JPS6330598B2 - - Google Patents

Info

Publication number
JPS6330598B2
JPS6330598B2 JP54159771A JP15977179A JPS6330598B2 JP S6330598 B2 JPS6330598 B2 JP S6330598B2 JP 54159771 A JP54159771 A JP 54159771A JP 15977179 A JP15977179 A JP 15977179A JP S6330598 B2 JPS6330598 B2 JP S6330598B2
Authority
JP
Japan
Prior art keywords
reactor
liquid level
coolant
ring
shaped
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
JP54159771A
Other languages
Japanese (ja)
Other versions
JPS5682490A (en
Inventor
Kenji Azuma
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Toshiba Corp
Original Assignee
Tokyo Shibaura Electric Co Ltd
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 Tokyo Shibaura Electric Co Ltd filed Critical Tokyo Shibaura Electric Co Ltd
Priority to JP15977179A priority Critical patent/JPS5682490A/en
Publication of JPS5682490A publication Critical patent/JPS5682490A/en
Publication of JPS6330598B2 publication Critical patent/JPS6330598B2/ja
Granted 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
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 本発明は液体金属冷却型原子炉における、地震
時等の液体冷却材の飛び散り(スロツシング)を
防止した原子炉に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a liquid metal cooled nuclear reactor that prevents liquid coolant from scattering (sloshing) during an earthquake or the like.

冷体金属冷却型原子炉は第1図に示したように
原子炉容器1内に炉心2が設けられ、炉心2は冷
却材3で冷却され、冷却材3としやへいプラグ4
との間にはカバーガス空間5を有し、冷却材3は
自由液面6を持つている。
As shown in FIG. 1, a cold metal-cooled nuclear reactor has a reactor core 2 installed in a reactor vessel 1, and the reactor core 2 is cooled by a coolant 3.
There is a cover gas space 5 between them, and the coolant 3 has a free liquid level 6.

このため、炉心2を出た冷却材3はその速度ポ
テンシヤルのために自由液面6で噴流を形成し
て、この噴流により、冷却材3中にカバーガスが
巻き込まれ、1次冷却系内に入り1次冷却系機器
および炉心2に損失を与えるおそれがあるのでは
ないかと心配されていた。
For this reason, the coolant 3 leaving the core 2 forms a jet at the free liquid level 6 due to its velocity potential, and this jet entrains the cover gas into the coolant 3, causing it to enter the primary cooling system. There were concerns that there was a risk of damage to the primary cooling system equipment and core 2.

又、地震時に冷却材3の自由液面6が揺動し、
冷却材の温度が高温であることから、たとえば炉
内上部機構内ないしは周辺構造物などに厳しい熱
衝撃を与えたり、過大なスロツシング荷重が周辺
構造物に作用する等の不都合がある。
Also, the free liquid level 6 of the coolant 3 oscillates during an earthquake,
Since the temperature of the coolant is high, there are disadvantages such as severe thermal shock being applied to the inside of the upper in-furnace mechanism or surrounding structures, and excessive sloshing load being applied to surrounding structures.

そこで、従来原子炉容器1の上部を閉塞するし
やへいプラグ4からシエル構造物8により、自由
液面6下に全範囲にわたつて1枚板構造のデイツ
ププレート9を吊り下げて設置し、上記カバーガ
スの巻き込みの防止ならびに液面の揺動を防止し
ていた。
Therefore, conventionally, a dip plate 9 of a single plate structure was installed by suspending the entire range below the free liquid level 6 from the shield plug 4 that closes the upper part of the reactor vessel 1 by means of a shell structure 8. This prevents the entrainment of the cover gas and also prevents the liquid level from fluctuating.

