JPH0656422B2 - Double tank type fast breeder reactor - Google Patents

Double tank type fast breeder reactor

Info

Publication number
JPH0656422B2
JPH0656422B2 JP61060580A JP6058086A JPH0656422B2 JP H0656422 B2 JPH0656422 B2 JP H0656422B2 JP 61060580 A JP61060580 A JP 61060580A JP 6058086 A JP6058086 A JP 6058086A JP H0656422 B2 JPH0656422 B2 JP H0656422B2
Authority
JP
Japan
Prior art keywords
cooling system
tank
coolant
secondary cooling
reactor vessel
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 - Lifetime
Application number
JP61060580A
Other languages
Japanese (ja)
Other versions
JPS62218890A (en
Inventor
禎男 服部
武志 仁田脇
洋二 柴田
昇 中尾
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.)
Central Research Institute of Electric Power Industry
Hitachi Ltd
Original Assignee
Central Research Institute of Electric Power Industry
Hitachi 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 Central Research Institute of Electric Power Industry, Hitachi Ltd filed Critical Central Research Institute of Electric Power Industry
Priority to JP61060580A priority Critical patent/JPH0656422B2/en
Publication of JPS62218890A publication Critical patent/JPS62218890A/en
Publication of JPH0656422B2 publication Critical patent/JPH0656422B2/en
Anticipated expiration legal-status Critical
Expired - Lifetime 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

  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
  • Other Liquid Machine Or Engine Such As Wave Power Use (AREA)

Description

【発明の詳細な説明】 〔産業上の利用分野〕 本発明は、二重タンク型高速増殖炉に係り、特に、原子
炉容器の熱保護対策に関するものである。
Description: TECHNICAL FIELD The present invention relates to a double tank type fast breeder reactor, and more particularly to a thermal protection measure for a reactor vessel.

〔従来の技術〕[Conventional technology]

タンク型高速増殖炉の一般的な系統構成を第3図に示
す。図において、1は原子炉容器、13はルーフデツ
キ、14は炉心である。原子炉容器1内の1次冷却系循
環ポンプ4により循環される1次冷却材は、炉心14を
冷却後、中間熱交換器3に入り、2次冷却材15に熱を
伝える。2次冷却材15は、2次冷却系循環ポンプ6に
より循環され、ホツトレグ配管16を通つて蒸気発生器
5にこの熱を輸送し、蒸気発生器5で熱交換する。ここ
で発生した蒸気は、主蒸気管17を通つてタービン18
へ流入する。
A general system configuration of a tank type fast breeder reactor is shown in FIG. In the figure, 1 is a reactor vessel, 13 is a roof deck, and 14 is a reactor core. The primary coolant circulated by the primary cooling system circulation pump 4 in the reactor vessel 1 cools the core 14 and then enters the intermediate heat exchanger 3 to transfer heat to the secondary coolant 15. The secondary coolant 15 is circulated by the secondary cooling system circulation pump 6, transports this heat to the steam generator 5 through the hot-leg piping 16, and exchanges heat with the steam generator 5. The steam generated here passes through the main steam pipe 17 and the turbine 18
Flow into.

このような構成のタンク型FBRにおいては、配置上の
必要性から、1次冷却材からの熱を輸送する2次冷却系
配管を長く引き廻すことが余儀なくされ、2次冷却系配
管および付属設備建設費が増大し、また、2次冷却系設
備を設置するためのスペースを必要とするという問題が
ある。
In the tank type FBR having such a configuration, the secondary cooling system pipe for transporting the heat from the primary coolant is unavoidably laid for a long time due to the necessity of arrangement, and the secondary cooling system pipe and the auxiliary equipment are attached. There are problems that the construction cost increases and that a space for installing the secondary cooling system equipment is required.

このようなタンク型炉の問題を解決し、その建設費を低
減するための方策の一つとして、特願昭58−1671
26号で提案された二重タンク型高速増殖炉がある。
As one of the measures for solving such a problem of the tank type furnace and reducing the construction cost thereof, Japanese Patent Application No. 58-1671.
There is a double tank type fast breeder reactor proposed in No. 26.

