JPS63275992A - Cooling apparatus for nuclear reactor - Google Patents
Cooling apparatus for nuclear reactorInfo
- Publication number
- JPS63275992A JPS63275992A JP62109866A JP10986687A JPS63275992A JP S63275992 A JPS63275992 A JP S63275992A JP 62109866 A JP62109866 A JP 62109866A JP 10986687 A JP10986687 A JP 10986687A JP S63275992 A JPS63275992 A JP S63275992A
- Authority
- JP
- Japan
- Prior art keywords
- cooling
- injector
- nuclear reactor
- cooling water
- condenser
- 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
- 238000001816 cooling Methods 0.000 title claims abstract description 41
- 239000000498 cooling water Substances 0.000 claims abstract description 26
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract description 10
- 238000010586 diagram Methods 0.000 description 2
- 230000005484 gravity Effects 0.000 description 2
- 238000009835 boiling Methods 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 230000003247 decreasing effect Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000001704 evaporation Methods 0.000 description 1
- 230000008020 evaporation Effects 0.000 description 1
- 239000000835 fiber Substances 0.000 description 1
- 239000012857 radioactive material Substances 0.000 description 1
- 238000011084 recovery Methods 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
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、原子炉停止時に原子炉圧力容器から発生する
蒸気を凝縮させる原子炉冷却装置に関する。DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Industrial Application Field) The present invention relates to a nuclear reactor cooling system that condenses steam generated from a reactor pressure vessel when a nuclear reactor is shut down.
（従来の技術）
沸騰水型原子炉では、原子炉停止時においても原子炉圧
力容器内に配置された炉心における放射性物質の崩壊熱
等によって蒸気が発生するので、これによる原子炉圧力
容器の加熱及び過圧を防止する目的で蒸気を外部に導い
て冷却・凝縮させろ原子炉冷却装置が提案されている。(Prior art) In a boiling water reactor, even when the reactor is shut down, steam is generated due to the decay heat of radioactive materials in the reactor core located inside the reactor pressure vessel, and this heats the reactor pressure vessel. In order to prevent overpressure, a reactor cooling system has been proposed in which steam is guided outside to be cooled and condensed.
第２図は上述したような原子炉冷却装置の従来例を示し
ている。第２図において、原子炉建屋１０内には原子炉
圧力容器８が収納されている。そして、ｆ心ｌを収納し
た原子炉圧力容器８より上方に、内部に伝熱管束２を有
する原子炉冷却復水器３を設置し、原子炉圧力容器８内
で発生した蒸気を伝熱管束２に導き、冷却、凝縮させ、
生成した凝縮水は重力によって再び原子炉圧力容器８内
に導かれる様に成っている。一方、原子炉冷却復水器３
は冷却水３ａを貯留し、伝熱管束２から熱を吸収して沸
騰、蒸発し、生成した蒸気は蒸気管４を介して大気に放
出される。蒸発して減少した冷却水は、外部に設置した
冷却水タンク９から電動ポンプ７によって補給される。FIG. 2 shows a conventional example of a nuclear reactor cooling system as described above. In FIG. 2, a reactor pressure vessel 8 is housed within a reactor building 10. As shown in FIG. A reactor cooling condenser 3 having a heat transfer tube bundle 2 inside is installed above the reactor pressure vessel 8 housing the f core, and the steam generated in the reactor pressure vessel 8 is transferred to the heat transfer tube bundle. 2, cooled and condensed,
The generated condensed water is guided back into the reactor pressure vessel 8 by gravity. On the other hand, reactor cooling condenser 3
The cooling water 3a is stored, absorbs heat from the heat transfer tube bundle 2, boils and evaporates, and the generated steam is released to the atmosphere via the steam pipe 4. The cooling water that has decreased due to evaporation is replenished by an electric pump 7 from a cooling water tank 9 installed outside.
