JPH0361155B2 - - Google Patents

Info

Publication number
JPH0361155B2
JPH0361155B2 JP57145639A JP14563982A JPH0361155B2 JP H0361155 B2 JPH0361155 B2 JP H0361155B2 JP 57145639 A JP57145639 A JP 57145639A JP 14563982 A JP14563982 A JP 14563982A JP H0361155 B2 JPH0361155 B2 JP H0361155B2
Authority
JP
Japan
Prior art keywords
liquid metal
plenum
core
tank
reactor
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
JP57145639A
Other languages
Japanese (ja)
Other versions
JPS5935182A (en
Inventor
Ryoichi Ootani
Iwao Ooshima
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 JP57145639A priority Critical patent/JPS5935182A/en
Publication of JPS5935182A publication Critical patent/JPS5935182A/en
Publication of JPH0361155B2 publication Critical patent/JPH0361155B2/ja
Granted legal-status Critical Current

Links

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)
  • Physical Or Chemical Processes And Apparatus (AREA)

Description

【発明の詳細な説明】 〔発明の技術分野〕 本発明は、液体金属冷却原子炉に係り、特に液
体金属の各プレナムの隔壁部に関する。
TECHNICAL FIELD OF THE INVENTION The present invention relates to liquid metal cooled nuclear reactors, and more particularly to partitions of each liquid metal plenum.

〔発明の技術的背景〕[Technical background of the invention]

第1図は従来の液体金属冷却原子炉の原子炉容
器内を概略的に示した構成図である。
FIG. 1 is a diagram schematically showing the inside of a reactor vessel of a conventional liquid metal cooled nuclear reactor.

液体金属冷却原子炉においてタンク型の原子炉
容器1内には下方中央に配置された炉心4の他に
ポンプ3と中間熱交換器2が配置されている。
In a liquid metal cooled nuclear reactor, a pump 3 and an intermediate heat exchanger 2 are arranged in a tank-shaped reactor vessel 1 in addition to a reactor core 4 disposed in the lower center.

これらの機器によつてこの原子炉容器1内は炉
心4の上部の液体金属領域である高温プレナム6
と、中間熱交換器2の出口14側の液体金属領域
である低温プレナム7と、前記高温プレナム6と
低温プレナム7の隔壁部となる液体金属領域であ
る中間プレナム5、ポンプ3の出口18側で炉心
4下部の液体金属領域である高圧プレナム9及び
この高圧プレナム9下部の液体金属領域である中
圧プレナム10との領域にそれぞれ区画される。
These devices create a high-temperature plenum 6, which is a liquid metal region above the reactor core 4, inside the reactor vessel 1.
, a low-temperature plenum 7 which is a liquid metal region on the outlet 14 side of the intermediate heat exchanger 2, an intermediate plenum 5 which is a liquid metal region forming a partition between the high-temperature plenum 6 and the low-temperature plenum 7, and an outlet 18 side of the pump 3. The high pressure plenum 9 is a liquid metal region below the core 4, and the intermediate pressure plenum 10 is a liquid metal region below the high pressure plenum 9.

液体金属はポンプ3からポンプ出口18および
ダクト19を通り、炉心下部の高圧プレナム9を
通つて炉心4へ送られる。
Liquid metal is sent from pump 3 through pump outlet 18 and duct 19 to core 4 through high pressure plenum 9 in the lower core.

液体金属は炉心4で熱せられて、高温プレナム
6へ達する。
The liquid metal is heated in the reactor core 4 and reaches the high temperature plenum 6.

高温となつた液体金属は中間熱交換器2に入
り、この中間熱交換器2で熱交換されて冷却され
る。
The high-temperature liquid metal enters the intermediate heat exchanger 2, where it exchanges heat and is cooled.

冷却された液体金属は中間熱交換器出口14か
ら低温プレナム7へ達しポンプ入口12に戻され
流入する。
The cooled liquid metal flows from the intermediate heat exchanger outlet 14 into the cold plenum 7 and back into the pump inlet 12.

このように炉容器内を液体金属が循環する。 In this way, liquid metal circulates within the furnace vessel.