この二重タンク型高速増殖炉の一例を第4図に示す。本
例においては、原子炉容器(1次冷却系タンク)1の外
側に2次冷却系タンク2を設置し、原子炉容器1と同
様、ルーフデツキ13から吊り下げてある。そして、原
子炉容器1と2次冷却系タンク2との間のアニユラス部
に2次冷却系循環ポンプ6と蒸気発生器5とを配設し、
その間に2次冷却材15を満してある。2次冷却系循環
ポンプ6と蒸気発生器5とは、1次系機器と同様に、ル
ーフデツキ13から吊り下げてあり、2次冷却材流路構
成上、中間熱交換器3と同一の基数設けてある。
An example of this double tank type fast breeder reactor is shown in FIG. In this example, the secondary cooling system tank 2 is installed outside the reactor vessel (primary cooling system tank) 1 and is hung from the roof deck 13 like the reactor vessel 1. The secondary cooling system circulation pump 6 and the steam generator 5 are arranged in the annulus portion between the reactor vessel 1 and the secondary cooling system tank 2.
Meanwhile, the secondary coolant 15 is filled. The secondary cooling system circulation pump 6 and the steam generator 5 are suspended from the roof deck 13 like the primary system device, and the same radix as the intermediate heat exchanger 3 is provided in the secondary coolant flow path configuration. There is.

2次冷却系循環ポンプ6により2次冷却系タンク2内か
ら吸い上げられた2次冷却材15は、コールドレグ配管
19を通つてルーフデツキ13上部まで立ち上がり、中
間熱交換器3の2次側入口ノズルに接続される。中間熱
交換器3の2次側に入つた2次冷却材15は、中間熱交
換器3内で1次側から熱を受けた後、2次側出口ノズル
よりホツトレグ配管16を通り、蒸気発生器5に入る。
蒸気発生器5内では、2次冷却材15は、水と蒸気側に
熱を伝えて流下する。流下した2次冷却材15は、2次
冷却系タンク2内へ戻り、タンク2内を通つて再び2次
冷却系循環ポンプ6に吸い上げられて循環する。
The secondary cooling material 15 sucked up from the secondary cooling system tank 2 by the secondary cooling system circulation pump 6 rises to the upper part of the roof deck 13 through the cold leg pipe 19 and reaches the secondary side inlet nozzle of the intermediate heat exchanger 3. Connected. The secondary coolant 15 that has entered the secondary side of the intermediate heat exchanger 3 receives heat from the primary side in the intermediate heat exchanger 3 and then passes through the hot-leg piping 16 from the secondary outlet nozzle to generate steam. Enter vessel 5.
In the steam generator 5, the secondary coolant 15 transfers heat to the water and steam sides and flows down. The secondary coolant 15 that has flowed down returns to the inside of the secondary cooling system tank 2, passes through the inside of the tank 2, and is sucked up by the secondary cooling system circulation pump 6 again and circulated.

このような構成にしてあるから、2次冷却系タンク2の
壁面に接する2次冷却材15は、どの領域でも比較的低
温であり、2次冷却系タンク2の健全性保持に寄与す
る。
With such a configuration, the secondary coolant 15 in contact with the wall surface of the secondary cooling system tank 2 has a relatively low temperature in any region and contributes to maintaining the soundness of the secondary cooling system tank 2.

2次冷却系における高温部は、中間熱交換器3の2次側
出口ノズルから蒸気発生器5の入口配管部までと、蒸気
発生器5の伝熱管部廻りのナトリウム流路のみに限られ
る。
The high temperature part in the secondary cooling system is limited to the secondary outlet nozzle of the intermediate heat exchanger 3 to the inlet pipe part of the steam generator 5 and only the sodium flow passage around the heat transfer tube part of the steam generator 5.

