JPS58876Y2 - Pressurizing device for reactor coolant - Google Patents

Pressurizing device for reactor coolant

Info

Publication number
JPS58876Y2
JPS58876Y2 JP1978099979U JP9997978U JPS58876Y2 JP S58876 Y2 JPS58876 Y2 JP S58876Y2 JP 1978099979 U JP1978099979 U JP 1978099979U JP 9997978 U JP9997978 U JP 9997978U JP S58876 Y2 JPS58876 Y2 JP S58876Y2
Authority
JP
Japan
Prior art keywords
electric heater
container
light water
vessel
pressure
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.)
Expired
Application number
JP1978099979U
Other languages
Japanese (ja)
Other versions
JPS5516489U (en
Inventor
耕治 桑原
潤一 柏井
Original Assignee
三菱重工業株式会社
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by 三菱重工業株式会社 filed Critical 三菱重工業株式会社
Priority to JP1978099979U priority Critical patent/JPS58876Y2/en
Publication of JPS5516489U publication Critical patent/JPS5516489U/ja
Application granted granted Critical
Publication of JPS58876Y2 publication Critical patent/JPS58876Y2/en
Expired legal-status Critical Current

Links

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Description

【考案の詳細な説明】 本考案は、原子炉特に加圧木型原子炉(以下PWRとい
う。
[Detailed Description of the Invention] The present invention is a nuclear reactor, particularly a pressurized wooden nuclear reactor (hereinafter referred to as PWR).

)の冷却材の圧力を調節する加圧装置に関する。) relates to a pressurizing device for adjusting the pressure of a coolant.

PWRにおいては、原子炉炉心を冷却すると共に炉心内
で発生した核反応熱を原子炉容器外に搬出し最終的に発
電機駆動タービンを駆動するための蒸気を発生させる冷
却材は、後述する加圧装置(以下加圧器という。
In a PWR, the coolant that cools the reactor core and carries the nuclear reaction heat generated within the reactor core out of the reactor vessel to generate steam that ultimately drives the generator drive turbine is used as a cooling agent, which will be described later. Pressure device (hereinafter referred to as pressurizer).

)によって所定の圧力に保持される。) is maintained at a predetermined pressure.

第1図は、従来の加圧器の概略構造を示したものである
FIG. 1 shows a schematic structure of a conventional pressurizer.

第1図において、図示しない原子炉冷却系に連通管01
を介して連絡した容器02の上部には、図示しない冷却
水供給装置に連絡したスプレィ装置03が設けられてい
る。
In Figure 1, a communication pipe 01 is connected to the reactor cooling system (not shown).
A spray device 03, which is connected to a cooling water supply device (not shown), is provided on the top of the container 02, which is connected to the cooling water supply device (not shown).

容器02内の下方は、冷却材通常軽水04で満たされ、
父上方は蒸気、を含んだ気体05で満たされでいて、容
器02の下部壁を貫ぬいて多数の電気ヒータ06が設け
られ、その貫通部は封止されている。
The lower part of the container 02 is filled with a coolant, usually light water 04,
The upper part of the container 02 is filled with a gas 05 containing steam, and a number of electric heaters 06 are provided penetrating the lower wall of the container 02, and the penetrating portions thereof are sealed.

図示の従来装置において、原子炉冷却材を加圧するとき
は、電気ヒータ06によって軽水04を加熱して蒸気を
発生せしめ、蒸気05の量を増して行なう。
In the illustrated conventional device, when pressurizing the reactor coolant, light water 04 is heated by electric heater 06 to generate steam, and the amount of steam 05 is increased.

逆に冷却材の圧力が上昇しすぎてその圧力を低下させる
ときは、スプレィ装置03より冷却水を噴出して気体0
5中の蒸気を凝縮してその体積を減少することによって
行なう。
On the other hand, if the pressure of the coolant increases too much and you want to lower it, the spray device 03 will spray out cooling water to remove the gas.
This is done by condensing the vapor in 5 to reduce its volume.

しかるに、前述した従来の装置では、次のような不具合
であった。
However, the conventional device described above has the following problems.

(イ)電気ヒータ06による伝熱形態がプール沸騰であ
るため熱負荷を大きくとれない。
(a) Since the heat transfer form by the electric heater 06 is pool boiling, a large heat load cannot be achieved.