この電動ポンプ７の駆動用電力は、外部電力系統あるい
はディーゼル発↑１機などで構成されるなＭ、？２ｎ１
１がら供給される。なお、第２図において、彼線で示す
矢印は蒸気の流れを、実、線で示す矢印は水の流れを示
している。The driving power for this electric pump 7 is provided by an external power system or a diesel engine, right? 2n1
Supplied from 1 piece. In addition, in FIG. 2, arrows shown with vertical lines indicate the flow of steam, and arrows shown with solid lines indicate the flow of water.
（発明が解決しようとする問題点） 以上の＋１が成を有する従来の原子炉冷却装置では。(Problem to be solved by the invention) In the conventional reactor cooling system, which has the above +1.
原子炉冷却復水器は可動部分がない為に故障が少なく、
高い（＋５頼性を有するものであるが、冷却水補給の為
の電動ポンプ及び電源設備は、動的機器によって構成さ
れる為、これらの故障発生が予想され、その為に、電）
功ポンプやディーゼル発電機などの機器を複数設置して
畳重化し、信頼性を高める必要があり、従って、設備が
複維化、大型化する不都合がある。Reactor cooling condensers have fewer moving parts, so there are fewer failures.
Although it has high reliability (+5), the electric pump and power supply equipment for replenishing cooling water are composed of dynamic equipment, so it is expected that these will fail, so
It is necessary to install and overlap multiple devices such as pumps and diesel generators to improve reliability, which inconveniences the equipment to become multi-fiber and larger.
本発明はこの様な点を考慮してなされたもので、簡素か
つイ８頼性の高い冷却水補給設備を備えた原子炉冷却装
置を提供することを目的とする。The present invention has been made in consideration of these points, and an object of the present invention is to provide a nuclear reactor cooling system equipped with a simple and highly reliable cooling water supply facility.
（問題点を解決するための手段）
上記目的を達成するために、本発明においては、原子炉
圧力容器内から発生した蒸気を伝熱管を介して導入して
冷却凝縮させるツバ（子炉冷却復水器と、この原子炉冷
却復水器内で発生した蒸気を圧力制御弁を介して系外へ
弯く蒸気管と、前記冷却復水器内で発生した蒸気を駆動
源として冷却水タンクから冷却水を冷却復水器へ導くイ
ンゼクタとから成ることを特徴とする原子炉冷却装置を
提供する。(Means for Solving the Problems) In order to achieve the above object, the present invention provides a collar (sub-reactor cooling recovery system) that introduces steam generated from inside the reactor pressure vessel through a heat transfer tube and cools and condenses it. A water tank, a steam pipe that curves the steam generated in the reactor cooling condenser to the outside of the system via a pressure control valve, and a cooling water tank that uses the steam generated in the cooling condenser as a driving source. A nuclear reactor cooling system is provided, comprising an injector that guides cooling water to a cooling condenser.
（作用）
本発明に係る原子炉冷却装置においては、原子炉冷却復
水器で発生する蒸気をインゼクタに導き、これを駆動源
として冷却水タンクの冷却水を原子炉冷却復水器に供給
する。原子炉冷却復水器で発生する蒸気は、圧力制御弁
によって、インゼクタを駆動するのに敵した圧力に制御
されろ。(Function) In the reactor cooling system according to the present invention, steam generated in the reactor cooling condenser is guided to the injector, and this is used as a driving source to supply cooling water in the cooling water tank to the reactor cooling condenser. . The steam generated in the reactor cooling condenser is controlled by a pressure control valve to a pressure suitable for driving the injector.
（実施例）
以下、本発明の実施例を第１図を参照して説明する。な
お、第１図において第２図と同一部分には同一符号を付
し、その部分の構成の説明は省略する。(Example) Hereinafter, an example of the present invention will be described with reference to FIG. In FIG. 1, the same parts as those in FIG. 2 are given the same reference numerals, and the explanation of the structure of the parts will be omitted.