なお、図中符号15はポンプ3および中間熱交
換器2を吊り下げているルーフスラブで原子炉容
器1の上蓋をなしており、また11はコンクリー
ト壁、16,17は各々中間熱交換器2の冷却材
の入口及び出口ダクトである。
In the figure, reference numeral 15 is a roof slab on which the pump 3 and the intermediate heat exchanger 2 are suspended, which forms the upper cover of the reactor vessel 1, 11 is a concrete wall, and 16 and 17 are the intermediate heat exchanger 2, respectively. coolant inlet and outlet ducts.

〔背景技術の問題点〕[Problems with background technology]

上記のように原子炉容器1内の液体金属が区画
されているために液体金属をチヤージする場合に
は、数ケ所よりチヤージしなければならない。
Since the liquid metal within the reactor vessel 1 is divided as described above, when charging the liquid metal, it must be charged from several locations.

また熱応力を少なくし、ガス溜りができないよ
うに、チヤージ位置、順番等を考慮しなければな
らない。
In addition, the charge position, order, etc. must be considered in order to reduce thermal stress and prevent gas accumulation.

さらに、事故時等にポンプが停止した際は、高
温プレナムと低温プレナムが独立してしまうので
自然循環による炉心冷却が行なわれないなどの問
題があつた。
Furthermore, when the pumps are stopped due to an accident, etc., the high-temperature plenum and the low-temperature plenum become independent, causing problems such as the core being unable to be cooled by natural circulation.

〔発明の目的〕[Purpose of the invention]

本発明は上記問題点を解決するためになされた
もので、第1の目的は、炉容器内への液体金属の
チヤージの際にガス溜りが出きず、どの部分から
でもチヤージ可能な液体金属冷却原子炉を提供す
ることにある。
The present invention has been made to solve the above problems, and the first object is to cool the liquid metal so that it can be charged from any part without causing gas accumulation when charging the liquid metal into the furnace vessel. The purpose is to provide nuclear reactors.

第2の目的はポンプが停止した場合に炉容器内
で液体金属の自然循環による炉心冷却可能な液体
金属冷却原子炉を提供することにある。
A second object is to provide a liquid metal cooled nuclear reactor in which the core can be cooled by natural circulation of liquid metal within the reactor vessel when the pumps are stopped.

〔発明の概要〕[Summary of the invention]

本発明はタンク型高速増殖炉において、原子炉
容器内に配置された中間熱交換器出口の低温プレ
ナムと、炉心下部の高圧プレナムと、隔壁となる
中間プレナムおよび炉心周囲の劃成区域との間に
それぞれ逆止弁(バルブ)を設けてなることを特
徴とする液体金属冷却原子炉であり、液体金属の
チヤージをスムーズに行なうことができ、しかも
冷却材流量喪失時には自然循環による炉心の冷却
を行うことができる。
The present invention provides a tank-type fast breeder reactor between a low-temperature plenum at the outlet of an intermediate heat exchanger disposed in a reactor vessel, a high-pressure plenum at the lower part of the core, and a partition between the intermediate plenum and a partition area around the core. It is a liquid metal cooled nuclear reactor characterized by having check valves installed at each side, which allows for smooth charging of liquid metal, and allows cooling of the reactor core through natural circulation when the coolant flow rate is lost. It can be carried out.

〔発明の実施例〕[Embodiments of the invention]

以下図面を参照して本発明を詳しく説明する。 The present invention will be described in detail below with reference to the drawings.

第2図は本発明に係る液体金属冷却原子炉の一
実施例における炉心周辺部を拡大して示す要部断
面図で、第1図と同一部分は同一符号で示し、重
複する部分の説明を省略する。
FIG. 2 is an enlarged sectional view of the main parts of the core periphery of an embodiment of the liquid metal cooled nuclear reactor according to the present invention. The same parts as in FIG. Omitted.

すなわち、炉心4の下部に位置しポンプ3の出
口18側と接続され高圧プレナム9と中間熱交換
器出口14側と接続される低温プレナム7との
間、炉心4の周囲の劃成区域8と低温プレナム7
との間、高温プレナム6と低温プレナム7との隔
壁となる中間プレナム5と低温プレナム7との
間、高圧プレナム9とその下部に位置する中圧プ
レナム10との間及び中圧プレナム10と低温プ
レナム7との間にはそれぞれバルブたとえば逆止
弁20,21,22,23,24が5個設けてあ
る。
That is, between the high-pressure plenum 9 located at the lower part of the core 4 and connected to the outlet 18 side of the pump 3 and the low-temperature plenum 7 connected to the intermediate heat exchanger outlet 14 side, and between the grown area 8 around the core 4 and Low temperature plenum 7
between the intermediate plenum 5 and the low temperature plenum 7, which are partition walls between the high temperature plenum 6 and the low temperature plenum 7, between the high pressure plenum 9 and the intermediate pressure plenum 10 located below it, and between the intermediate pressure plenum 10 and the low temperature plenum 9. Five valves, such as check valves 20, 21, 22, 23, and 24, are provided between the plenum 7 and the plenum 7, respectively.