2次冷却性タンク2内に上記のごとく各機器を配設する
と、蒸気発生器5から循環ポンプ6への配管が不要とな
り、他の2次冷却系配管も極めて短かくできる。また、
二重タンク型構成としたことにより、従来必要とされて
いた充填ドレン系やオーバーフロー系統等の付属設備が
不要となり、2次冷却系カバーガス圧制御系も大幅に簡
素化でき、大幅なコスト低減につながる。
When each device is arranged in the secondary cooling tank 2 as described above, piping from the steam generator 5 to the circulation pump 6 is not required, and other secondary cooling system piping can be made extremely short. Also,
By adopting a double tank type configuration, auxiliary equipment such as a filling drain system and an overflow system, which were conventionally required, are no longer required, and the secondary cooling system cover gas pressure control system can be greatly simplified, resulting in a significant cost reduction. Leads to.

ただ、こと特願昭58−167126号においては、1
次冷却材20と2次冷却材15とに接液する原子炉容器
1の冷却対策についての配慮がなかつた。
However, in Japanese Patent Application No. 58-167126, 1
No consideration was given to measures for cooling the reactor vessel 1 in contact with the secondary coolant 20 and the secondary coolant 15.

〔発明が解決しようとする問題点〕[Problems to be solved by the invention]

第5図に、上記二重タンク型高速増殖炉の中間熱交換器
3および蒸気発生器5付近の冷却材液位関係の一例を示
す。
FIG. 5 shows an example of the coolant liquid level relationship in the vicinity of the intermediate heat exchanger 3 and the steam generator 5 of the double tank type fast breeder reactor.

本図に示すように、原子炉容器1内では、中間熱交換器
3の1次側圧力損失によつて、熱交換前の高温の1次冷
却材21と、熱交換後の低温の1次冷却材22との間
に、ΔH分の液位差が生ずる。同様に、2次冷却系タ
ンク2内では、蒸気発生器5の2次冷却材側圧力損失に
よつて、熱交換前の高温の2次冷却材23と、熱交換後
の低温の2次冷却材24との間に、ΔH分の液位差が
生ずる。
As shown in the figure, in the reactor vessel 1, due to the primary side pressure loss of the intermediate heat exchanger 3, the high temperature primary coolant 21 before heat exchange and the low temperature primary coolant after heat exchange A liquid level difference of ΔH 1 minute occurs between the coolant 22 and the coolant. Similarly, in the secondary cooling system tank 2, due to the pressure loss on the secondary coolant side of the steam generator 5, the high temperature secondary coolant 23 before the heat exchange and the low temperature secondary coolant after the heat exchange. A liquid level difference of ΔH 2 is generated between the material 24 and the material 24.

これらの液位差のために、原子炉容器1の上部は、高温
の1次冷却材21および高温の2次冷却材23との両方
からの熱輻射により、著しく高温になるおそれがある。
したがつて、原子炉容器1の健全性を確保するために
は、何らかの熱保護対策が必要となる。
Due to these liquid level differences, the upper part of the reactor vessel 1 may become extremely hot due to heat radiation from both the high-temperature primary coolant 21 and the high-temperature secondary coolant 23.
Therefore, in order to ensure the soundness of the reactor vessel 1, some heat protection measure is required.

本発明の目的は、充分な熱保護対策を施し、原子炉容器
の健全性を確保した二重タンク型高速増殖炉を提供する
ことである。
An object of the present invention is to provide a double tank type fast breeder reactor in which the soundness of the reactor vessel is ensured by taking sufficient heat protection measures.

〔問題点を解決するための手段〕[Means for solving problems]

本発明は、上記目的を達成するために、2次主循環ポン
プ出口配管から2次冷却系タンク内への戻り配管を設
け、この戻り配管からの低温の2次冷却材を貯留し底部
から2次冷却系タンク内に放出するバケツトを原子炉容
器外側面に設けた二重タンク型高速増殖炉を提案するも
のである。
In order to achieve the above object, the present invention provides a return pipe from the outlet pipe of the secondary main circulation pump to the inside of the secondary cooling system tank, and stores the low-temperature secondary coolant from the return pipe, We propose a double tank type fast breeder reactor in which a bucket for discharging into the secondary cooling system tank is provided on the outer surface of the reactor vessel.