第１図において、原子炉圧力容器８より上方に、内部に
伝熱管束２を有する原子炉冷却復水器３を設置し原子炉
圧力容器で発生した蒸気を伝熱管束２に導き、冷却・凝
縮させ、生成した凝縮水は重力によって原子炉圧力容器
８内に導かれる。一方、原子炉冷却復水器３内には、冷
却水３ａが貯留されており、この冷却水３ａは伝熱管束
２から熱を吸収して沸騰、蒸発する。In FIG. 1, a reactor cooling condenser 3 having a heat transfer tube bundle 2 inside is installed above the reactor pressure vessel 8, and the steam generated in the reactor pressure vessel is guided to the heat transfer tube bundle 2 for cooling and cooling. The condensed water produced is guided into the reactor pressure vessel 8 by gravity. On the other hand, cooling water 3a is stored in the reactor cooling condenser 3, and this cooling water 3a absorbs heat from the heat exchanger tube bundle 2 and boils and evaporates.
さらに本発明においては、冷却水タンク９を水源とする
インゼクタ５を設け、原子炉冷却復水器３からインゼク
タ５へ連通ずる冷却水供給配管１２を設け、インゼクタ
５の吐出側は、給水配管１３を介して原子炉冷却復水器
３内に開放されている。Furthermore, in the present invention, an injector 5 is provided which uses the cooling water tank 9 as a water source, a cooling water supply pipe 12 is provided that communicates from the reactor cooling condenser 3 to the injector 5, and the discharge side of the injector 5 is connected to the water supply pipe 13. It is open to the inside of the reactor cooling condenser 3 via.
また、蒸気／Ｉ？４には、圧力制御弁６を設ける。なお
、第１図において、破線で示す矢印は蒸気の流れを、実
線で示す矢印は水の流れを示している。Also, steam/I? 4 is provided with a pressure control valve 6. In FIG. 1, arrows shown with broken lines indicate the flow of steam, and arrows shown with solid lines indicate the flow of water.
以上の構成において、原子炉冷却復水器３の内部の蒸気
圧力は圧力制御弁６によって、インゼクタ５の作動に敵
した圧力に制御され、発生する蒸気の一部はインゼクタ
５に供給され、これを駆動源として冷却水タンク９がら
冷却水を吸引、加圧し、原子炉冷却復水器３に補給する
。In the above configuration, the steam pressure inside the reactor cooling condenser 3 is controlled by the pressure control valve 6 to a pressure suitable for the operation of the injector 5, and a part of the generated steam is supplied to the injector 5. is used as a driving source to suck and pressurize cooling water from the cooling water tank 9 and supply it to the reactor cooling condenser 3.
インゼクタは、可動部分がなく、高い信頼性を有してい
る為、これを畳重化して設置する必要はなく、もって簡
素な設備となる。Since the injector has no moving parts and has high reliability, there is no need to install it in a folded manner, resulting in a simple equipment.
また、原子炉冷却復水器にて発生する蒸気を駆動源とす
る為、電源設備などの外部動力供給設備が不要となり、
設備がＮ素化されると共に、外部動力の喪失による機能
喪失と言う事態の発生がない事から、更に信頼性を向上
させることができる。In addition, since the steam generated in the reactor cooling condenser is used as the driving source, external power supply equipment such as power supply equipment is not required.
Since the equipment is N-containing and there is no loss of functionality due to loss of external power, reliability can be further improved.
以上、説明したように本発明によれば、冷却水供給にイ
ンゼクタを使用する為、設備が簡素化されるとともにイ
４頼性の高い原子炉冷却装置を得ろことができる。As described above, according to the present invention, since an injector is used for supplying cooling water, the equipment is simplified and a highly reliable reactor cooling system can be obtained.
