JPS58201089A - Fast breeder - Google Patents

Fast breeder

Info

Publication number
JPS58201089A
JPS58201089A JP57084319A JP8431982A JPS58201089A JP S58201089 A JPS58201089 A JP S58201089A JP 57084319 A JP57084319 A JP 57084319A JP 8431982 A JP8431982 A JP 8431982A JP S58201089 A JPS58201089 A JP S58201089A
Authority
JP
Japan
Prior art keywords
heat exchanger
intermediate heat
shell
reactor vessel
core
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.)
Pending
Application number
JP57084319A
Other languages
Japanese (ja)
Inventor
馬渡 勝彦
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 JP57084319A priority Critical patent/JPS58201089A/en
Publication of JPS58201089A publication Critical patent/JPS58201089A/en
Pending 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

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  • Crystals, And After-Treatments Of Crystals (AREA)
  • Semiconductor Lasers (AREA)

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。
(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

【発明の詳細な説明】 本発明はタンク形高速増殖炉に関する。[Detailed description of the invention] The present invention relates to a tank-type fast breeder reactor.

明する。図中1は原子炉容器を示す。この原子炉容器1
の上部開口1人はルーフスラブ2によって閉塞されてい
る。上記原子炉容器1内には、複数の燃料集合体3A、
制御棒3B等より構成されている炉心3が所定位置に収
容されている。
I will clarify. In the figure, 1 indicates the reactor vessel. This reactor vessel 1
The upper opening 1 of the roof slab 2 is closed off by the roof slab 2. Inside the reactor vessel 1, a plurality of fuel assemblies 3A,
A reactor core 3 composed of control rods 3B and the like is housed in a predetermined position.

この炉心3は炉心支持構造物4により支持されている。This core 3 is supported by a core support structure 4.

この炉心支持構造物4外周の上記原子炉容器1内には中
間熱交換器5および循環ポンプ6が前記ルーフスラブ2
を貫通して設置されている。同じくルーフスラブ2を貫
通しかつルーフスラブ2に支持されて前記制御棒を駆動
させる制御棒駆動機構7が設置されている。上記炉心支
持構造物4は吊り胴8を介してルーフスラブ2より吊り
下げられている。よって、炉心3を支持する炉心支持構
造物4と上記制御棒駆動機構7は共にルーフスラブ2に
支持されることになり、地震等により垂直方向に振動が
生じても上記両者の間の相対変位はきわめて少なくてす
み、地震時に制御棒3Bが炉心3に対して変位せず制御
が不安定となることを防止する。
An intermediate heat exchanger 5 and a circulation pump 6 are installed in the reactor vessel 1 on the outer periphery of the core support structure 4.
It is installed through the A control rod drive mechanism 7 is installed which similarly penetrates the roof slab 2 and is supported by the roof slab 2 to drive the control rod. The core support structure 4 is suspended from the roof slab 2 via a hanging shell 8. Therefore, the core support structure 4 that supports the reactor core 3 and the control rod drive mechanism 7 are both supported by the roof slab 2, and even if vibration occurs in the vertical direction due to an earthquake or the like, relative displacement between the two will not occur. It is possible to prevent the control rods 3B from being displaced with respect to the reactor core 3 during an earthquake, thereby preventing control from becoming unstable.

上記吊り胴8側壁には複数の流出口8Aが形成されてい
る。また炉心支持構1ハ4と原子炉容器1との間には振
れ止め部材9が設けられている。この振れ止め部材9は
吊り胴8によって吊持されている炉心8の水平方向の振
れを抑制する構成である。また、この振れ止め部材9は
、原子炉容器1内を上下に2分し、上方を上部プレナム
10.下方を下部プレナム1ノとする隔壁としての機能
も有している。なお図中12は原子炉容器1内に収容さ
れている冷却材を示す。
A plurality of outflow ports 8A are formed in the side wall of the hanging drum 8. Further, a steady rest member 9 is provided between the core support structure 1c4 and the reactor vessel 1. This steady rest member 9 is configured to suppress horizontal swing of the reactor core 8 suspended by the suspension barrel 8. Further, this steady rest member 9 divides the inside of the reactor vessel 1 into upper and lower halves, and the upper part is an upper plenum 10. It also functions as a partition wall with the lower plenum 1 located below. Note that 12 in the figure indicates a coolant contained in the reactor vessel 1.

以上の構成によると、冷却材12は、炉心3を下方から
上方に向けて上昇しその際昇温する。
According to the above configuration, the coolant 12 rises from the bottom to the top of the reactor core 3, and its temperature increases at this time.

