JPS60171487A - Pressure vessel for nuclear reactor - Google Patents
Pressure vessel for nuclear reactorInfo
- Publication number
- JPS60171487A JPS60171487A JP59027121A JP2712184A JPS60171487A JP S60171487 A JPS60171487 A JP S60171487A JP 59027121 A JP59027121 A JP 59027121A JP 2712184 A JP2712184 A JP 2712184A JP S60171487 A JPS60171487 A JP S60171487A
- Authority
- JP
- Japan
- Prior art keywords
- pressure vessel
- reactor pressure
- cylindrical body
- reactor
- cylindrical shell
- 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
- Y02E30/30—Nuclear fission reactors
Landscapes
- Pressure Vessels And Lids Thereof (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
【発明の詳細な説明】 〔発明の利用分野〕 不発明は・原子炉圧力容器に関する。[Detailed description of the invention] [Field of application of the invention] The invention relates to nuclear reactor pressure vessels.
一般に加圧水型原子炉は、原子炉圧力ｇ器と。 Generally, pressurized water reactors are equipped with reactor pressure gators.
この内部に位置した原子炉内部構造物、原子炉燃料集合
体及び制御棒で構成され、給水ノズルからの加圧された
冷却水中を、原子炉燃料から発生する熱により加熱する
。It consists of reactor internal structures, reactor fuel assemblies, and control rods located inside the reactor, and pressurized cooling water from the water supply nozzle is heated by heat generated from the reactor fuel.
従来技術を図面を用いて説明する。The prior art will be explained using drawings.
第１図において２原子炉圧力容器給水ノズル６から注入
される冷却水は、原子炉圧力容器円筒胴１とコアバレル
５のｉ’Ｈ３ｆ１降し、さらにコアバレル５の内側を上
昇し、コアバレル５に接続した原子炉圧力容器出口ノズ
ル７から排出される。In FIG. 1, the cooling water injected from the two reactor pressure vessel water supply nozzles 6 flows down i'H3f1 of the reactor pressure vessel cylindrical body 1 and the core barrel 5, further rises inside the core barrel 5, and is connected to the core barrel 5. is discharged from the reactor pressure vessel outlet nozzle 7.
しかし、炉心冷却系作動時に、１皇子炉圧力ｇ Ｒ内部
の圧力が高いまま、通常運転時よりも低い温度の冷却水
が原子炉圧力容器内部に注入されると、原子炉圧力容５
は加圧熱衝撃金堂けることになる。However, when the core cooling system is operating, if cooling water with a lower temperature than during normal operation is injected into the reactor pressure vessel while the pressure inside the reactor remains high, the reactor pressure
The pressure and thermal shock will cause the metal to melt.
さらに、原子炉圧力８４円筒胴１の炉心近くの領域では
、原子炉圧力容器の４：Ａ利は中性子の照射を多く受け
、この部分は加圧熱衡撃を受けることにエリ破壊靭性値
が低下することがあり、原子炉圧力容器の寿命を短くす
る可能性があるという欠点があった・
〔発明の目的〕
本発明の目的は、炉心冷却水にエリ起きるｊ皇子炉圧力
容器に対する加圧熱画撃を防ＩＩ−シ、原子炉圧力容器
材料の靭性値低下を１へ１゛↓市する原子炉圧力容器を
提供することにある。Furthermore, in the area near the core of the cylindrical shell 1, where the reactor pressure is 84, the 4:A area of the reactor pressure vessel receives a lot of neutron irradiation, and this area is subjected to pressurized thermal shock, which increases the fracture toughness value. [Object of the Invention] The purpose of the present invention is to prevent pressurization of the Oji reactor pressure vessel, which occurs in the reactor core cooling water. It is an object of the present invention to provide a nuclear reactor pressure vessel that prevents thermal damage and reduces the decrease in toughness of the reactor pressure vessel material by 1 to 1.
〔発明の１概要〕
本発明は１円筒胴の内側に、円筒胴上部のノズルより円
筒胴内部に供給される冷却水が１円筒胴内壁に直接触れ
ることを阻＋）−する位置に円筒を設は前記目的を達成
するようにしたものである。[1 Summary of the Invention] The present invention provides a cylindrical body with a cylinder located inside the cylindrical body at a position that prevents the cooling water supplied into the cylindrical body from a nozzle on the upper part of the cylindrical body from directly touching the inner wall of the cylindrical body. The design was designed to achieve the above objectives.