また、このバケツト内の2次冷却材の液面と、熱しやへ
い効果に寄与する2次冷却材の流量とを調節するための
流量調節弁を前記戻り配管に配置する構造も提案する。
Also proposed is a structure in which a flow control valve for adjusting the liquid level of the secondary coolant in the bucket and the flow rate of the secondary coolant that contributes to the heat and heat effect is arranged in the return pipe.

〔作用〕[Action]

本発明において、2次主循環ポンプ出口配管から分岐
し、2次冷却系タンクに戻つてきた低温の2次冷却材
は、原子炉容器の外壁に設けられたバケツトに一時貯留
され、バケツト底部に設けた出口孔から2次冷却系タン
ク内のコールドプールに放出される。この低温の2次冷
却材が、蒸気発生器内の高温の2次冷却材から原子炉容
器への熱輻射に対する熱しやへいの役目を果すと同時
に、1次冷却材からの熱輻射により加熱された原子炉容
器を冷却するから、原子炉容器の異常な温度上昇が妨げ
られる。
In the present invention, the low-temperature secondary coolant that has branched from the outlet pipe of the secondary main circulation pump and returned to the secondary cooling system tank is temporarily stored in a bucket provided on the outer wall of the reactor vessel, and is stored at the bottom of the bucket. It is discharged to the cold pool in the secondary cooling system tank from the provided exit hole. This low-temperature secondary coolant serves as a heat shield against the heat radiation from the high-temperature secondary coolant in the steam generator to the reactor vessel, and at the same time is heated by the heat radiation from the primary coolant. Moreover, since the reactor vessel is cooled, an abnormal temperature rise in the reactor vessel is prevented.

さらに、戻り配管途中に設置してある流量調節弁を調整
すると、バケツト内の低温2次冷却材の液位および流量
を調節し、熱しやへい効果をコントロールできる。
Furthermore, by adjusting the flow rate control valve installed in the middle of the return pipe, the liquid level and flow rate of the low temperature secondary coolant in the bucket can be adjusted to control the heat and heat effect.

〔実施例〕〔Example〕

次に、本発明の一実施例を第1図および第2図により説
明する。
Next, an embodiment of the present invention will be described with reference to FIGS. 1 and 2.

第1図は本発明の一実施例を示す二重タンク型高速増殖
炉の冷却系統の概略系統図である。中間熱交換器3、1
次主冷却系循環ポンプ4等の1次主冷却系主要機器を収
納した原子炉容器1の外側にさらに2次冷却系タンク2
を設け、原子炉容器1との間のアニユラス部に蒸気発生
器5、2次冷却系循環ポンプ6等の2次主冷却系主要機
器を収納してある。
FIG. 1 is a schematic system diagram of a cooling system of a double tank type fast breeder reactor showing an embodiment of the present invention. Intermediate heat exchanger 3, 1
A secondary cooling system tank 2 is further provided outside the reactor vessel 1 containing the primary primary cooling system main equipment such as the secondary main cooling system circulation pump 4.
The steam generator 5, the secondary cooling system circulation pump 6 and other main secondary cooling system equipment are housed in the annulus portion between the reactor vessel 1.

2次冷却材は、2次主循環ポンプ6で昇圧されたのち、
中間熱交換器3で1次冷却材により加熱され、蒸気発生
器5に流入し、水蒸気により冷却されたのち、2次冷却
系タンク2内に戻り、再び2次主循環ポンプ6で昇圧さ
れる。
After the secondary coolant is pressurized by the secondary main circulation pump 6,
It is heated by the primary coolant in the intermediate heat exchanger 3, flows into the steam generator 5, is cooled by steam, and then returns to the secondary cooling system tank 2 and is pressurized again by the secondary main circulation pump 6. .

