JPH0249593Y2 - - Google Patents

Info

Publication number
JPH0249593Y2
JPH0249593Y2 JP1982044622U JP4462282U JPH0249593Y2 JP H0249593 Y2 JPH0249593 Y2 JP H0249593Y2 JP 1982044622 U JP1982044622 U JP 1982044622U JP 4462282 U JP4462282 U JP 4462282U JP H0249593 Y2 JPH0249593 Y2 JP H0249593Y2
Authority
JP
Japan
Prior art keywords
reactor
low
inner cylinder
temperature sodium
outlet nozzle
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
JP1982044622U
Other languages
Japanese (ja)
Other versions
JPS58148696U (en
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 filed Critical
Priority to JP1982044622U priority Critical patent/JPS58148696U/en
Publication of JPS58148696U publication Critical patent/JPS58148696U/en
Application granted granted Critical
Publication of JPH0249593Y2 publication Critical patent/JPH0249593Y2/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

  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Description

【考案の詳細な説明】 本案は高速増殖炉の改良に関するものである。[Detailed explanation of the idea] This project concerns the improvement of fast breeder reactors.

従来の高速増殖炉を第1図により説明すると、
aが内部に炉心bを形成するとともに同炉心bよ
りも上方の胴部に冷却材出口ノズルcを形成した
原子炉容器、dが同原子炉容器aの中に同炉心b
よりも上方に位置して設けられるとともに同容器
aの内面との間に環状空間eを画成する内筒、f
が同内筒dに穿設された複数のフローホール、g
が炉心上部機構、hが遮蔽プラグ、iがペデスタ
ル、jがシールガスで、原子炉が何らかの信号に
よりトリツプされると、低流量運転に移り、炉心
bから上部プレナムk内へ低温の液体金属ナトリ
ウム(以下ナトリウムと称する)lが流出する。
このときの低温ナトリウムは低流量のため、上部
プレナムk内に残留する高温ナトリウムmと混合
せず、上部プレナムk内では上方の高温ナトリウ
ム領域と下方の低温ナトリウム領域とに分離、画
成されて(成層化現象が起つて)、大きな温度差
が生じる。上記高温ナトリウム領域と上記低温ナ
トリウム領域との境界面は低温ナトリウムlの流
出とともに徐々に上昇し、内筒dに設けた複数の
フローホールfの最下縁以上になると、低温ナト
リウムlの一部が各フローホールfから環状空間
eへ流出して、冷却材出口ノズルoへ向う。しか
しフローホールfから出口ノズルo向う低温ナト
リウムlは一部なので、上記境界面はその後も上
昇を続け、遂には内筒dの上縁を越えるようにな
り、そこから溢流して、出口ノズルcへ向うよう
になつている。
A conventional fast breeder reactor is explained using Figure 1.
a is a reactor vessel in which a core b is formed and a coolant outlet nozzle c is formed in the body above the core b; d is a reactor vessel in which a reactor core B is formed inside the reactor vessel a;
an inner cylinder f that is located above the container a and defines an annular space e between it and the inner surface of the container a;
is a plurality of flow holes drilled in the same inner cylinder d, g
is the upper core mechanism, h is the shielding plug, i is the pedestal, and j is the seal gas. When the reactor is tripped by some signal, it goes into low flow operation and low-temperature liquid metal sodium flows from the core b into the upper plenum k. (hereinafter referred to as sodium) flows out.
Because the flow rate of the low-temperature sodium at this time is low, it does not mix with the high-temperature sodium m remaining in the upper plenum k, and the upper plenum k is separated and defined into an upper high-temperature sodium region and a lower low-temperature sodium region. (A stratification phenomenon occurs), resulting in a large temperature difference. The interface between the high-temperature sodium region and the low-temperature sodium region gradually rises as the low-temperature sodium 1 flows out, and when it reaches the lowest edge of the plurality of flow holes f provided in the inner cylinder d, a portion of the low-temperature sodium 1 flows out from each flow hole f into the annular space e and toward the coolant outlet nozzle o. However, since only a portion of the low-temperature sodium l flows from the flow hole f to the outlet nozzle o, the boundary surface continues to rise and finally exceeds the upper edge of the inner cylinder d, overflowing from there to the outlet nozzle c. It's starting to move towards.

前記高速増殖炉では、上記各フローホールfが
内筒dのほぼ同じ高さ位置に設けられていて、フ
ローホールfの出口ノズルcに対する距離がフロ
ーホールfごとに異るので、前記境界面が各フロ
ーホールfの最下縁以上になつてから内筒dの上
縁を越えるまでの間、低温ナトリウムが出口ノズ
ルcへ異る時間に到達して、出口ノズルcは軸非
対称的に熱衝撃を受けるという問題があつた。
In the fast breeder reactor, each of the flow holes f is provided at approximately the same height position in the inner cylinder d, and the distance of the flow hole f to the outlet nozzle c differs for each flow hole f, so that the boundary surface From reaching the lowest edge of each flow hole f to passing the upper edge of the inner cylinder d, the low temperature sodium reaches the outlet nozzle c at different times, and the outlet nozzle c undergoes thermal shock in an axially asymmetric manner. There was a problem with receiving it.

