JPS6321594A - Nuclear reactor container - Google Patents
Nuclear reactor containerInfo
- Publication number
- JPS6321594A JPS6321594A JP61166285A JP16628586A JPS6321594A JP S6321594 A JPS6321594 A JP S6321594A JP 61166285 A JP61166285 A JP 61166285A JP 16628586 A JP16628586 A JP 16628586A JP S6321594 A JPS6321594 A JP S6321594A
- Authority
- JP
- Japan
- Prior art keywords
- pressure
- dry well
- reactor
- containment vessel
- reduction device
- 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 description 5
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 5
- 239000002826 coolant Substances 0.000 description 3
- 238000009835 boiling Methods 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000012857 radioactive material Substances 0.000 description 1
- 230000001052 transient effect Effects 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】
〔発明の目的〕
（産業上の利用分野）
本発明は＾圧力時における圧力低減装置を協えた原子炉
格納容器に関する。DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Industrial Application Field) The present invention relates to a nuclear reactor containment vessel equipped with a pressure reduction device at the time of pressure.
（従来の技術）
従来、沸騰水型原子力発電所の原子炉格納容器は、圧力
抑制機能による格納方式を採用しており、第３図に承り
様に、原子炉圧力容器１などの原子炉−次系を収納する
ドライウェル部２と水を貯えたウェットウェル（サプレ
ッションチェンバ）部３により構成されている。また冷
却材喪失事故時における最大過渡圧力に耐える能力を持
ち、更に充分な気密性を保持することにより外部に対す
る放射性物質の拡散を防止する構造となっている。(Prior Art) Conventionally, reactor containment vessels in boiling water nuclear power plants have adopted a containment system using a pressure suppression function. It consists of a dry well section 2 that houses the secondary system and a wet well (suppression chamber) section 3 that stores water. It also has the ability to withstand the maximum transient pressure in the event of a loss of coolant accident, and has a structure that maintains sufficient airtightness to prevent radioactive materials from dispersing to the outside.
圧力抑制機能の原理としては、−次系配管の破Ｉｌ′ｉ
事故時に、ドライウェル２中に放出される原子炉−次系
の蒸気、水がベント管４を通じてサプレッションブール
水５中に導入され、ここで蒸気冷に１されることにより
エネルギーを吸収し、ドライウェル２内の圧力上昇を抑
えるものである。The principle of the pressure suppression function is that the -order system piping failure Il'i
At the time of an accident, reactor-related steam and water released into the dry well 2 are introduced into the suppression boule water 5 through the vent pipe 4, where they are steam-cooled and absorb energy. This suppresses the rise in pressure within the well 2.
（発明が解決しようとする問題点）
このため従来の原子炉格納容器においては、ドライウェ
ル２の設計圧力を比較的大きく設定しておく必要があり
、ドライウェル２の壁厚が大きくなる原因となっている
。(Problem to be solved by the invention) For this reason, in the conventional reactor containment vessel, it is necessary to set the design pressure of the dry well 2 relatively large, which causes the wall thickness of the dry well 2 to become large. It has become.
ところで従来から、原子炉格納施設としては、原子炉圧
力容器１を取り囲む原子炉格納容器、更にその外側に原
子炉建屋６を備えており、筒構造物とも充分な耐震性を
有し、耐震壁、スラブ等は充分な強度をａする構造とな
っている。Conventionally, nuclear reactor containment facilities have been equipped with a reactor containment vessel surrounding a reactor pressure vessel 1, and a reactor building 6 outside of the reactor containment vessel. , slabs, etc. have a structure that provides sufficient strength.
そこで本発明では、従来の原子炉ｉｔ屋の強固な構造を
利用し、ドライウェル内圧力上胃時に、圧力低減装置を
介して圧力を原子炉建屋内に開放し、原子炉建屋を耐圧
・漏洩、バウンダリとして機能させることにより、ドラ
イウェル設計圧力を低減することを目的とする。Therefore, in the present invention, by utilizing the strong structure of the conventional reactor IT shop, when the pressure inside the dry well rises, the pressure is released into the reactor building via a pressure reduction device, and the reactor building is made pressure-resistant and leak-proof. The purpose is to reduce drywell design pressure by functioning as a boundary.
（問題点を解決するための手段）
本発明は原子炉格納容器に係り、ドライウェルが内設さ
れている原子炉建屋の上方空間とドライウェルとを圧力
低減装置を介して連通し、原子炉格納容器を原子炉建屋
と一体化したことを特徴としている。(Means for Solving the Problems) The present invention relates to a nuclear reactor containment vessel, which communicates the upper space of a reactor building in which a dry well is installed with the dry well via a pressure reduction device, and It is characterized by integrating the containment vessel with the reactor building.