本発明は、上記の2次冷却材主循環ライン中、2次主循
環ポンプ出口配管7から、途中に流量調節弁9の設置し
た2次冷却系タンク2内への戻り配管8を設け、さら
に、原子炉容器1の外周には上記戻り配管8からの低温
の2次冷却材を貯留するためのバケツト10を設けたこ
とを特徴とする。
The present invention provides a return pipe 8 from the secondary main circulation pump outlet pipe 7 into the secondary cooling system tank 2 in which a flow rate control valve 9 is installed in the secondary coolant main circulation line. A bucket 10 for storing the low temperature secondary coolant from the return pipe 8 is provided on the outer periphery of the reactor vessel 1.

2次主循環ポンプ出口配管7から分岐し、2次冷却系タ
ンク2内へ戻つてきた低温の2次冷却材は、バケツト1
0に一時貯留され、バケツト壁に設けた出口孔11から
2次冷却系タンク2内に放出される。このため、バケツ
ト10の低温の2次冷却材が、蒸気発生器5内の高温の
2次冷却材から原子炉容器1に流れる高熱流に対して熱
しやへいの役目を果すとともに、原子炉容器を冷却する
こととなり、原子炉容器1の異常な温度上昇が妨げられ
る。
The low-temperature secondary coolant that has branched from the secondary main circulation pump outlet pipe 7 and returned to the inside of the secondary cooling system tank 2 is the bucket 1.
It is temporarily stored at 0 and is discharged into the secondary cooling system tank 2 through the outlet hole 11 provided in the bucket wall. Therefore, the low-temperature secondary coolant of the bucket 10 plays a role of heat and heat against the high heat flow flowing from the high-temperature secondary coolant in the steam generator 5 to the reactor vessel 1, and Will be cooled, and an abnormal temperature rise of the reactor vessel 1 will be prevented.

バケツト10内の2次冷却材の液面と、熱しやへい効果
に寄与する低温2次冷却材の流量とは、流量調節弁9に
よつて調節できる。
The liquid level of the secondary coolant in the bucket 10 and the flow rate of the low temperature secondary coolant that contributes to the heat and heat effect can be adjusted by the flow rate control valve 9.

第2図に、原子炉容器1外側面付近の構造例を示す。2
次主循環ポンプ6および蒸気発生器5と原子炉容器1と
の間には、2次主循環ポンプ出口配管からの戻り配管8
が接続されたバケツト10が設けられており、このバケ
ツト10の底部には貯留冷却材の出口孔11が設けられ
ている。2次主循環ポンプ出口の戻り配管8は、バケツ
ト10内での分配管12に接続してある。
FIG. 2 shows a structural example near the outer surface of the reactor vessel 1. Two
Between the secondary main circulation pump 6 and the steam generator 5 and the reactor vessel 1, a return pipe 8 from the secondary main circulation pump outlet pipe is provided.
Is provided with an outlet hole 11 for the stored cooling material at the bottom of the bucket 10. The return pipe 8 at the outlet of the secondary main circulation pump is connected to the distribution pipe 12 in the bucket 10.

第1図にも示したように、2次主循環ポンプ出口から戻
り配管8を通して戻つてくる低温の2次冷却材の一部は
分配管12によりバケツト10内に一様に分配され、バ
ケツト壁下部に設けた出口孔11から2次冷却系タンク
内に流出する。バケツト10内の低温2次冷却材の液面
は、戻り配管8からの流入量と出口孔11からの流出量
のバランスにより定まるから、戻り配管8上の流量調節
弁9を適度に調整すると、バケツト10内の液位および
流量を適切に設定できる。
As shown in FIG. 1, a part of the low temperature secondary coolant returning from the outlet of the secondary main circulation pump through the return pipe 8 is evenly distributed in the bucket 10 by the distribution pipe 12, and the bucket wall It flows out into the secondary cooling system tank from the outlet hole 11 provided in the lower part. Since the liquid level of the low temperature secondary coolant in the bucket 10 is determined by the balance between the inflow amount from the return pipe 8 and the outflow amount from the outlet hole 11, if the flow control valve 9 on the return pipe 8 is adjusted appropriately, The liquid level and flow rate in the bucket 10 can be set appropriately.