これら5個の逆止弁20,21,22,23,
24は通常時バネにより開となつており、一方に
圧力が加わると閉となるものである。
These five check valves 20, 21, 22, 23,
24 is normally opened by a spring, and is closed when pressure is applied to one side.

次に作用について説明する。 Next, the effect will be explained.

原子炉が運転開始する前に炉容器1内へ液体金
属をチヤージする。
Before the reactor starts operating, liquid metal is charged into the reactor vessel 1.

この時は5個の逆止弁20,21,22,2
3,24なスプリングにより開の状態となつてい
るので高温プレナム6と低温プレナム7は逆止弁
21により、中間プレナム5と低温プレナム7
は、逆止弁22により、高圧プレナム9と中圧プ
レナム10は逆止弁23により、中圧プレナム1
0と低温プレナム7は逆止弁24により各々接続
されているため、どのプレナムより液体金属をチ
ヤージしても炉容器の下端より順次チヤージされ
るために、ガス溜りが発生せず、熱応力の偏りが
少なくなり、より正確かつ安全に液体金属のチヤ
ージができる。
At this time, five check valves 20, 21, 22, 2
Since the high temperature plenum 6 and the low temperature plenum 7 are kept open by the springs 3 and 24, the middle plenum 5 and the low temperature plenum 7 are closed by the check valve 21.
The high pressure plenum 9 and the medium pressure plenum 10 are connected to each other by the check valve 22, and the medium pressure plenum 1 is connected to the medium pressure plenum 1 by the check valve 23.
0 and the low-temperature plenum 7 are connected by check valves 24, so no matter which plenum the liquid metal is charged from, it is sequentially charged from the lower end of the furnace vessel, preventing gas accumulation and reducing thermal stress. With less bias, liquid metal can be charged more accurately and safely.

原子炉が運転を開始すると、ポンプ3の始動と
ともに各プレナムに圧力差が発生する。
When the nuclear reactor starts operating, the pump 3 starts and a pressure difference occurs in each plenum.

ポンプ3の出口18側である高圧プレナム9が
最も高圧となり、液体金属は炉心4へ送られる。
The high pressure plenum 9 on the outlet 18 side of the pump 3 has the highest pressure, and the liquid metal is sent to the reactor core 4.

炉心4の出力損失によつて圧力は若干低くな
り、高温プレナム6へ流入する。
Due to the power loss in the core 4, the pressure becomes slightly lower and flows into the hot plenum 6.

高温プレナム6から中間熱交換器2に流入し、
この中間熱交換器2の圧力損失によつてさらに低
圧になり、低温プレナム7へ流入する。
from the high temperature plenum 6 into the intermediate heat exchanger 2;
This pressure loss in the intermediate heat exchanger 2 further lowers the pressure, which flows into the low-temperature plenum 7.

この低温プレナム7はポンプ入口側につながつ
ているので最も圧力が低いプレナムとなる。
Since this low-temperature plenum 7 is connected to the pump inlet side, it becomes the plenum with the lowest pressure.

又、中間プレナム5は液体金属が流動しないの
で、ポンプによる圧力は受けない。
Further, since liquid metal does not flow through the intermediate plenum 5, it is not subjected to pressure from the pump.

又、高圧プレナム9部には図示のように燃料集
合体26のエントランスノズル27が位置してお
り、ポンプ3の圧力により、燃料集合体26が浮
き上がらないようにするためその下端は中圧プレ
ナム10に差し込まれており、高圧プレナム9と
中圧プレナム10の圧力差により、燃料集合体2
6下端を隔壁25に押しつけている。
Further, as shown in the figure, the entrance nozzle 27 of the fuel assembly 26 is located in the high-pressure plenum 9, and in order to prevent the fuel assembly 26 from floating due to the pressure of the pump 3, its lower end is connected to the intermediate-pressure plenum 10. The fuel assembly 2 is inserted into the fuel assembly 2 due to the pressure difference between the high pressure plenum 9 and the intermediate pressure plenum 10.
The lower end of 6 is pressed against the partition wall 25.