(ロ)容器02が大きいため、多数の電熱ヒータ06を
貫通封着することは、高度な製作技術を要すると共に消
費時間も多大になって経済的にも不利である。
(b) Since the container 02 is large, sealing a large number of electric heaters 06 through the container requires sophisticated manufacturing technology and consumes a lot of time, which is economically disadvantageous.

(ハ)使用中電気ヒータ06の先端が軽水04の液面よ
り露出し、このような場合に通電すると電気ヒータ06
が過熱し焼損することがあり、又、これを避けようとす
ると適切な圧力制御ができない。
(c) During use, the tip of the electric heater 06 is exposed from the surface of the light water 04, and in such a case, if the electric heater 06 is turned on, the electric heater 06
may overheat and burn out, and if you try to avoid this, you will not be able to properly control the pressure.

本考案は、前記した従来装置の不具合を解消するために
なされたものである。
The present invention has been made in order to solve the above-mentioned problems of the conventional device.

以下図示の実施例に基づいて本考案を説明する。The present invention will be explained below based on the illustrated embodiments.

第2図において、図示しない原子炉冷却系に連通管1に
連絡した圧力容器2の天井部には、図示しない冷却水供
給装置に連絡したスプレィ装置3が設けられている。
In FIG. 2, a spray device 3 connected to a cooling water supply device (not shown) is provided on the ceiling of a pressure vessel 2 which is connected to a communication pipe 1 to a reactor cooling system (not shown).

圧力容器2の下部は、冷却材即ち軽水4で満たされ、上
部は水蒸気を含む気体5で満たされている。
The lower part of the pressure vessel 2 is filled with a coolant, ie, light water 4, and the upper part is filled with a gas 5 containing water vapor.

圧力容器2に比して低位置に設置された加熱装置10の
容器7内には、棒状の電気ヒータ6が林設され、同電気
ヒータ6は図示しない電源に連結している。
A rod-shaped electric heater 6 is installed in the container 7 of the heating device 10, which is installed at a lower position than the pressure container 2, and the electric heater 6 is connected to a power source (not shown).

容器7の上部は、導管8を介して圧力容器2の気体部に
連絡すると共に容器7の下部は導管9を介して圧力容器
2の下部に連絡している。
The upper part of the vessel 7 communicates with the gas part of the pressure vessel 2 via a conduit 8, and the lower part of the vessel 7 communicates with the lower part of the pressure vessel 2 via a conduit 9.

前記した構成の本実施例の作用を説明する。The operation of this embodiment having the above-mentioned configuration will be explained.

冷却材の圧力を低下するときの作用は、前記従来装置と
同じなので説明を省略する。
The operation when lowering the pressure of the coolant is the same as that of the conventional device, so a description thereof will be omitted.

冷却材を加圧するときは、電気ヒータ6に通電し、容器
7内の軽水を加熱し沸騰させる。
When pressurizing the coolant, the electric heater 6 is energized to heat and boil the light water in the container 7.

これにより容器7内の軽水は、気液2相状態となり比重
が減少して圧力容器2内の軽水との間に比量差が生じて
矢印の方向に自然循環流が発生する。
As a result, the light water in the container 7 enters a gas-liquid two-phase state, and its specific gravity decreases, creating a difference in specific volume between it and the light water in the pressure container 2, and a natural circulation flow occurs in the direction of the arrow.

導管8から圧力容器2内に導入された2相の軽水の液分
は下方に落下して軽水4に混入する。
The two-phase light water liquid introduced into the pressure vessel 2 from the conduit 8 falls downward and mixes with the light water 4.

前記2相の軽水の気体部すなわち水蒸気は、圧力容器2
の上方に累積し、気体5の圧力が上昇し、原子炉冷却材
を加圧する。
The gaseous portion of the two-phase light water, that is, water vapor, is transferred to the pressure vessel 2.
, the pressure of gas 5 increases and pressurizes the reactor coolant.

前記した自然循環流により、電気ヒータ6と軽水との熱
伝達は、強制対流熱伝達となる。
Due to the natural circulation flow described above, heat transfer between the electric heater 6 and the light water is forced convection heat transfer.