〔発明の効果〕〔The invention's effect〕

本発明によれば、原子炉容器外壁に設けたバケツト内の
低温2次冷却材が、蒸気発生器内の高温2次冷却材から
原子炉容器に流れる高熱流に対してしやへいの役目を果
すので、原子炉容器が高温になるのを緩和できる。
According to the present invention, the low temperature secondary coolant in the bucket provided on the outer wall of the reactor vessel serves as a shield against the high heat flow flowing from the high temperature secondary coolant in the steam generator to the reactor vessel. As a result, the temperature of the reactor vessel can be reduced.

さらに、このバケツトに貯留する低温の2次冷却材を、
2次主循環ポンプ出口配管から分岐し、途中に流量調節
弁を設置した戻り配管から供給するので、貯留冷却材の
液位および流量を調整でき、熱しやへい効果をコントロ
ール可能である。
In addition, the low temperature secondary coolant stored in this bucket
Since it branches from the outlet pipe of the secondary main circulation pump and is supplied from the return pipe with a flow rate control valve installed in the middle, the liquid level and flow rate of the stored coolant can be adjusted, and the heat and heat effect can be controlled.

【図面の簡単な説明】[Brief description of drawings]

第1図は本発明の一実施例を示す系統図、第2図は第1
図における原子炉容器外側面付近の構造図、第3図は一
般的なタンク型高速増殖炉の冷却系系統図、第4図は二
重タンク型高速増殖炉の縦断面図、第5図は第4図にお
ける冷却材の液面関係を示す図である。 1……原子炉容器、2……2次冷却系タンク、6……2
次主循環ポンプ、7……2次主循環ポンプ出口配管、8
……戻り配管、9……流量調節弁、10……バケツト、
11……出口孔、21……分配管。
FIG. 1 is a system diagram showing an embodiment of the present invention, and FIG.
Fig. 3 is a structural diagram of the vicinity of the outer surface of the reactor vessel in Fig. 3, Fig. 3 is a cooling system system diagram of a general tank type fast breeder reactor, Fig. 4 is a vertical sectional view of a double tank type fast breeder reactor, and Fig. 5 It is a figure which shows the liquid level relationship of the coolant in FIG. 1 ... Reactor vessel, 2 ... Secondary cooling system tank, 6 ... 2
Secondary main circulation pump, 7 ... Secondary main circulation pump outlet piping, 8
...... Return pipe, 9 ...... Flow control valve, 10 ...... Bucket,
11 ... Exit hole, 21 ... Distribution pipe.

───────────────────────────────────────────────────── フロントページの続き (72)発明者 柴田 洋二 茨城県日立市幸町3丁目1番1号 株式会 社日立製作所日立工場内 (72)発明者 中尾 昇 茨城県日立市幸町3丁目1番1号 株式会 社日立製作所日立工場内 ─────────────────────────────────────────────────── ─── Continuation of the front page (72) Inventor Yoji Shibata 3-1-1, Saiwaicho, Hitachi-shi, Ibaraki Hitachi Ltd. Hitachi factory (72) Inventor Noboru Nakao 3-chome, Saiwai-cho, Hitachi, Ibaraki No. 1 Hitachi Ltd. Hitachi factory

Claims (2)

