JPS586490A - Nuclear reactor - Google Patents
Nuclear reactorInfo
- Publication number
- JPS586490A JPS586490A JP56104484A JP10448481A JPS586490A JP S586490 A JPS586490 A JP S586490A JP 56104484 A JP56104484 A JP 56104484A JP 10448481 A JP10448481 A JP 10448481A JP S586490 A JPS586490 A JP S586490A
- Authority
- JP
- Japan
- Prior art keywords
- piping
- furnace
- reactor
- length
- joint
- 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
- Treatment Of Water By Oxidation Or Reduction (AREA)
- Analysing Materials By The Use Of Radiation (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】
本発明は、相対変位吸収構造に係わり、特に、オーバヘ
ッド型炉心冷却装置を持つ原子炉に好適な相対変位吸収
構造に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a relative displacement absorbing structure, and particularly to a relative displacement absorbing structure suitable for a nuclear reactor having an overhead type core cooling device.
本発明の公知例を第１図に示す。原子炉圧力容器（以下
ＲＰＶと略す）１とスプレースノく−ジャ２の間を結ぶ
為炉内配管３が用いられる。炉内配管３は、シュラウド
ヘッド４に取付けられる。シュラウドヘッド４とＲ，Ｐ
Ｖｌの相対変位はスリップジヨイント５によって吸収さ
れる。しかし、スリップジヨイント５からのリークある
いは、内部を流れる流体の為に炉内配管３が振動する為
、炉内配管３を出来るだけ短くする必要があった。A known example of the present invention is shown in FIG. In-reactor piping 3 is used to connect reactor pressure vessel (hereinafter abbreviated as RPV) 1 and spray nozzle 2. The in-furnace piping 3 is attached to the shroud head 4. Shroud head 4 and R, P
The relative displacement of Vl is absorbed by the slip joint 5. However, since the furnace piping 3 vibrates due to leakage from the slip joint 5 or fluid flowing inside, it was necessary to make the furnace piping 3 as short as possible.
本発明の目的は、ＲＰｖノズル位置を下げる事無く、炉
内配管の長さを短くシ、振動しにくい構造とするととも
に、スリップジヨイント部からのリークを無クシ、振動
原因を除く事にある。The purpose of the present invention is to shorten the length of the piping inside the furnace without lowering the RPv nozzle position, create a structure that is less likely to vibrate, eliminate leakage from the slip joint, and eliminate the cause of vibration. .
従来技術においては、炉内配管の変位吸収継手を垂直に
配置し、かつシュラウドヘッド取外しの為に炉内、配管
を上に凸のＵ字形としている事により炉内配管の長さが
長くなり振動しやすい構造になっていた事に着目し、本
発明においては変位吸収継手部を水平にする事により、
振動しにくい燈い炉内配管構造を提供する。また変位吸
収継手としてペローを採用する事により、リークに伴う
振動を防止する事も可能になる。In the conventional technology, the displacement absorbing joint of the furnace piping is arranged vertically, and the furnace interior and piping are made into an upwardly convex U-shape for removing the shroud head, which increases the length of the furnace piping and causes vibration. Focusing on the fact that the structure was easy to move, in the present invention, by making the displacement absorbing joint horizontal,
To provide a piping structure in a light furnace that does not easily vibrate. In addition, by using Perot as a displacement absorbing joint, it is also possible to prevent vibrations caused by leaks.
以下、本発明の一実施例を第２図により説明する。ＲＰ
Ｖｌとスプレースパージャ２の間を結ぶ炉内配管３は、
ペロージヨイント７、サーマルスリーブ８を経てノズル
６に接続される。炉内配管３が取付けられているシュラ
ウドヘッド４とノズル６の相対変位はペロー７で吸収さ
れる。シュラウドヘッド４′ｆ：取外すときは、ベロー
７とサーマルスリーブ８の接続部を取外す事により可能
である。ベロ−７自体を取外す時は、さらに炉内配管３
との接続部を外すことにより可能である。An embodiment of the present invention will be described below with reference to FIG. R.P.
The furnace piping 3 connecting between the Vl and the spray sparger 2 is
It is connected to the nozzle 6 via a perose joint 7 and a thermal sleeve 8. The relative displacement between the shroud head 4 to which the furnace piping 3 is attached and the nozzle 6 is absorbed by the Perot 7. Shroud head 4'f: It can be removed by removing the connection between bellows 7 and thermal sleeve 8. When removing Vero-7 itself, further remove the furnace piping 3.
This can be done by disconnecting the connection.
本実施例においては、炉内配管３の長さを従来技術に比
べ１／２〜１／３に短くする事が出来る。In this embodiment, the length of the furnace piping 3 can be reduced to 1/2 to 1/3 compared to the conventional technology.
第１図においては、シュ２ウドヘツド４と炉内配管３を
上方向に取外す為、スリップジヨイント５と炉内配管３
からなる配管の引きまわしが上側に凸のＵ字構造にせざ
るを得す、この為に猷管長さが長くなる。In Figure 1, in order to remove the shroud head 4 and the furnace piping 3 upward, the slip joint 5 and the furnace piping 3 are removed.