第１図は本発明の一実施例を示す原子炉冷却装置の系統
図、第２図は原子炉冷却装置の従来例を示す系統図であ
る。
２・・・伝熱管束 ３・・原子炉冷却復水器４
・・・蒸気管 ５・・・インゼクタ６・・・
圧力制御弁 ８・・・ＤＸ子炉圧カ容器９・・・
冷却水タンク
代理人 昇理士 則 近 憲 佑
同 第子丸 健
第１図FIG. 1 is a system diagram of a nuclear reactor cooling system showing one embodiment of the present invention, and FIG. 2 is a system diagram showing a conventional example of a nuclear reactor cooling system. 2...Heat transfer tube bundle 3...Reactor cooling condenser 4
...Steam pipe 5...Injector 6...
Pressure control valve 8...DX child reactor pressure vessel 9...
Cooling water tank agent Nori Chika Ken Yudo Daishimaru Ken Figure 1
Claims (1)
して導入して冷却凝縮させる原子炉冷却復水器と、この
原子炉冷却復水器内で発生した蒸気を圧力制御弁を介し
て系外へ導く蒸気管と、前記冷却復水器内で発生した蒸
気を駆動源として冷却水タンクから冷却水を冷却復水器
へ導くインゼクタとから成ることを特徴とする原子炉冷
却装置。(1) A reactor cooling condenser that introduces steam generated from inside the reactor pressure vessel via a heat transfer tube and cools and condenses it; A nuclear reactor cooling system comprising: a steam pipe that guides the cooling water to the outside of the system; and an injector that uses steam generated in the cooling condenser as a driving source to guide cooling water from a cooling water tank to the cooling condenser.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62109866A JPS63275992A (en) | 1987-05-07 | 1987-05-07 | Cooling apparatus for nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62109866A JPS63275992A (en) | 1987-05-07 | 1987-05-07 | Cooling apparatus for nuclear reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS63275992A true JPS63275992A (en) | 1988-11-14 |
Family
ID=14521183
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP62109866A Pending JPS63275992A (en) | 1987-05-07 | 1987-05-07 | Cooling apparatus for nuclear reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS63275992A (en) |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH02268295A (en) * | 1989-03-20 | 1990-11-01 | General Electric Co <Ge> | Heat removing system for containment vessel |
| JP2012013558A (en) * | 2010-07-01 | 2012-01-19 | Hitachi-Ge Nuclear Energy Ltd | Isolation cooling system of nuclear power plant |
| JP2013104729A (en) * | 2011-11-11 | 2013-05-30 | Hitachi-Ge Nuclear Energy Ltd | Nuclear reactor core cooling system and nuclear power plant facility equipped with the same |
| JP2015531492A (en) * | 2012-10-12 | 2015-11-02 | コリア ハイドロ アンド ニュークリア パワー カンパニー リミティッド | Water replenisher for driven auxiliary water system at nuclear power plant |
| JP2015534649A (en) * | 2012-10-12 | 2015-12-03 | コリア ハイドロ アンド ニュークリア パワー カンパニー リミティッド | Water replenisher for driven auxiliary water system at nuclear power plant |
-
1987
- 1987-05-07 JP JP62109866A patent/JPS63275992A/en active Pending
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH02268295A (en) * | 1989-03-20 | 1990-11-01 | General Electric Co <Ge> | Heat removing system for containment vessel |
| JP2012013558A (en) * | 2010-07-01 | 2012-01-19 | Hitachi-Ge Nuclear Energy Ltd | Isolation cooling system of nuclear power plant |
| JP2013104729A (en) * | 2011-11-11 | 2013-05-30 | Hitachi-Ge Nuclear Energy Ltd | Nuclear reactor core cooling system and nuclear power plant facility equipped with the same |
| JP2015531492A (en) * | 2012-10-12 | 2015-11-02 | コリア ハイドロ アンド ニュークリア パワー カンパニー リミティッド | Water replenisher for driven auxiliary water system at nuclear power plant |
| JP2015534649A (en) * | 2012-10-12 | 2015-12-03 | コリア ハイドロ アンド ニュークリア パワー カンパニー リミティッド | Water replenisher for driven auxiliary water system at nuclear power plant |
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