ところで、上記手段においては、デイツププレ
ート9はしやへいプラグ4の下面よりシエル構造
物8により吊り下げられ、その周囲の固定された
1枚のプレートであり、液体金属冷却型原子炉の
高温冷却材中に設置されていて、定常時に厳しい
熱応力条件にさらされている。又原子炉の起動、
停止等による冷却材の温度変化により熱サイクル
を受けるため、厳しいクリープ、疲労損傷等を受
ける。
By the way, in the above means, the dip plate 9 is a single plate suspended from the lower surface of the shield plug 4 by the shell structure 8 and fixed around it, and is It is installed in a coolant and is exposed to severe thermal stress conditions at steady state. Also, the start-up of the nuclear reactor,
Because they are subjected to thermal cycles due to temperature changes in the coolant due to shutdowns, etc., they are subject to severe creep, fatigue damage, etc.

更に、デイツププレート9はしやへいプラグ4
の下面から吊り下げられていることから原子炉寿
命中補修が不可能であり、機器の信頼性を向上さ
せる上からも熱応力を小さく制限し、かつ、ガス
巻き込みの防止、地震時の液面揺動の防止等の機
能を十分発揮できかつ極力単純な構造とすること
が望ましい。
In addition, the deep plate 9 and the deep plug 4
Since it is suspended from the bottom of the reactor, it cannot be repaired during the life of the reactor, and in order to improve the reliability of the equipment, it is necessary to limit thermal stress to a small level, prevent gas entrainment, and reduce the liquid level during earthquakes. It is desirable to have a structure that is as simple as possible and can sufficiently perform functions such as preventing rocking.

ところが原子炉の出力増加につれて、あるいは
原子炉型式の異なる概念として考えられているタ
ンク型原子炉型式を採用する場合には、設計例に
よると原子炉容器径が10mとか21mとかになるた
め、このデイツププレート方式では、超大型重量
部品を原子炉容器内に持ちこむことになり、補修
の面一つ考えても非常に困難さを増すし、物量増
大にもつながる。かつ又大口径平板であるため一
体物構造では大きな熱応力が発生するので、多分
割構造とする必要があるが、大口径なためきわめ
て部品数が増加し構造も複雑となる等の不都合に
直面する。
However, as the output of nuclear reactors increases, or when adopting a tank-type reactor type, which is considered as a different concept of reactor type, the diameter of the reactor vessel becomes 10 m or 21 m according to design examples, so this With the dip plate method, extremely large and heavy parts are brought into the reactor vessel, making repairs extremely difficult and increasing the amount of material needed. Moreover, since it is a large-diameter flat plate, a one-piece structure would generate large thermal stress, so a multi-segment structure is required, but due to the large diameter, the number of parts increases considerably and the structure becomes complicated. do.

本発明は上記欠点を除去するためになされたも
ので、従来のデイツププレートの機能を十分維持
したまま、上記欠点を克服できる信頼性の高い原
子炉冷却材液面のスロツシングを防止した原子炉
を提供することを目的としている。
The present invention has been made in order to eliminate the above-mentioned drawbacks, and is capable of overcoming the above-mentioned drawbacks while sufficiently maintaining the functions of conventional dip plates. is intended to provide.

すなわち、本発明は原子炉容器内に収納された
炉心を冷却する冷却材の自由液面下に複数段のバ
ツフルを設けてなることを特徴とする原子炉であ
る。
That is, the present invention is a nuclear reactor characterized in that a plurality of baffles are provided below the free liquid surface of a coolant that cools a reactor core housed in a reactor vessel.

以下、第2図を参照して本発明の一実施例を詳
細に説明する。
Hereinafter, one embodiment of the present invention will be described in detail with reference to FIG.

第2図は本発明の要部のみを示したもので、第
1図と同一部分は同一部分で示してある。
FIG. 2 shows only the essential parts of the present invention, and the same parts as those in FIG. 1 are shown as the same parts.

すなわち、第2図においては原子炉容器1の内
壁面の冷却材3の液面6よりわずか下方にリング
状バツフル10,11を2段取付けた例である。
なおリング状バツフル10,11は水平でも、わ
ずかに下方傾斜させて容器1の内壁面に取り付け
ても良い。
That is, FIG. 2 shows an example in which two ring-shaped buffles 10 and 11 are installed slightly below the liquid level 6 of the coolant 3 on the inner wall surface of the reactor vessel 1.
Note that the ring-shaped buffles 10 and 11 may be attached to the inner wall surface of the container 1 either horizontally or with a slight downward slope.