The piping must be routed in a U-shaped structure with an upward convexity, which increases the length of the piping.
本発明の場合これを水平とする為配管の長さが短く出来
るので、炉内配管の剛性が向上し、振動低減の効果が著
しい。更に、ノズルＩＳＩ時の被曝量低減の為ノズル６
の位置を炉心よシ出来るだけ上方にずらそうとする場合
、炉内配管３の長さを従来構造に比べ十分短く保った上
でこれが可能となる。In the case of the present invention, since the piping is made horizontal, the length of the piping can be shortened, so the rigidity of the piping inside the furnace is improved, and the effect of vibration reduction is remarkable. In addition, nozzle 6 was installed to reduce the amount of radiation exposure during nozzle ISI.
When attempting to shift the position of the reactor as far upward as possible from the reactor core, this can be done while keeping the length of the in-core piping 3 sufficiently short compared to the conventional structure.
さらに、ベロージヨイントの場合には、ジヨイント部か
らのリークを無くす事が出来る。従来技術の場合のスリ
ップジヨイントにおいては、この部分からのリークが炉
内配管３の振動の一原因となっているが本発明においは
これを防ぐ事が可能となる。Furthermore, in the case of a bellows joint, leakage from the joint can be eliminated. In the case of the slip joint in the case of the prior art, leakage from this part is a cause of vibration of the furnace pipe 3, but in the present invention, it is possible to prevent this.
本発明によれば、炉内配管の長さを従来技術に比べ１／
２〜１／３に短くする事が出来るので、炉内配管の振動
を低減する効果がある。また、炉内配管の長さを出来る
だけ短くした上でノズルの位置を上げる事が出来るので
ノズルＩＳＩ時の被曝量を低減する効果がある。さらに
、スリップジヨイント部からのリークを防止できるので
、リークによる振動を防止できる効果がある。According to the present invention, the length of the furnace piping can be reduced to 1/1 compared to the conventional technology.
Since the length can be shortened by 2 to 1/3, it has the effect of reducing vibrations in the furnace piping. Furthermore, since the nozzle position can be raised while reducing the length of the in-furnace piping as much as possible, there is an effect of reducing the amount of radiation exposure during nozzle ISI. Furthermore, since leakage from the slip joint can be prevented, vibrations due to leakage can be prevented.
本発明の他の実施例としては、炉内配管の長さが十分短
く、炉内配管の振動が問題とならないように出来る場合
には、ベロージヨイントの代りに、水平のスリップジヨ
イント構造を用いる事も可能である。In another embodiment of the present invention, a horizontal slip joint structure may be used instead of a bellows joint if the length of the furnace piping is sufficiently short to prevent vibration of the furnace piping from becoming a problem. is also possible.
第１図は従来技術を説明する縦断面図、第２図は本発明
の一実施例を示す縦断面図である。
１・・・ＲＰＶ、２・・・スプレースノクーシャ、３・
・・炉内配管、４・・・シュラウドヘッド、６・・・ノ
ズル、７・・・竿１図FIG. 1 is a longitudinal sectional view illustrating a conventional technique, and FIG. 2 is a longitudinal sectional view showing an embodiment of the present invention. 1... RPV, 2... Spray Snooksha, 3.
... Piping inside the furnace, 4... Shroud head, 6... Nozzle, 7... Rod 1 diagram
Claims (1)
パージャと、これらの間にある炉内配管から成る原子炉
において、炉内配管の途中に設ける変位吸収継手を水平
に配置した事を特徴とする原子炉。1. In a nuclear reactor consisting of a reactor pressure vessel, a spray sparger installed therein, and the reactor piping between these, the feature is that a displacement absorbing joint installed in the middle of the reactor piping is arranged horizontally. nuclear reactor.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56104484A JPS586490A (en) | 1981-07-06 | 1981-07-06 | Nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56104484A JPS586490A (en) | 1981-07-06 | 1981-07-06 | Nuclear reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS586490A true JPS586490A (en) | 1983-01-14 |
Family
ID=14381826
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP56104484A Pending JPS586490A (en) | 1981-07-06 | 1981-07-06 | Nuclear reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS586490A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2012145577A (en) * | 2011-01-06 | 2012-08-02 | Ge-Hitachi Nuclear Energy Americas Llc | Reactor pressure vessel head vents and methods of using the same |
-
1981
- 1981-07-06 JP JP56104484A patent/JPS586490A/en active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2012145577A (en) * | 2011-01-06 | 2012-08-02 | Ge-Hitachi Nuclear Energy Americas Llc | Reactor pressure vessel head vents and methods of using the same |
| US8873695B2 (en) | 2011-01-06 | 2014-10-28 | Ge-Hitachi Nuclear Energy Americas Llc | Reactor pressure vessel head vents and methods of using the same |
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