そして高温となった冷却材12は吊り胴8内に流入し流
出口8Aを介して吊り胴8外に流出する。そして中間熱
交換器5の流入口より中間熱交換器5内に流入しそこで
2次冷却材(図示せず)と熱交換する。冷却された冷却
材12は中間熱交換器5の流出口より下部プレナム内に
流れ込み循環ポンプ6により加圧されて再度前記炉心3
下方に送り込まれる構成である。
The coolant 12, which has reached a high temperature, flows into the suspension shell 8 and flows out of the suspension shell 8 through the outlet 8A. The coolant then flows into the intermediate heat exchanger 5 from the inlet of the intermediate heat exchanger 5, where it exchanges heat with a secondary coolant (not shown). The cooled coolant 12 flows into the lower plenum from the outlet of the intermediate heat exchanger 5, is pressurized by the circulation pump 6, and then flows into the core 3 again.
It is configured to be sent downward.

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

以上の構成によると、振れ止め部材9の上方に形成され
た上部ゾレナム全体書二高温の冷却材が流入する。よっ
て原子炉容器ノは高温冷却材に接触する。また隔壁機能
を有する上記振れ止め部材9はその上面に高温の冷却材
が接触し、下面には低温の冷却材が接触する。そして、
原−子炉容器1は内部に収容された多量の冷却材や各機
器の荷重を支持するため構造的に強固なものであり、ま
た振れ止め部材9も地震時における炉心3の水平方向の
振れを防止するため構造的に強固なものであり、ともに
剛性が太きい。
According to the above configuration, the high-temperature coolant flows into the upper solenum formed above the steady rest member 9. The reactor vessel is thus in contact with the high temperature coolant. Further, the steady rest member 9 having a partition function has its upper surface in contact with a high-temperature coolant, and its lower surface in contact with a low-temperature coolant. and,
The reactor vessel 1 is structurally strong in order to support the load of a large amount of coolant and various equipment housed inside, and the anti-sway member 9 also prevents horizontal shaking of the reactor core 3 during an earthquake. It is structurally strong to prevent this, and both have high rigidity.

このため、これら原子炉容器1や振れ止め部材9に高温
の冷却材が接触した場合、熱変形の逃げが少ないため過
大な熱応力が発生する不具合があった。
For this reason, when a high-temperature coolant comes into contact with the reactor vessel 1 or the steady rest member 9, there is a problem in that excessive thermal stress is generated because there is little escape of thermal deformation.

〔発明の目的〕[Purpose of the invention]

本発明の目的は、中間熱交換器を取り囲むように中間熱
交換器シェルを設け、吊り胴内と上記中間熱交換器シェ
ル内を連通管により連通させることにより、高温冷却材
の流路を形成し、原子炉容器や振れ止め部材に高温冷却
材が直接接触しない構成とし、原子炉容器や振れ止め部
材に熱応力が生じることのない高速増殖炉を提供するこ
とにある。
An object of the present invention is to form a high-temperature coolant flow path by providing an intermediate heat exchanger shell to surround the intermediate heat exchanger and communicating the inside of the hanging shell and the inside of the intermediate heat exchanger shell through a communication pipe. Another object of the present invention is to provide a fast breeder reactor having a structure in which high-temperature coolant does not come into direct contact with the reactor vessel or the steady rest member, and in which thermal stress is not generated in the reactor vessel or the steady rest member.

〔発明の概要〕[Summary of the invention]

本発明による高速増殖炉は原子炉容器を設け、この原子
炉容器の上部開口を閉塞するルーフスラブを設け、上記
原子炉容器内に炉心を設け、スラブより吊り下げる吊り
胴を設け、この昂り胴外周面と前記原子炉容器内周面と
の間に中間熱交換器を設けこの中間熱交換器を取り囲む
ように中間熱交換器シェルを設け、この中間熱交−5−
rr 換器シェル内と前記吊り胴内部とを連通ずる連通管を設
けた構成である。
The fast breeder reactor according to the present invention is provided with a reactor vessel, a roof slab that closes the upper opening of the reactor vessel, a reactor core provided within the reactor vessel, and a suspension shell suspended from the slab. An intermediate heat exchanger is provided between the outer peripheral surface of the shell and the inner peripheral surface of the reactor vessel, and an intermediate heat exchanger shell is provided to surround the intermediate heat exchanger, and this intermediate heat exchanger -5-
rr This configuration includes a communication pipe that communicates the inside of the exchanger shell and the inside of the hanging barrel.

すなわち中間熱交換器外周を中間熱交換器シェルで取り
囲み、吊り胴内部と中間熱変換器シェルとを連通管で連
通させ、高温の冷却材を直接中間熱変換器に送るもので
ある。
That is, the outer periphery of the intermediate heat exchanger is surrounded by an intermediate heat exchanger shell, and the inside of the suspension shell and the intermediate heat converter shell are communicated with each other through a communication pipe, so that high-temperature coolant is directly sent to the intermediate heat converter.