本案は前記の問題点に対処するもので、内部に
炉心を形成した原子炉容器と、上記炉心よりも上
方の上記原子炉容器の胴部に水平方向に間隔をお
いて設けた複数個の冷却材出口ノズルと、上記炉
心よりも上方の上記原子炉容器内に設置して同原
子炉容器の内面との間に環状空間を形成した内筒
とを有し、同内筒のうち、上記各冷却材出口ノズ
ルの円筒上半部に沿つた略波形の仮想線上に複数
のフローフオールを間隔をおいて穿設したことを
特徴とする高速増殖炉に係り、その目的とする処
は、冷却材出口ノズルが軸対称的に熱衝撃を受け
るだけで、同出口ノズルの構造健全性を高めるこ
とができる改良された高速増殖炉を供する点にあ
る。
This proposal addresses the above-mentioned problems, and consists of a reactor vessel with a reactor core formed inside, and a plurality of cooling units installed horizontally at intervals in the body of the reactor vessel above the reactor core. It has a material outlet nozzle, and an inner cylinder installed in the reactor vessel above the reactor core to form an annular space between it and the inner surface of the reactor vessel. A fast breeder reactor is characterized in that a plurality of flow falls are bored at intervals on a substantially wave-shaped virtual line along the cylindrical upper half of a coolant outlet nozzle, the purpose of which is to provide cooling. The object of the present invention is to provide an improved fast breeder reactor in which the structural integrity of the outlet nozzle can be improved simply by subjecting the outlet nozzle to thermal shock in an axially symmetrical manner.

次に本案の高速増殖炉を第2,3,4図に示す
一実施例により説明すると、1が内部に炉心2を
形成するとともに同炉心2よりも上方の胴部に冷
却材出口ノズル3を形成した原子炉容器、4が同
原子炉容器1の中に同炉心2よりも上方に位置し
て設けられるとともに同容器1の内面との間に環
状空間5を画成する内筒、6a〜6eが同内筒4
に穿設された複数のフローホールで、同各フロー
ホール6a〜6eは、上記内筒4のうち、上記各
冷却材出口ノズル3の円筒上半部に沿つた略波形
の仮想線上に間隔をおいて穿設されている。また
7は炉心上部機構、8は遮蔽プラグ、9はペデス
タル、10はカバーガスである。
Next, the fast breeder reactor of the present invention will be explained with reference to an embodiment shown in Figs. The formed reactor vessel 4 is provided in the reactor vessel 1 above the reactor core 2, and an inner cylinder 6a to 6a defines an annular space 5 between it and the inner surface of the vessel 1. 6e is the same inner cylinder 4
A plurality of flow holes are formed in the inner cylinder 4, and each of the flow holes 6a to 6e is spaced apart from each other on a substantially wave-shaped imaginary line along the upper half of the cylinder of each of the coolant outlet nozzles 3 in the inner cylinder 4. It is drilled at Further, 7 is a core upper mechanism, 8 is a shielding plug, 9 is a pedestal, and 10 is a cover gas.

次に前記高速増殖炉の作用を説明する。原子炉
が何らかの信号によりトリツプされると、低流量
運転に移り、炉心2から上部プレナム11内へ低
温ナトリウムが流出する。このときの低温ナトリ
ウムは低流量のため、上部プレナム11内に残留
する高温ナトリウムと混合せず、上部プレナム1
1内では上方の高温ナトリウム領域と下方の低温
ナトリウム領域とに分離、画成されて(成層化現
象が起つて)、大きな温度差が生じる。上記高温
ナトリウム領域と上記低温ナトリウム領域との境
界面は低温ナトリウムの流出とともに徐々に上昇
し、最下位のフローホール6e以上になると、低
温ナトリウムが上部プレナム11内から同フロー
ホール6eを経て環状空間5へ流出し始める。ま
た上記境界面が下から二番目のフローホール6d
以上になると、低温ナトリウムが上部プレナム1
1内から同フローホール6dを経て環状空間5へ
流出し始める。以下同様に上記境界面が6c,6
b,6a以上になると、低温ナトリウムが上部プ
レナム11内から同各フローホール6c,6b,
6aを経て環状空間5へ流出し始めるが、各フロ
ーホール6e〜6aと出口ノズル3の内筒側開口
部との間の距離は、同各フローホール6e〜6a
からの低温ナトリウムが出口ノズル3へ同じ時期
に到達するように設定されているので、低温ナト
リウムが出口ノズル3へ同じ時期に到達し、出口
ノズル3はほぼ軸対称的に熱衝撃を受けて、出口
ノズル3の構造健全性が高められる。
Next, the operation of the fast breeder reactor will be explained. When the reactor is tripped by some signal, it goes into low flow operation and low temperature sodium flows out from the core 2 into the upper plenum 11. At this time, the low-temperature sodium does not mix with the high-temperature sodium remaining in the upper plenum 11 due to its low flow rate, and
1 is separated and defined into an upper high-temperature sodium region and a lower low-temperature sodium region (a stratification phenomenon occurs), resulting in a large temperature difference. The interface between the high-temperature sodium region and the low-temperature sodium region gradually rises as the low-temperature sodium flows out, and when it reaches the lowest flow hole 6e or higher, the low-temperature sodium flows from the upper plenum 11 through the flow hole 6e into the annular space. It begins to flow to 5. Also, the above boundary surface is the second flow hole 6d from the bottom.
If the temperature rises above, the low-temperature sodium will reach upper plenum 1
1 begins to flow out into the annular space 5 through the flow hole 6d. Similarly, the above boundary surfaces are 6c, 6
When the temperature rises above b, 6a, low-temperature sodium flows from inside the upper plenum 11 to the same flow holes 6c, 6b,
The distance between each flow hole 6e to 6a and the inner cylinder side opening of the outlet nozzle 3 is the same as that of each flow hole 6e to 6a.
Since the setting is such that the low-temperature sodium reaches the outlet nozzle 3 at the same time, the low-temperature sodium reaches the outlet nozzle 3 at the same time, and the outlet nozzle 3 receives a thermal shock almost axially symmetrically. The structural integrity of the outlet nozzle 3 is enhanced.