（作 用）
本発明においては、ドライウェル内の圧力が所定値以上
になった場合には、圧力低減装置が作動し、ドライウェ
ル内の雰囲気が原子炉建屋の上方空間に拡散され、圧力
の低減化が図られる。(Function) In the present invention, when the pressure in the dry well exceeds a predetermined value, the pressure reduction device is activated and the atmosphere in the dry well is diffused into the space above the reactor building, reducing the pressure. The reduction will be achieved.
（実施例） 以下図面を参照して本発明の実施例について説明する。(Example) Embodiments of the present invention will be described below with reference to the drawings.
第１図は本発明の第１の実施例を示す縦断面図である。FIG. 1 is a longitudinal sectional view showing a first embodiment of the present invention.
図において符号１１は原子炉圧力容器であり、この原子
炉圧力容器１１を取囲むように、ドライウェル１２が設
置されている。ドライウェル１２の外周囲には貯水槽１
３が配設され、主蒸気逃がし弁を介して主蒸気逃がし管
（図示せず）が接続されている。また、ドライウェル１
２は原子炉格納容器を兼ねた原子炉Ｕ屋１４により取囲
まれ、ドライウェル１２の上方の原子炉建屋１４内の空
間１５とドライウェル１２とが、圧力逃がし弁１６を介
して連通されている。原子炉建屋１４を原子炉格納容器
として兼用するため、原子炉建屋１４内にライナーを設
置し、耐漏洩性を持たけである。In the figure, reference numeral 11 indicates a reactor pressure vessel, and a dry well 12 is installed so as to surround this reactor pressure vessel 11. A water storage tank 1 is installed around the outside of the dry well 12.
3 is provided, and a main steam relief pipe (not shown) is connected via a main steam relief valve. Also, dry well 1
2 is surrounded by a reactor U building 14 that also serves as a reactor containment vessel, and a space 15 in the reactor building 14 above the dry well 12 and the dry well 12 are communicated via a pressure relief valve 16. There is. Since the reactor building 14 is also used as a reactor containment vessel, a liner is installed inside the reactor building 14 to provide leak resistance.
次にこのような構成からなる本実施例の作用について説
明する。Next, the operation of this embodiment having such a configuration will be explained.
冷却材喪失事故時に、ドライウェル１２内の圧力が高く
なった場合には、圧力逃がし弁１６が開ぎ、ドライウェ
ル１２内の雰囲気が原子炉建屋１４内の空間１５に拡散
される。この空間１５は、従来の圧力抑Ｎ、ＩＩ式格納
容器の体積に比べ十分大きくなっているので、ドライウ
ェル１２内の圧力を従来よりさらに低減化することがで
きる。When the pressure within the dry well 12 increases during a loss of coolant accident, the pressure relief valve 16 opens and the atmosphere within the dry well 12 is diffused into the space 15 within the reactor building 14. Since this space 15 is sufficiently larger than the volume of conventional pressure containment vessels of type N and II, the pressure within the dry well 12 can be further reduced than in the past.
これにより、ドライウェル１２の設計圧力を小さくする
ことができ、ドライウェル１２の壁厚を低減化すること
が可能となる。Thereby, the design pressure of the dry well 12 can be reduced, and the wall thickness of the dry well 12 can be reduced.
第２図は本発明の第２の実施例を示す縦断面図であり、
ドライウェル１２の圧力低減装置としてブローアウトパ
ネル１７が用いられている。FIG. 2 is a longitudinal sectional view showing a second embodiment of the present invention,
A blowout panel 17 is used as a pressure reduction device for the dry well 12.
この実施例によれば、冷却材喪失事故等によりドライウ
ェル１２内の圧力が所定値以上に上背すると、ブローア
ウトパネル１７が破れ、ドライウェル１２内の雰囲気が
原子炉建屋１４内の空間１５に拡散される。According to this embodiment, when the pressure inside the dry well 12 rises above a predetermined value due to a coolant loss accident or the like, the blowout panel 17 is torn and the atmosphere inside the dry well 12 is reduced to the space 15 inside the reactor building 14. spread to.