前記した構成及び作用を有する本実施例によれば、軽水
が電気ヒータ6の周囲を流動されるので、熱抵抗が低下
して電気ヒータ6の熱負荷を大きくとれると共に加熱装
置10が圧力容器2より低位置にあるので、圧力容器2
内の軽水4の量が著しく少くなっても電気ヒータ6は常
に軽水中にあるので、電気ヒータ6の過熱による焼損を
防止することができる。
According to this embodiment having the above-described configuration and operation, since light water is flowed around the electric heater 6, the thermal resistance is reduced and the thermal load on the electric heater 6 can be increased, and the heating device 10 is connected to the pressure vessel 2. Because it is located at a lower position, pressure vessel 2
Since the electric heater 6 is always in the light water even if the amount of light water 4 in the tank becomes extremely small, it is possible to prevent the electric heater 6 from being burnt out due to overheating.

更に容器7を大きな圧力容器2と別体にしたので、電気
ヒータ6の設置等の製作が非常に容易になり、製作コス
トの低減及び信頼性の向上を併せ達成することができる
Furthermore, since the container 7 is made separate from the large pressure vessel 2, manufacturing such as installation of the electric heater 6 becomes extremely easy, and it is possible to reduce manufacturing costs and improve reliability.

第3図は、本考案の別の実施例を示したもので、前記第
1の実施例(第2図に示す)と異なる所は、導管9の途
中に循環ポンプ11を設けたところで、他は同じである
FIG. 3 shows another embodiment of the present invention, which differs from the first embodiment (shown in FIG. 2) in that a circulation pump 11 is provided in the middle of the conduit 9; are the same.

循環ポンプ11により矢印に示された方向の軽水の循環
流を更に確実にせんとするもので、その作用効果は前記
第1の実施例のものと同じで゛ある。
The circulating flow of light water in the direction indicated by the arrow is further ensured by the circulation pump 11, and its operation and effect are the same as those of the first embodiment.

【図面の簡単な説明】[Brief explanation of the drawing]

第1図は、従来装置の概略図、第2図は、本考案の実施
例を示す系統図、第3図は、本考案の他の実施例を示す
系統図である。 1・・・・・・連通管、2・・・・・・圧力容器、6・
・・・・・電気ヒータ、7・・・・・・容器、8,9・
・・・・・導管、10・・・・・・加熱装置。
FIG. 1 is a schematic diagram of a conventional device, FIG. 2 is a system diagram showing an embodiment of the present invention, and FIG. 3 is a system diagram showing another embodiment of the present invention. 1... Communication pipe, 2... Pressure vessel, 6...
...Electric heater, 7...Container, 8,9.
... Conduit, 10 ... Heating device.

Claims (1)

【実用新案登録請求の範囲】[Scope of utility model registration request] 下部が原子炉冷却系に連通し上部に冷却用スプレィ装置
を具備した圧力容器及び同容器の下部と中央部とに夫々
連通した導管を有し同容器に比して相対的低位置に配設
された電気加熱装置を有してなることを特徴とする原子
炉冷却材用加圧装置。
A pressure vessel whose lower part communicates with the reactor cooling system and which is equipped with a cooling spray device at the upper part, and a conduit that communicates with the lower part and the center of the vessel, respectively, and is located at a relatively low position compared to the vessel. 1. A pressurizing device for a nuclear reactor coolant, comprising an electric heating device.
JP1978099979U 1978-07-20 1978-07-20 Pressurizing device for reactor coolant Expired JPS58876Y2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1978099979U JPS58876Y2 (en) 1978-07-20 1978-07-20 Pressurizing device for reactor coolant

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP1978099979U JPS58876Y2 (en) 1978-07-20 1978-07-20 Pressurizing device for reactor coolant

Publications (2)

Publication Number Publication Date
JPS5516489U JPS5516489U (en) 1980-02-01
JPS58876Y2 true JPS58876Y2 (en) 1983-01-08

Family

ID=29037220

Family Applications (1)

Application Number Title Priority Date Filing Date
JP1978099979U Expired JPS58876Y2 (en) 1978-07-20 1978-07-20 Pressurizing device for reactor coolant

Country Status (1)

Country Link
JP (1) JPS58876Y2 (en)

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5861904U (en) * 1981-10-22 1983-04-26 高木産業株式会社 Cylinder with built-in position detector
US4437385A (en) * 1982-04-01 1984-03-20 Deere & Company Electrohydraulic valve system
JPS6327705U (en) * 1986-08-07 1988-02-23

Also Published As

Publication number Publication date
JPS5516489U (en) 1980-02-01

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