JPS5940887U - Main steam relief device of nuclear reactor - Google Patents
Main steam relief device of nuclear reactorInfo
- Publication number
- JPS5940887U JPS5940887U JP1982136194U JP13619482U JPS5940887U JP S5940887 U JPS5940887 U JP S5940887U JP 1982136194 U JP1982136194 U JP 1982136194U JP 13619482 U JP13619482 U JP 13619482U JP S5940887 U JPS5940887 U JP S5940887U
- Authority
- JP
- Japan
- Prior art keywords
- main steam
- steam relief
- pipe
- relief device
- vent 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.)
- Pending
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
-
- 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) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
図面中、第1図は沸騰水型原子炉の一つであるMARK
−II型原子炉の概略を示す断面図、第2図および第3
図は従来の主蒸気逃し装置を示す概略図、第4図および
第5図は本考案の一実施例を示すもので、第4図は要部
の概略図、第5図は第4図の■−V線に沿う矢視断面図
、第6図はスペーサの他の実施例である。
1・・・・・・原子炉格納容器、1a・・・・・・底部
、2・・・・・・ −ダイヤフラムフロア、3・・・
・・・ペデスタル、4・・・・・・原子炉圧力容器、5
・・・・・・主蒸気管、6・・・・・・安全弁、7・・
・・・・主蒸気逃し管、9・・・・・・ベント管、11
・・・・・・連結具、12・・・・・・スペーサ、12
a・・・・・・支持筒、12b・・・・・・連結板、1
2C・・・・・・支持板、13・・・・・・連結具、1
3a・・・・・・支持環、13b・・・・・・連結棒、
14・・・・・・ガイド筒、15・・・・・・ジェット
ディフレクタ、16・・・・・・支持片、17・・・・
・・孔、18・・・・・・クエンチャ、D・・・・・・
ドライウェル、S・・・・・・サプレッションチャンバ
、W・・・・・・冷却水。In the drawings, Figure 1 is MARK, which is one of the boiling water reactors.
- Cross-sectional view schematically showing the type II nuclear reactor, Figures 2 and 3
The figure is a schematic diagram showing a conventional main steam relief device, and Figures 4 and 5 show an embodiment of the present invention. 6, which is a sectional view taken along the line 2-V, shows another embodiment of the spacer. 1... Reactor containment vessel, 1a... bottom, 2... - diaphragm floor, 3...
...Pedestal, 4...Reactor pressure vessel, 5
...Main steam pipe, 6...Safety valve, 7...
...Main steam relief pipe, 9...Bent pipe, 11
...Connection tool, 12... Spacer, 12
a...Support tube, 12b...Connection plate, 1
2C...Support plate, 13...Connector, 1
3a...Support ring, 13b...Connection rod,
14...Guide tube, 15...Jet deflector, 16...Support piece, 17...
...Hole, 18...Quencher, D...
Dry well, S...Suppression chamber, W...Cooling water.
Claims (1)
ンバとに区画するダイヤフラムフロアを貫通してベント
管を設け、該ベント管内に、主蒸気を前記サプレッショ
ンチャンバ内に貯えられた冷却水中に放出するようにし
た主蒸気逃し管を貫挿し、該主蒸気逃し管と前記ベント
管との間に、両者の長さ方向の相対移動を許容しかつ半
径方向の相対移動を規制するスペーサを設けるとともに
、前記ベント管と、原子炉格納容器の内壁または該原子
炉格納容器内に設けたペデスタルの外壁との間に、ベン
ト管の半径方向の移動を規制する連結具を設けてなるこ
とを特徴とする原子炉の主蒸気逃し装置。A vent pipe is provided through a diaphragm floor that divides the inside of the reactor containment vessel into a dry well and a suppression chamber, and main steam is released into the vent pipe into the cooling water stored in the suppression chamber. A main steam relief pipe is inserted through the main steam relief pipe, and a spacer is provided between the main steam relief pipe and the vent pipe to allow relative movement in the length direction and restrict relative movement in the radial direction, and and an inner wall of a reactor containment vessel or an outer wall of a pedestal provided in the reactor containment vessel, a connector for regulating movement of the vent pipe in the radial direction is provided. Main steam relief device.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP1982136194U JPS5940887U (en) | 1982-09-08 | 1982-09-08 | Main steam relief device of nuclear reactor |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP1982136194U JPS5940887U (en) | 1982-09-08 | 1982-09-08 | Main steam relief device of nuclear reactor |
Publications (1)
Publication Number | Publication Date |
---|---|
JPS5940887U true JPS5940887U (en) | 1984-03-15 |
Family
ID=30306300
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP1982136194U Pending JPS5940887U (en) | 1982-09-08 | 1982-09-08 | Main steam relief device of nuclear reactor |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS5940887U (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH0355035U (en) * | 1989-09-28 | 1991-05-28 |
-
1982
- 1982-09-08 JP JP1982136194U patent/JPS5940887U/en active Pending
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH0355035U (en) * | 1989-09-28 | 1991-05-28 |
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