, piping, and piping support structure.
第１図は本発明の一実施例の原子炉格納容器の断面図、
第２図は第１図の■−■矢視断面図、第３図は従来のＭ
ＡＲＫ−ｍタイプの原子ニー格納容器の断面図、第４図
は第３図の■−ＩＶ矢祷断面図を示す。
１・・・原子炉圧力容器。FIG. 1 is a sectional view of a reactor containment vessel according to an embodiment of the present invention;
Figure 2 is a sectional view taken along the ■-■ arrow in Figure 1, and Figure 3 is a conventional M
FIG. 4 is a cross-sectional view of the ARK-m type atomic knee containment vessel, and FIG. 4 is a cross-sectional view taken along the -IV arrow in FIG. 1... Nuclear reactor pressure vessel.
Claims (1)
に格納し、これらを支持するダイヤフラム床の下部に、
圧力抑制プールと下部ドライウェルを設け、前記上部ド
ライウェルと前記圧力抑制プールとを前記原子炉圧力容
器の支持壁中をダウンカマを介して連通させるものに於
いて、前記ダウンカマの下部に設けられた蒸気放出口に
対して前記圧力抑制プール中の水の流れを一定方向に案
内する螺線形ノズルを複数個設け、かつ、ノズル口の上
下方向に配列位置を上部から圧力抑制プール室内側壁か
ら遠ざかる位置に設置することにより、一次系配管破断
時の高温高圧の蒸気の流出によるプール水の不確定な動
きを円周方向に吹き出させて、水の回転エネルギに変換
し、前記圧力抑制プールの水の揺動を押え、前記圧力抑
制空間内に設けられた配管及び配管支持構造物の荷重条
件を緩和させることを特徴とする原子炉格納容器。1. The reactor pressure vessel and auxiliary equipment are stored in the upper dry well, and the lower part of the diaphragm floor that supports them is
A pressure suppression pool and a lower dry well are provided, and the upper dry well and the pressure suppression pool are communicated through a support wall of the reactor pressure vessel via a downcomer, wherein the pressure suppression pool is provided at the lower part of the downcomer. A plurality of spiral nozzles are provided to guide the flow of water in the pressure suppression pool in a fixed direction relative to the steam release port, and the nozzle openings are arranged in the vertical direction from the top to a position away from the pressure suppression pool indoor wall. By installing it in A nuclear reactor containment vessel characterized by suppressing rocking and relaxing load conditions of piping and piping support structures provided in the pressure suppression space.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61215805A JPS6371694A (en) | 1986-09-16 | 1986-09-16 | Nuclear reactor container |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61215805A JPS6371694A (en) | 1986-09-16 | 1986-09-16 | Nuclear reactor container |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS6371694A true JPS6371694A (en) | 1988-04-01 |
Family
ID=16678546
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP61215805A Pending JPS6371694A (en) | 1986-09-16 | 1986-09-16 | Nuclear reactor container |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6371694A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111370150A (en) * | 2020-03-17 | 2020-07-03 | 中国核动力研究设计院 | Outer wall flow equalizing structure for containment vessel |
-
1986
- 1986-09-16 JP JP61215805A patent/JPS6371694A/en active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111370150A (en) * | 2020-03-17 | 2020-07-03 | 中国核动力研究设计院 | Outer wall flow equalizing structure for containment vessel |
| CN111370150B (en) * | 2020-03-17 | 2022-02-11 | 中国核动力研究设计院 | Outer wall flow equalizing structure for containment vessel |
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