次に本発明の〜実施例を図面によって説明する。 Next, embodiments of the present invention will be described with reference to the drawings.
第３図について説明すると、原子炉圧力容器円筒胴１の
下部に１唄子炉圧力容器下鏡２が溶接されている。この
原子炉圧力容器円筒胴１の上部には原子炉圧力容器上ぶ
ｆｃ３が取り付けられる。原子炉圧力容器円筒胴１には
原子炉圧力容器給水ノズル６及び原子炉圧力容器出口ノ
ズル７が４ソリ付けられている。甘た。原子炉圧力容器
円筒胴１の内側には、コアバレル５が設置され、このコ
アバレル５と原子炉圧力容器円筒胴１の間には、原子炉
圧力容器内筒４が、原子炉圧力容器円筒胴工に取り付け
られている。なお、原子炉圧力容器出口ノズル７は、コ
アバレル５に接続されている。Referring to FIG. 3, a lower mirror 2 of the reactor pressure vessel is welded to the lower part of the cylindrical body 1 of the reactor pressure vessel. A reactor pressure vessel upper fc3 is attached to the upper part of the reactor pressure vessel cylindrical body 1. Four reactor pressure vessel water supply nozzles 6 and four reactor pressure vessel outlet nozzles 7 are attached to the reactor pressure vessel cylindrical body 1 . Sweet. A core barrel 5 is installed inside the reactor pressure vessel cylindrical body 1, and a reactor pressure vessel inner cylinder 4 is installed between the core barrel 5 and the reactor pressure vessel cylindrical body 1. is attached to. Note that the reactor pressure vessel outlet nozzle 7 is connected to the core barrel 5.
第３図は１通常・軍転状態を示しており、原子炉圧力容
器給水ノズル６から注入される冷却水は、原子炉圧力容
器内筒４とコアバレル５０間を下降し、さらにコアバレ
ル５の内側全上昇して原子炉圧力容器出口ノズルより排
出される。FIG. 3 shows the normal and militarized states, in which the cooling water injected from the reactor pressure vessel water supply nozzle 6 descends between the reactor pressure vessel inner cylinder 4 and the core barrel 50, and then goes all the way inside the core barrel 5. It rises and is discharged from the reactor pressure vessel outlet nozzle.
したがって、冷却水は直阪に原子炉圧力容器円筒胴１の
内壁に触れることがなく、冷却水の輻１Ｗ変動は原子炉
圧力容器円筒胴１と原子炉圧力容器内筒４の間にある炉
水にエリ・原子炉圧力容器円筒胴１の内壁に伝わらす、
炉心冷却系作動時に通常運転時よりもさらに低い温度の
冷却水が注入されても・原子炉圧力容器は加圧熱衝撃を
受けることがない構造となっている。Therefore, the cooling water does not directly touch the inner wall of the reactor pressure vessel cylindrical shell 1, and the 1W fluctuation of the cooling water is applied to the reactor pressure vessel between the reactor pressure vessel cylindrical shell 1 and the reactor pressure vessel inner cylinder 4. The water is transmitted to the inner wall of the cylindrical reactor pressure vessel 1,
Even if cooling water at a temperature lower than that during normal operation is injected during the operation of the core cooling system, the reactor pressure vessel is structured so that it will not receive pressurized thermal shock.
第５図は本発明の他の実施例を示すもので、第３図と同
一部分は同一符号で示す。第３図と異なる点は、原子炉
圧力容器内筒４に貫通孔９を設けたことにある。このよ
うにすることによって、原子炉圧力容器円筒胴と原子炉
圧力容器内筒の間に空気がたまることを防止することが
できる。FIG. 5 shows another embodiment of the present invention, in which the same parts as in FIG. 3 are designated by the same reference numerals. The difference from FIG. 3 is that a through hole 9 is provided in the reactor pressure vessel inner cylinder 4. By doing so, it is possible to prevent air from accumulating between the cylindrical body of the reactor pressure vessel and the inner cylinder of the reactor pressure vessel.