よつて、高圧プレナム9が最も圧力が高く、次
に中圧プレナム10、高温プレナム6、中間プレ
ナム5、低温プレナム7の順に圧力が低くなる。
Therefore, the high pressure plenum 9 has the highest pressure, followed by the intermediate pressure plenum 10, the high temperature plenum 6, the intermediate plenum 5, and the low temperature plenum 7, which have lower pressures in this order.

運転中は上記各プレナムの圧力差により、高圧
プレナム9と低温プレナム7間の逆止弁20、炉
心4周囲の劃成区域8と低温プレナム7との間の
逆止弁21、中間プレナム5と低温プレナム7の
間の逆止弁22、高圧プレナム9と中圧プレナム
10の間の逆止弁23、及び中圧プレナム10と
低温プレナム7との間の逆止弁24は閉の状態と
なつている。
During operation, due to the pressure difference between the above plenums, the check valve 20 between the high pressure plenum 9 and the low temperature plenum 7, the check valve 21 between the recessed area 8 around the core 4 and the low temperature plenum 7, the intermediate plenum 5 and The check valve 22 between the low-temperature plenum 7, the check valve 23 between the high-pressure plenum 9 and the medium-pressure plenum 10, and the check valve 24 between the medium-pressure plenum 10 and the low-temperature plenum 7 are in a closed state. ing.

また、燃料交換時あるいは主冷却系事故、電源
喪失事故等によりポンプ3が停止した場合には各
プレナム間の圧力差がほとんどなくなるので、逆
止弁20,21,22,23,24はバネによ
り、開の状態となる。
In addition, if the pump 3 is stopped during fuel exchange, main cooling system accident, power loss accident, etc., the pressure difference between each plenum will be almost eliminated, so the check valves 20, 21, 22, 23, and 24 are operated by springs. , it becomes open.

よつて高圧プレナム9、中圧プレナム10及び
低温プレナム7が連通するので液体金属は炉心部
4で熱せられて高温プレナム6へ上昇し、中間熱
交換器2で冷却されて、低温プレナム7に下降す
る。
Therefore, the high pressure plenum 9, the intermediate pressure plenum 10, and the low temperature plenum 7 are in communication, so that the liquid metal is heated in the core 4 and rises to the high temperature plenum 6, is cooled by the intermediate heat exchanger 2, and descends to the low temperature plenum 7. do.

すなわち低温プレナム7の冷却された液体金属
は逆止弁23,24あるいは20を通つて炉心を
冷却するというように自然循環による炉心冷却が
行なわれる。
That is, the cooled liquid metal in the low-temperature plenum 7 passes through the check valves 23, 24, or 20 to cool the core, thereby performing core cooling by natural circulation.

逆止弁21,22も開となるが、炉心4を通ら
ないので上昇流は起こらず、自然循環は起こらな
い。
The check valves 21 and 22 are also opened, but since the air does not pass through the core 4, no upward flow occurs and no natural circulation occurs.

又、ガス作動弁、電動弁、電磁弁等を用いて、
ポンプ3や流量計と連動するようにすることも可
能である。
Also, using gas-operated valves, electric valves, solenoid valves, etc.
It is also possible to make it work in conjunction with the pump 3 or a flow meter.

第3図は、本発明の他の実施例で、高圧プレナ
ム9、劃成区域8、中間プレナム5、低圧プレナ
ム7の間に一個の逆止弁を取り付けた状態を部分
的に示すものであつて、原子炉の運転時の逆止弁
の状態を示している。
FIG. 3 partially shows another embodiment of the present invention in which a check valve is installed between the high pressure plenum 9, the cultivation area 8, the intermediate plenum 5, and the low pressure plenum 7. This shows the check valve status during reactor operation.

すなわち、高圧プレナム9と低圧プレナム7の
間に圧力差があるため逆止弁29のスプリング3
0は圧力差によつて押され逆止弁29は閉の状態
となつている。
That is, since there is a pressure difference between the high pressure plenum 9 and the low pressure plenum 7, the spring 3 of the check valve 29
0 is pushed by the pressure difference, and the check valve 29 is in a closed state.