【特許請求の範囲】[Claims] 【請求項1】炉心および1次冷却系設備を設けた原子炉
容器の外側に2次冷却系タンクを設け、2次冷却系タン
ク内で前記原子炉容器外側の環状部分に2次冷却系循環
ポンプと蒸気発生器を配設した二重タンク型高速増殖炉
において、前記2次冷却系循環ポンプの出口配管から2
次冷却系タンク内への戻り配管を設け、この戻り配管か
らの低温の2次冷却材を貯留し底部から2次冷却系タン
ク内に放出するバケツトを前記原子炉容器外側面に設け
たことを特徴とする二重タンク型高速増殖炉。
1. A secondary cooling system tank is provided outside a reactor vessel provided with a core and a primary cooling system facility, and a secondary cooling system is circulated in an annular portion outside the reactor vessel within the secondary cooling system tank. In a double-tank type fast breeder reactor in which a pump and a steam generator are installed, 2 from the outlet pipe of the secondary cooling system circulation pump
A bucket is provided on the outer surface of the reactor vessel to provide a return pipe to the secondary cooling system tank and to store the low temperature secondary coolant from the return pipe and discharge it from the bottom into the secondary cooling system tank. Double tank type fast breeder reactor featuring.
【請求項2】特許請求の範囲第1項に記載の二重タンク
型高速増殖炉において、前記戻り配管が、前記バケツト
内に貯留すべき2次冷却材の液面と流量とを調整する流
量調整弁を備えたことを特徴とする二重タンク型高速増
殖炉。
2. The double tank type fast breeder reactor according to claim 1, wherein the return pipe adjusts the liquid level and the flow rate of the secondary coolant to be stored in the bucket. A double-tank fast breeder reactor equipped with a regulating valve.
JP61060580A 1986-03-20 1986-03-20 Double tank type fast breeder reactor Expired - Lifetime JPH0656422B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP61060580A JPH0656422B2 (en) 1986-03-20 1986-03-20 Double tank type fast breeder reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP61060580A JPH0656422B2 (en) 1986-03-20 1986-03-20 Double tank type fast breeder reactor

Publications (2)

Publication Number Publication Date
JPS62218890A JPS62218890A (en) 1987-09-26
JPH0656422B2 true JPH0656422B2 (en) 1994-07-27

Family

ID=13146324

Family Applications (1)

Application Number Title Priority Date Filing Date
JP61060580A Expired - Lifetime JPH0656422B2 (en) 1986-03-20 1986-03-20 Double tank type fast breeder reactor

Country Status (1)

Country Link
JP (1) JPH0656422B2 (en)

Also Published As

Publication number Publication date
JPS62218890A (en) 1987-09-26

Similar Documents

Publication Publication Date Title
US4367194A (en) Emergency core cooling system
US4762667A (en) Passive reactor auxiliary cooling system
US3498880A (en) Liquid cooled nuclear reactor with means for isolating heat exchanger
US4608224A (en) Nuclear reactor cooled by a liquid metal
JP2002156485A (en) Reactor
US4362694A (en) Liquid metal-cooled nuclear reactor
JPS5916238B2 (en) Nuclear reactor emergency cooling system
US5295169A (en) Reactor containment facilities
EP0950248A1 (en) Nuclear reactor with improved natural coolant circulation
JPS58146891A (en) Reactor device
GB1484093A (en) Liquid cooled nuclear reactor
JP3040819B2 (en) Secondary side decay heat release device for pressurized water reactor
EP0141158B1 (en) Double tank type fast breeder reactor
US4302296A (en) Apparatus for insulating hot sodium in pool-type nuclear reactors
US4127444A (en) Device for thermal protection of a nuclear reactor vessel
JP2899979B2 (en) High temperature gas furnace
JPH0656422B2 (en) Double tank type fast breeder reactor
GB1491232A (en) Nuclear reactors
JPH0760193B2 (en) Sodium cooled reactor
CA1257715A (en) Reactor with natural convection backup cooling system
US3994777A (en) Nuclear reactor overflow line
JPS61791A (en) Fast neutron reactor
JPH0656423B2 (en) Double tank type fast breeder reactor
JPS5850497A (en) Fast breeder
CN116189933A (en) Submerged containment vessel with active water cooled heat sink