この実施例においては、原子炉圧力容器円筒胴１と炉心
８とのｊ…に、原子炉圧力容器内筒があるため、原子炉
圧力容器円筒胴１の中性子照射量が少なくなり・原子炉
圧力容器円筒胴１の材料の照射脆化を少なくすることが
できる。In this embodiment, since the reactor pressure vessel inner cylinder is located between the reactor pressure vessel cylindrical shell 1 and the reactor core 8, the amount of neutron irradiation in the reactor pressure vessel cylindrical shell 1 is reduced, and the reactor pressure Irradiation embrittlement of the material of the container cylindrical body 1 can be reduced.
本発明によれば、原子炉圧力容器は加圧熱衝撃を防止す
ることができる。According to the present invention, the reactor pressure vessel can prevent pressurization thermal shock.
第１図は従来技術による原子炉圧力容器の断面図・第２
図は第１図のＡ−Ａ断面図、第３図は本発明の一実施例
を示す原子炉圧力容器の断面図２第４図は第３図のＢ−
Ｂｌｆｉ面図、第５図は貫通孔を設けた原子炉圧力容器
の断面図である。
１・・・原子炉圧力容器円筒胴、２・・・原子炉圧力容
器下鏡・３・・・原子炉圧力容器上ぶた、４・・・原子
炉圧力容器内筒、５・・・コアバレル、６・・・原子炉
圧力容器給水ノズル、７・・・原子炉圧力容器出口ノズ
ル、第 １ 図
第２図
第３図
佑４図Figure 1 is a cross-sectional view of a reactor pressure vessel according to conventional technology.
The figure is a sectional view taken along the line A-A in FIG. 1, and FIG.
The Blfi plane view and FIG. 5 are cross-sectional views of a nuclear reactor pressure vessel provided with through holes. 1... Reactor pressure vessel cylindrical body, 2... Reactor pressure vessel lower mirror, 3... Reactor pressure vessel upper lid, 4... Reactor pressure vessel inner cylinder, 5... Core barrel, 6... Reactor pressure vessel water supply nozzle, 7... Reactor pressure vessel outlet nozzle, Figure 1, Figure 2, Figure 3, and Figure 4.
Claims (1)
；笥胴の上部に位置する上ぶたと・前記円筒胴・下鏡及
び上ぶたと内部又は外部配管とを接続するためのノズル
を備えたものにおいて、前記円筒胴の内則に、前記円筒
胴下部のノズルより前記円筒胴内部に供給される冷却水
が、前記円筒胴内壁に面接触れること全阻止する位置に
内荀全設けたことを特徴とする原子炉圧力容器。1. For connecting the cylindrical body, the lower mirror attached to the lower part of the cylindrical body, the circle; the upper lid located at the upper part of the cylindrical body, the cylindrical body, the lower mirror, the upper lid, and internal or external piping. In the cylindrical shell, the inner wall of the cylindrical shell is located at a position that completely prevents the cooling water supplied into the cylindrical shell from the nozzle at the lower part of the cylindrical shell from coming into contact with the inner wall of the cylindrical shell. A nuclear reactor pressure vessel characterized by complete installation.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59027121A JPS60171487A (en) | 1984-02-17 | 1984-02-17 | Pressure vessel for nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59027121A JPS60171487A (en) | 1984-02-17 | 1984-02-17 | Pressure vessel for nuclear reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS60171487A true JPS60171487A (en) | 1985-09-04 |
Family
ID=12212221
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP59027121A Pending JPS60171487A (en) | 1984-02-17 | 1984-02-17 | Pressure vessel for nuclear reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS60171487A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB2294988A (en) * | 1994-10-31 | 1996-05-15 | Aisin Seiki | Anti-skid brake system |
-
1984
- 1984-02-17 JP JP59027121A patent/JPS60171487A/en active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB2294988A (en) * | 1994-10-31 | 1996-05-15 | Aisin Seiki | Anti-skid brake system |
| GB2294988B (en) * | 1994-10-31 | 1998-03-04 | Aisin Seiki | Anti-skid control device |
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