このため、高圧プレナム9、劃成区域8、中間
プレナム5及び低温プレナム7の各々のプレナム
間の液体金属の流動はなく、高圧プレナム9よ
り、エントランスノズル27より燃料集合体26
内を通つて高温プレナムへ流動する流路のみ連通
している。
Therefore, there is no flow of liquid metal between the high pressure plenum 9, the cultivation area 8, the intermediate plenum 5, and the low temperature plenum 7, and the liquid metal flows from the high pressure plenum 9 to the entrance nozzle 27 to the fuel assembly 26.
Only the flow path through which flow flows to the hot plenum is in communication.

燃料交換時あるいは、主冷却系事故、電源喪失
事故等によるポンプの停止時においては、各プレ
ナム間の圧力差はほとんどなくなるのでスプリン
グ30により逆止弁29が開き、高圧プレナム
9、劃成区域8、中間プレナム5及び低温プレナ
ム7の各プレナム間が連通する。
When replacing fuel or when the pump is stopped due to an accident in the main cooling system, power loss, etc., the pressure difference between each plenum is almost eliminated, so the check valve 29 is opened by the spring 30, and the high-pressure plenum 9 and the cultivation area 8 are opened. , the intermediate plenum 5 and the low temperature plenum 7 communicate with each other.

すなわち逆止弁29がスプリング30により押
され、図中右側に移動するため中間プレナム5
と、逆止弁中空部32および逆止弁孔34を介し
て導通しているスライド区域38と、高圧プレナ
ム9が連通し、また導通孔33が開通することに
より、劃成区域8と隔壁孔35を介して導通して
いる導通区域37と、中間プレナム5と導通して
いる逆止弁中空部32と、低温プレナム7の流入
部39とが各々連通する。
That is, the check valve 29 is pushed by the spring 30 and moves to the right in the figure, so that the intermediate plenum 5
The high-pressure plenum 9 communicates with the slide section 38 which is in communication via the check valve hollow part 32 and the check valve hole 34, and the communication hole 33 is opened, so that the formation section 8 and the partition wall hole are in communication with each other. 35, the check valve hollow 32, which communicates with the intermediate plenum 5, and the inlet 39 of the cold plenum 7 each communicate with each other.

よつて各プレナムへのチヤージがスムーズに行
なわれる。
Therefore, charging to each plenum is performed smoothly.

各プレナムの連通により、自然循環が起こり、
炉心冷却がなされる。
Natural circulation occurs due to communication between each plenum,
Core cooling is performed.

低温プレナム7より炉心部への液体金属の流路
は下記のようになる。
The flow path of liquid metal from the low-temperature plenum 7 to the core is as follows.

低温プレナム7の液体金属は流入部39より導
通孔33を通つて逆止弁中空部32へ流れ、さら
に逆止弁孔34を通つてスライド区域38へ流
れ、逆止弁29と弁座36のすき間を通つて高圧
プレナム9へと導れる。
The liquid metal in the cold plenum 7 flows from the inlet 39 through the through hole 33 into the check valve hollow 32 and further through the check valve hole 34 into the sliding area 38, where it flows between the check valve 29 and the valve seat 36. It is led to the high pressure plenum 9 through the gap.

高圧プレナム9から、エントランスノズルオリ
フイス28を通つて燃料集合体26内に入り、炉
心4へ達する。
From the high pressure plenum 9, it enters the fuel assembly 26 through the entrance nozzle orifice 28 and reaches the core 4.

また前記ポンプが作動し低圧プレナムと高圧プ
レナムの間に圧力差が発生すると、逆止弁29の
逆止弁オリフイスを液体金属が高流速で流れるた
め、逆止弁29はスプリング30の開方向への力
よりも大きな閉の力を受け閉じる。
Further, when the pump is activated and a pressure difference is generated between the low pressure plenum and the high pressure plenum, liquid metal flows at a high flow rate through the check valve orifice of the check valve 29, so that the check valve 29 moves in the opening direction of the spring 30. It closes when it receives a closing force that is greater than the closing force.

このことにより、通常の原子炉運転に支障を来
たすことなく前記の利点をだけが得られる。
This provides only the above-mentioned advantages without interfering with normal reactor operation.