したがって高温冷却材は吊り胴内部から中間熱交換器シ
ェル内へ連通管を介して直接通流するので、原子炉容器
や振れ止め部材に高温冷却材が直接接触することはなく
原子炉容器や振れ止め部材に大きな熱応力が生じること
はない。
Therefore, the high-temperature coolant flows directly from the inside of the suspension shell into the intermediate heat exchanger shell via the communication pipe, so the high-temperature coolant does not come into direct contact with the reactor vessel or steady rest members, and No large thermal stresses occur in the stop member.

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

第2図を参照して本発明の第一実施例を説明する。図中
101は冷却材100を収容している原子炉容器を示す
。この原子炉容器101の上部開口J OIAはルーフ
スラブ102によって閉塞されている。上記原子炉容器
101内には複数の燃料集合体xo’th、制御棒1θ
3B等より構成されている炉心(JIHψ・3が所定位
置に設置されている。この炉心103は炉心支持構1ハ
                   − 6−遺物
104により支持されている。この炉心支持構造物1θ
4外周の上記原子炉容器101内には中間熱交換器10
5および循環ポンプ106が前記ルーフスラブ102を
貫通して設置されている。同じく上記ルーフスラブ10
2を貫通しかつルーフスラブ102に支持されて前記制
御棒を駆動させる制御棒駆動機構107が設置されてい
る。また前記炉心支持構造物104は円筒状の吊り胴J
OBを介してルーフスラブ102より吊り下げられてい
る。すなわち炉心103を支持する炉心支持構造物10
4は共にルーフスラブ102に支持されることになり、
地震等により垂直方向に振動が生じても上記両者の間の
相対変位はきわめて少なくてすむ構成である。そして炉
心支持構造物104と原子炉容器101との間には振れ
止め部材109が設けられている。この振れ止め部材1
09により炉心103を支持している炉心支持構造物1
04の水平方向の振れを抑制する構成である。
A first embodiment of the present invention will be described with reference to FIG. In the figure, 101 indicates a reactor vessel housing the coolant 100. The upper opening JOIA of this reactor vessel 101 is closed by a roof slab 102. Inside the reactor vessel 101, there are a plurality of fuel assemblies xo'th, control rods 1θ
A core (JIHψ・3) consisting of 3B, etc. is installed at a predetermined position. This core 103 is supported by a core support structure 1 H-6- relic 104. This core support structure 1θ
4. An intermediate heat exchanger 10 is located inside the reactor vessel 101 on the outer periphery.
5 and a circulation pump 106 are installed passing through the roof slab 102. Same as above roof slab 10
A control rod drive mechanism 107 is installed that passes through the roof slab 2 and is supported by the roof slab 102 to drive the control rods. Further, the core support structure 104 is a cylindrical suspension structure J.
It is suspended from the roof slab 102 via the OB. That is, the core support structure 10 that supports the core 103
4 are both supported by the roof slab 102,
Even if vibration occurs in the vertical direction due to an earthquake or the like, the relative displacement between the two is extremely small. A steady rest member 109 is provided between the core support structure 104 and the reactor vessel 101. This steady rest member 1
Core support structure 1 supporting core 103 by 09
This is a configuration that suppresses the horizontal shake of 04.

前記中間熱変換器105の外周側には、この中間熱交換
器105を取り囲むように中間熱交換器シェル110が
設けられている。この中間熱交換器シェル110は前記
振れ止め部材109により支持されている。そしてこの
中間熱交換器シェル110内部と吊り胴10B内部とは
連通管111により連通されている。すなわち上記吊り
胴108から中間熱交換器シェル110への高温冷却材
を連通管111を介して直接溝びく構成である。よって
上記吊り胴108、中間熱交換器シェル110および連
通管111により高温冷却材と低温冷却材との境界を形
成している。したがって吊り胴108内の高温冷却材は
連通管111を通り中間熱交換器シェル110内に流入
し原子炉容器101に接することなく中間熱交換器10
5内に流入する構成である。さらに中間熱交換器シェル
105外側の原子炉容器101内上部には原子炉容器1
01下方より低温冷却材が流入する構成となっており原
子炉容器101を低温に保持する構成となっている。
An intermediate heat exchanger shell 110 is provided on the outer peripheral side of the intermediate heat exchanger 105 so as to surround the intermediate heat exchanger 105. This intermediate heat exchanger shell 110 is supported by the steady rest member 109. The interior of the intermediate heat exchanger shell 110 and the interior of the suspension shell 10B are communicated through a communication pipe 111. That is, the configuration is such that high-temperature coolant is directly channeled from the suspension shell 108 to the intermediate heat exchanger shell 110 via the communication pipe 111. Therefore, the suspension shell 108, the intermediate heat exchanger shell 110, and the communication pipe 111 form a boundary between the high-temperature refrigerant and the low-temperature refrigerant. Therefore, the high temperature coolant in the suspension shell 108 flows into the intermediate heat exchanger shell 110 through the communication pipe 111 and does not come into contact with the reactor vessel 101.
5. Furthermore, a reactor vessel 1 is provided in the upper part of the reactor vessel 101 outside the intermediate heat exchanger shell 105.
The structure is such that low-temperature coolant flows in from below 01 to maintain the reactor vessel 101 at a low temperature.