圧力低減装置として、この他にラブチャーディスクなど
を用い、ドライウェル１２内の圧力が所定値以上に上昇
した時に、ドライウェル内の雰囲気を原子炉１１屋内の
空間１５に拡散させて、ドライウェル１２の圧力の低減
化を図ることができる。In addition, a Loveture disk or the like is used as a pressure reduction device, and when the pressure inside the dry well 12 rises above a predetermined value, the atmosphere inside the dry well is diffused into the space 15 inside the reactor 11, and the dry well is closed. 12 pressure can be reduced.
以上説明したように、本発明によれば、ドライウェル内
の圧力が所定値を越えて上背した場合、圧力低減装置が
作動し、ドライウェル内の雰囲気が格納６嘉を兼ねた原
子炉建屋内に拡散され圧力の低減化が図られるので、ド
ライウェルの設計圧力を従来のものより低くすることが
できる。これにより、ドライウェルの壁厚を小さくする
ことができ、原子炉格納施設の建設費を低減化すること
ができる。As explained above, according to the present invention, when the pressure in the dry well exceeds a predetermined value, the pressure reduction device is activated and the atmosphere in the dry well is reduced to Since it is diffused indoors and the pressure is reduced, the design pressure of the dry well can be lower than that of conventional dry wells. Thereby, the wall thickness of the dry well can be reduced, and the construction cost of the reactor containment facility can be reduced.
第１図および第２図は本発明の実施例を示す縦断面図、
第３図は従来の圧力抑制御型格納容器を示１１ＩｒＩｒ
Ｉ面図である。
１１・・・原子炉圧力容器、１２・・・ドライウェル、
１４・・・原子炉建屋、１５・・・原子炉建屋の空間、
１６・・・圧力逃がし弁、１７・・・ブローアウトパネ
ル。
出願人代理人 佐 藤 −雄
第１図
Ｊ！１Ｆ７２図FIG. 1 and FIG. 2 are longitudinal sectional views showing embodiments of the present invention;
Figure 3 shows a conventional pressure suppression controlled containment vessel.
It is an I side view. 11...Reactor pressure vessel, 12...Dry well,
14... Reactor building, 15... Space of the reactor building,
16...Pressure relief valve, 17...Blowout panel. Applicant's agent Mr. Sato Figure 1 J! 1F72 figure
Claims (1)
間とドライウェルとが圧力低減装置を介して連通されて
いることを特徴とする原子炉建屋と一体化された原子炉
格納容器。 ２、圧力低減装置は圧力逃がし弁を備えていることを特
徴とする特許請求の範囲第１項記載の原子炉格納容器。 ３、圧力低減装置はラプチャーディスクを備えているこ
とを特徴とする特許請求の範囲第１項記載の原子炉格納
容器。 ４、圧力低減装置はブローアウトパネルを備えているこ
とを特徴とする特許請求の範囲第１項記載の原子炉格納
容器。[Claims] 1. An integrated reactor building characterized in that the upper space of the reactor building in which the dry well is installed and the dry well are communicated via a pressure reduction device. Reactor containment vessel. 2. The reactor containment vessel according to claim 1, wherein the pressure reduction device is equipped with a pressure relief valve. 3. The reactor containment vessel according to claim 1, wherein the pressure reduction device is equipped with a rupture disk. 4. The reactor containment vessel according to claim 1, wherein the pressure reduction device is equipped with a blowout panel.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61166285A JPS6321594A (en) | 1986-07-15 | 1986-07-15 | Nuclear reactor container |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61166285A JPS6321594A (en) | 1986-07-15 | 1986-07-15 | Nuclear reactor container |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS6321594A true JPS6321594A (en) | 1988-01-29 |
Family
ID=15828525
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP61166285A Pending JPS6321594A (en) | 1986-07-15 | 1986-07-15 | Nuclear reactor container |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6321594A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2016217771A (en) * | 2015-05-15 | 2016-12-22 | 株式会社東芝 | Operation floor confinement zone and nuclear power plant |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS56158987A (en) * | 1980-05-13 | 1981-12-08 | Nippon Atomic Ind Group Co | Device for protecting |
-
1986
- 1986-07-15 JP JP61166285A patent/JPS6321594A/en active Pending
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS56158987A (en) * | 1980-05-13 | 1981-12-08 | Nippon Atomic Ind Group Co | Device for protecting |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2016217771A (en) * | 2015-05-15 | 2016-12-22 | 株式会社東芝 | Operation floor confinement zone and nuclear power plant |
| US10706975B2 (en) | 2015-05-15 | 2020-07-07 | Kabushiki Kaisha Toshiba | Operating floor confinement and nuclear plant |
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