〔発明の効果〕〔Effect of the invention〕

以上詳述したように本発明によれば、原子炉容
器への液体金属をチヤージするに際してのガス溜
り防止及び熱応力の抑制ができ、より確実かつ安
全な液体金属のチヤージが行なえ、しかも非常時
の自然循環による炉心冷却ができるとともに中間
プレナムなどの特定部分へのチヤージの必要がな
い信頼性の高い液体金属冷却原子炉を提供でき
る。
As detailed above, according to the present invention, gas accumulation can be prevented and thermal stress can be suppressed when charging liquid metal to a reactor vessel, and liquid metal can be charged more reliably and safely. It is possible to provide a highly reliable liquid metal cooled nuclear reactor that can cool the reactor core by natural circulation and does not require charging specific parts such as the intermediate plenum.

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

第1図は従来の液体金属冷却原子炉の概略を示
す縦断面図、第2図は本発明に係る液体金属冷却
原子炉の一実施例における炉心周辺部を拡大して
示す縦断面図、第3図は本発明に係る液体金属冷
却原子炉に使用される逆止弁を示す縦断面図であ
る。 1……原子炉容器、2……中間熱交換器、3…
…ポンプ、4……炉心、5……中間プレナム、6
……高温プレナム、7……低温プレナム、8……
劃成区域、9……高圧プレナム、10……中圧プ
レナム、11……コンクリート壁、12……ポン
プ入口、13……中間熱交換器入口、14……中
間熱交換器出口、15……ルーフスラブ、16…
…中間熱交換器冷却ナトリウム出口ダクト、17
……中間熱交換器冷却ナトリウム入口ダクト、1
8……ポンプ出口、19……ダクト、20,2
1,22,23,24……逆止弁、25……隔
壁、26……燃料集合体、27……エントランス
ノズル、28……エントランスノズルオリフイ
ス、29……逆止弁、30……スプリング、31
……スライドリング、32……逆止弁中空部、3
3……導通孔、34……逆止弁孔、35……隔壁
孔、36……弁座、37……導通区域、38……
スライド区域、39……流入部。
FIG. 1 is a vertical cross-sectional view schematically showing a conventional liquid metal cooled nuclear reactor, and FIG. FIG. 3 is a longitudinal sectional view showing a check valve used in a liquid metal cooled nuclear reactor according to the present invention. 1...Reactor vessel, 2...Intermediate heat exchanger, 3...
...Pump, 4...Core, 5...Intermediate plenum, 6
...High temperature plenum, 7...Low temperature plenum, 8...
Cultivation area, 9... High pressure plenum, 10... Medium pressure plenum, 11... Concrete wall, 12... Pump inlet, 13... Intermediate heat exchanger inlet, 14... Intermediate heat exchanger outlet, 15... Roof slab, 16...
...Intermediate heat exchanger cooling sodium outlet duct, 17
...Intermediate heat exchanger cooling sodium inlet duct, 1
8...Pump outlet, 19...Duct, 20,2
1, 22, 23, 24... Check valve, 25... Partition wall, 26... Fuel assembly, 27... Entrance nozzle, 28... Entrance nozzle orifice, 29... Check valve, 30... Spring, 31
...Slide ring, 32...Check valve hollow part, 3
3... Conduction hole, 34... Check valve hole, 35... Bulkhead hole, 36... Valve seat, 37... Conduction area, 38...
Slide area, 39...inflow section.

Claims (1)