第3図は本発明の他の実施例を示しており、原
子炉容器1の上部フランジ1aから垂設される円
筒状支持部材12にバツフル10,11を取り付
けた例でバツフル10,11は冷却材3の自由液
面6下に浸漬される。
FIG. 3 shows another embodiment of the present invention, in which the buttfuls 10 and 11 are attached to a cylindrical support member 12 suspended from the upper flange 1a of the reactor vessel 1, and the buttfuls 10 and 11 are cooled. The material 3 is immersed below the free liquid level 6.

ここで、第2図および第3図ともにリング状バ
ツフル3の巾寸法、段数、液面下浸漬深さ等は使
用条件に適する様設計により任意に決めることが
できる。
Here, in both FIGS. 2 and 3, the width dimension, number of stages, immersion depth below the liquid surface, etc. of the ring-shaped buffle 3 can be arbitrarily determined by design to suit the usage conditions.

しかして、自由液面は地震時に第4図に示す如
くA―B面6がA′―B′面6aへと揺動する事に
より、スロツシングが発達し過大な衝撃力を発生
せしめるため、本発明のリング状バツフルが自由
液面周辺部にあることにより、このスロツシング
の発達を阻止できる。
However, during an earthquake, the free liquid level swings from the A-B plane 6 to the A'-B' plane 6a as shown in Figure 4, and sloshing develops, generating an excessive impact force. Since the ring-shaped buffle of the invention is located around the free liquid level, the development of this sloshing can be prevented.

又従来心配されていた、地震のない通常時の自
由液面からのガス巻き込み現象に対しては、その
後の検討の結果、自由液面付近での速度ポテンシ
ヤルはきわめて小さく第1図に示す原子炉出口ノ
ズル13の高さ位置を自由液面から十分離すこと
により、実用上さしつかえない程度に防止できる
ことが明白になつた。一方一般に高速炉の設計に
おいては、万一の配管破断時の安全対策上から第
1図のl寸法を十分確保する必要があるため、自
動的にカバーガス巻き込みの問題は解消されてい
る。
Furthermore, regarding the phenomenon of gas entrainment from the free liquid level during normal times without earthquakes, which was a concern in the past, subsequent studies revealed that the velocity potential near the free liquid level is extremely small, and the nuclear reactor shown in Figure 1. It has become clear that this problem can be prevented to a practical degree by setting the height of the outlet nozzle 13 sufficiently away from the free liquid level. On the other hand, in general, when designing a fast reactor, it is necessary to ensure a sufficient l dimension in FIG. 1 for safety reasons in the event of pipe breakage, so the problem of cover gas entrainment is automatically resolved.

以上の2つの事実を組み合わせた本発明に係る
リング状バツフルは、従来のデイツププレートの
機能を十分維持しており、かつ前述の欠点を克服
できており、構造もきわめて単純な所から信頼性
の高い原子炉冷却材液面のスロツシングを防止し
た原子炉であるといえる。
The ring-shaped baffle according to the present invention, which combines the above two facts, sufficiently maintains the functions of the conventional dip plate, overcomes the above-mentioned drawbacks, and has an extremely simple structure that increases reliability. It can be said that this is a reactor that prevents sloshing of the reactor coolant liquid level.

以上説明のように、本発明はバツフルを原子炉
冷却材自由液面下の適切な位置に設置することに
より、地震時の冷却材液面のスロツシングの発達
を防止でき、周辺機器に過大な衝撃荷重を負荷す
ることもなく、又液面揺動により周辺機器にNu
温度による厳しい熱衝撃を与える心配もなくな
る。
As explained above, the present invention prevents the development of sloshing of the coolant liquid level during an earthquake by installing the Batsuful at an appropriate position below the free liquid level of the reactor coolant, thereby preventing excessive shock to peripheral equipment. There is no need to apply any load, and the fluctuation of the liquid level prevents Nu from surrounding equipment.
There is no need to worry about severe thermal shock caused by temperature.