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

第1図は従来の高速増殖炉を示す縦断側面図、
第2図は本案に係る高速増殖炉の一実施例を示す
縦断側面図、第3図は内筒部分の横断平面図、第
4図は第3図の矢印方向からみた内筒の展開図
である。 1……原子炉容器、2……炉心、3……冷却材
出口ノズル、4……内筒、5……環状空間、6a
〜6e……フローホール。
Figure 1 is a vertical side view showing a conventional fast breeder reactor.
Figure 2 is a longitudinal cross-sectional side view showing an embodiment of the fast breeder reactor according to the present invention, Figure 3 is a cross-sectional plan view of the inner cylinder portion, and Figure 4 is a developed view of the inner cylinder seen from the direction of the arrow in Figure 3. be. DESCRIPTION OF SYMBOLS 1... Reactor vessel, 2... Core, 3... Coolant outlet nozzle, 4... Inner cylinder, 5... Annular space, 6a
~6e...Flow hole.

Claims (1)

【実用新案登録請求の範囲】[Scope of utility model registration request] 内部に炉心を形成した原子炉容器と、上記炉心
よりも上方の上記原子炉容器の胴部に水平方向に
間隔をおいて設けた複数個の冷却材出口ノズル
と、上記炉心よりも上方の上記原子炉容器内に設
置して同原子炉容器の内面との間に環状空間を形
成した内筒とを有し、同内筒のうち、上記各冷却
材出口ノズルの円筒上半部に沿つた略波形の仮想
線上に複数のフローフオールを間隔をおいて穿設
したことを特徴とする高速増殖炉。
a reactor vessel having a reactor core formed therein; a plurality of coolant outlet nozzles provided at intervals in the horizontal direction in the body of the reactor vessel above the reactor core; an inner cylinder installed in the reactor vessel to form an annular space between it and the inner surface of the reactor vessel; A fast breeder reactor characterized in that a plurality of flow holes are bored at intervals on an imaginary line of a substantially waveform.
JP1982044622U 1982-03-31 1982-03-31 fast breeder reactor Granted JPS58148696U (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1982044622U JPS58148696U (en) 1982-03-31 1982-03-31 fast breeder reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP1982044622U JPS58148696U (en) 1982-03-31 1982-03-31 fast breeder reactor

Publications (2)

Publication Number Publication Date
JPS58148696U JPS58148696U (en) 1983-10-05
JPH0249593Y2 true JPH0249593Y2 (en) 1990-12-27

Family

ID=30055673

Family Applications (1)

Application Number Title Priority Date Filing Date
JP1982044622U Granted JPS58148696U (en) 1982-03-31 1982-03-31 fast breeder reactor

Country Status (1)

Country Link
JP (1) JPS58148696U (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
USRE43135E1 (en) 2001-05-18 2012-01-24 Danisco A/S Method of improving dough and bread quality
USRE43341E1 (en) 1995-06-07 2012-05-01 Danisco A/S Method of improving the properties of a flour dough, a flour dough improving composition and improved food products
US8889371B2 (en) 2004-07-16 2014-11-18 Dupont Nutrition Biosciences Aps Lipolytic enzyme: uses thereof in the food industry

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS55166097A (en) * 1979-06-12 1980-12-24 Tokyo Shibaura Electric Co Nuclear reactor cooling device

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS55166097A (en) * 1979-06-12 1980-12-24 Tokyo Shibaura Electric Co Nuclear reactor cooling device

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
USRE43341E1 (en) 1995-06-07 2012-05-01 Danisco A/S Method of improving the properties of a flour dough, a flour dough improving composition and improved food products
USRE43135E1 (en) 2001-05-18 2012-01-24 Danisco A/S Method of improving dough and bread quality
US8889371B2 (en) 2004-07-16 2014-11-18 Dupont Nutrition Biosciences Aps Lipolytic enzyme: uses thereof in the food industry

Also Published As

Publication number Publication date
JPS58148696U (en) 1983-10-05

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