【特許請求の範囲】 1 液体金属を収容する頂部の開いた主容器と、
この主容器内に配置された炉心と、前記主容器内
で前記炉心の周囲に劃成区域を形成して該炉心を
収容する内部槽と、この内部槽との間に液体金属
層を形成して、該内部槽を収容する中間槽と、前
記内部槽及び中間槽を貫通し炉心周囲に間隔をも
つて設置される中間熱交換器と、この中間熱交換
器と間隔をもつて、かつ同軸円上に設置される1
次系ポンプと、この1次系ポンプの出口の配管
と、連結され、該炉心部液体金属の入口となる炉
心下部に設置される第1の下部槽とこの第1の下
部槽の下部に設置され、固定孔を介して連通して
いる第2の下部槽とを備えた液体金属冷却原子炉
において、前記第1の下部槽の液体金属がポンプ
により押し出され高圧となつている部分(高圧プ
レナム)と、前記第1の下部槽の外側で、かつ前
記主容器下部で、しかも前記中間熱交換器または
炉心冷却系の出口側の冷された液体金属の部分
(低温プレナム)との間にバルブを設けたことを
特徴とする液体金属冷却原子炉。 2 炉心周囲の液体金属が停滞している劃成区域
と、前記低温プレナムとの間にバルブを設けた事
を特徴とする特許請求の範囲第1項記載の液体金
属冷却原子炉。 3 内部槽と中間槽の間の液体金属の停滞してい
る領域(中間プレナム)と低温プレナムとの間に
バルブを設けた事を特徴とする特許請求の範囲第
1項記載の液体金属冷却原子炉。 4 第2の下部槽内の圧力が下げられている液体
金属領域(中圧プレナム)と低温プレナムとの間
にバルブを設けたことを特徴とする特許請求の範
囲第1項記載の液体金属冷却原子炉。 5 高圧プレナムと、中圧プレナムとの間にバル
ブを設けたことを特徴とする特許請求の範囲第1
項記載の液体金属冷却原子炉。 6 バルブは5個設けられ、そのうち複数個のバ
ルブが連動して開閉することを特徴とする特許請
求の範囲第1項記載の液体金属冷却原子炉。 7 5個設けられたバルブがポンプあるいは流量
計と連動して開閉することを特徴とする特許請求
の範囲第1項記載の液体金属冷却原子炉。
[Claims] 1. A main container with an open top containing liquid metal;
A liquid metal layer is formed between a reactor core disposed within the main vessel, an internal tank for accommodating the reactor core by forming a cultivation area around the core within the main vessel, and the internal tank. an intermediate tank that accommodates the internal tank; an intermediate heat exchanger that penetrates the internal tank and the intermediate tank and is installed at a distance around the core; 1 placed on a circle
A secondary system pump, a first lower tank installed at the bottom of the core that is connected to the outlet piping of this primary system pump and serves as an inlet for the liquid metal in the reactor core, and a first lower tank installed at the bottom of this first lower tank. In a liquid metal cooled nuclear reactor, the liquid metal in the first lower tank is pushed out by a pump and is under high pressure (high pressure plenum). ) and a portion of the cooled liquid metal (cold plenum) outside the first lower tank and at the bottom of the main vessel and on the exit side of the intermediate heat exchanger or core cooling system. A liquid metal cooled nuclear reactor characterized by being provided with. 2. The liquid metal cooled nuclear reactor according to claim 1, characterized in that a valve is provided between the low-temperature plenum and a cultivation area in which liquid metal around the core is stagnant. 3. The liquid metal cooled atom according to claim 1, characterized in that a valve is provided between the region where the liquid metal is stagnant (intermediate plenum) between the inner tank and the intermediate tank and the low-temperature plenum. Furnace. 4. Liquid metal cooling according to claim 1, characterized in that a valve is provided between the liquid metal region (intermediate pressure plenum) in which the pressure in the second lower tank is lowered and the low temperature plenum. Reactor. 5 Claim 1 characterized in that a valve is provided between the high pressure plenum and the intermediate pressure plenum.
Liquid metal cooled nuclear reactor as described in Section. 6. The liquid metal cooled nuclear reactor according to claim 1, wherein five valves are provided, and a plurality of the valves are opened and closed in conjunction with each other. 7. The liquid metal cooled nuclear reactor according to claim 1, wherein the five valves are opened and closed in conjunction with a pump or a flow meter.
JP57145639A 1982-08-23 1982-08-23 Liquid metal cooled reactor Granted JPS5935182A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57145639A JPS5935182A (en) 1982-08-23 1982-08-23 Liquid metal cooled reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57145639A JPS5935182A (en) 1982-08-23 1982-08-23 Liquid metal cooled reactor

Publications (2)

Publication Number Publication Date
JPS5935182A JPS5935182A (en) 1984-02-25
JPH0361155B2 true JPH0361155B2 (en) 1991-09-18

Family

ID=15389659

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57145639A Granted JPS5935182A (en) 1982-08-23 1982-08-23 Liquid metal cooled reactor

Country Status (1)

Country Link
JP (1) JPS5935182A (en)

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* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US11881320B2 (en) * 2019-12-23 2024-01-23 Terrapower, Llc Molten fuel reactors and orifice ring plates for molten fuel reactors

Also Published As

Publication number Publication date
JPS5935182A (en) 1984-02-25

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