さらに従来のデイツププレートが直面してい
た、超大径・重量部品を炉内に持ちこむことに付
随して生じた前述の諸問題点も解消される。
Furthermore, the aforementioned problems encountered with conventional dip plates associated with bringing extremely large diameter and heavy parts into the furnace are also eliminated.

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

第1図は従来の原子炉を1部概略的側面で示す
断面図、第2図および第3図は本発明に係る原子
炉の各々の実施例の要部のみを示す断面図、第4
図は本発明の効果を説明するための自由液面のス
ロツシングを示す概念図である。 1…原子炉容器、4…しやへいプラグ、10,
11…リング状バツフル、12…支持部材。
FIG. 1 is a sectional view schematically showing a part of a conventional nuclear reactor, FIGS. 2 and 3 are sectional views showing only the main parts of each embodiment of the nuclear reactor according to the present invention, and FIG.
The figure is a conceptual diagram showing sloshing of the free liquid level for explaining the effects of the present invention. 1...Reactor vessel, 4...Shiyahei plug, 10,
11...Ring-shaped buttful, 12...Supporting member.

Claims (1)

【特許請求の範囲】 1 原子炉容器内に収納された炉心を冷却する冷
却材の自由液面の直下部で原子炉出口ノズルより
上部の炉容器内の周辺部に鉛直方向に積層した複
数段の水平方向平板リング状のバツフルを設けて
なることを特徴とする原子炉。 2 前記複数段のリング状バツフルは前記原子炉
容器内の内壁面に直接取付けてあることを特徴と
する特許請求の範囲第1項記載の原子炉。 3 前記複数段のバツフル板はリング状に形成さ
れたかつしやへいプラグの下面から垂設された支
持部材に設けられてな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。
[Claims] 1. A plurality of stages stacked vertically in the periphery of the reactor vessel directly below the free liquid level of the coolant that cools the reactor core housed in the reactor vessel and above the reactor outlet nozzle. A nuclear reactor characterized by being provided with a horizontal flat ring-shaped buttful. 2. The nuclear reactor according to claim 1, wherein the plurality of ring-shaped baffles are directly attached to an inner wall surface within the reactor vessel. 3. The nuclear reactor according to claim 1, wherein the plurality of stages of buttful plates are provided on a support member that hangs down from the lower surface of a ring-shaped plug.
JP15977179A 1979-12-11 1979-12-11 Nuclear reactor Granted JPS5682490A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP15977179A JPS5682490A (en) 1979-12-11 1979-12-11 Nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP15977179A JPS5682490A (en) 1979-12-11 1979-12-11 Nuclear reactor

Publications (2)

Publication Number Publication Date
JPS5682490A JPS5682490A (en) 1981-07-06
JPS6330598B2 true JPS6330598B2 (en) 1988-06-20

Family

ID=15700896

Family Applications (1)

Application Number Title Priority Date Filing Date
JP15977179A Granted JPS5682490A (en) 1979-12-11 1979-12-11 Nuclear reactor

Country Status (1)

Country Link
JP (1) JPS5682490A (en)

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5219639A (en) * 1975-08-01 1977-02-15 Dainippon Pharmaceut Co Ltd Preparation of omega-(n-acylamino)alkyl- phosphorylethanolamines
JPS5255596U (en) * 1975-10-21 1977-04-21

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5219639A (en) * 1975-08-01 1977-02-15 Dainippon Pharmaceut Co Ltd Preparation of omega-(n-acylamino)alkyl- phosphorylethanolamines
JPS5255596U (en) * 1975-10-21 1977-04-21

Also Published As

Publication number Publication date
JPS5682490A (en) 1981-07-06

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