以上の構成をもとにその作用を説明する。まず冷却材1
00は炉心103を下方より上方に通流しその際昇温す
る。昇温した冷却材100は吊り胴10B内に流入する
。そして連通管11ノ内を通流し中間熱交換器シェル1
10内に流入し、中間熱交換器105の流入口(図示せ
ず)より中間熱交換器105内に流入する。
The operation will be explained based on the above configuration. First, coolant 1
00 flows through the core 103 from the bottom to the top, raising the temperature at that time. The heated coolant 100 flows into the suspension shell 10B. Then, the communication pipe 11 is passed through the intermediate heat exchanger shell 1.
10 and flows into the intermediate heat exchanger 105 from an inlet (not shown) of the intermediate heat exchanger 105.

そして、この高温の冷却材はこの中間熱交換器105内
で二次冷却材(図示せず)と熱交換し低温となった冷却
材は中間熱交換器105の流出口(図示せず)より原子
炉容器101下方に流出する。そして循環ポンプ106
により加圧され再度炉心103下方に送り込まれる構成
である。
This high-temperature coolant exchanges heat with a secondary coolant (not shown) in the intermediate heat exchanger 105, and the low-temperature coolant flows from the outlet (not shown) of the intermediate heat exchanger 105. It flows out below the reactor vessel 101. and circulation pump 106
The structure is such that the fuel is pressurized by the reactor core 103 and sent again to the lower part of the reactor core 103.

したがって原子炉容器101および振れ止め部材109
には低温の冷却材のみが接触し、過大な熱応力の発生を
防止することができる。
Therefore, the reactor vessel 101 and the steady rest member 109
Only low-temperature coolant comes into contact with the tube, which prevents excessive thermal stress from occurring.

次に第3図を参照して本発明の第2実施例を説明する。Next, a second embodiment of the present invention will be described with reference to FIG.

この第2実施例は中間熱交換器シェル110を複数の支
持部材112を介して吊り胴108に支持している。前
記第1実施例では振れ止め部#109により上記中間熱
交換器シェル110を支持する構成であったが、振れ止
め部材109による支持をやめ、支持部材112を設け
ることにより連通管111と吊りjliilloIの取
付は部および連通管111と中間熱交換器シェル110
との取付は部の応力を緩和する構成である。その他の構
成は前記第1実施例と同じ構成である。
In this second embodiment, an intermediate heat exchanger shell 110 is supported by a suspension shell 108 via a plurality of support members 112. In the first embodiment, the intermediate heat exchanger shell 110 is supported by the steady rest part #109, but the support by the steady rest member 109 is discontinued and a supporting member 112 is provided, thereby making it possible to connect the communication pipe 111 to the hanging pipe. The installation of the connecting pipe 111 and the intermediate heat exchanger shell 110
The mounting structure is designed to relieve stress on the parts. The other configurations are the same as those of the first embodiment.

次に第4図を参照して第3実施例を説明する。Next, a third embodiment will be described with reference to FIG.

この第3実施例は中間熱交換器シェル110を振れ止め
部材109により支持したものである。
In this third embodiment, an intermediate heat exchanger shell 110 is supported by a steady rest member 109.

そして吊り胴108と上記中間熱交換器シェル110を
連通する連通管111は可撓管で構成されている。そし
て中間熱交換器105のケーシング105べの下端部は
可撓継手113を介して中間熱交換器シェル110の下
端部に接続されている。
A communication pipe 111 that communicates the suspension shell 108 with the intermediate heat exchanger shell 110 is made of a flexible pipe. The lower end of the casing 105 of the intermediate heat exchanger 105 is connected to the lower end of the intermediate heat exchanger shell 110 via a flexible joint 113.

そして、この′!s3実施例は連通管JJJを伸縮性を
有する苛撓管で構成することにより吊り胴10Bと中間
熱交換器105の相対変位を吸収することができる。
And this'! In the s3 embodiment, the communication tube JJJ is made of a flexible tube having elasticity, so that the relative displacement between the hanging shell 10B and the intermediate heat exchanger 105 can be absorbed.

なお以上箱1ないし第3の実施例では中間熱交換器シェ
ル110を振れ止め部材109あるいは吊り胴10Bよ
り支持した構成としたが、ルーフスラブ102より吊り
下げた状態で支持してもよい。
Although the intermediate heat exchanger shell 110 is supported by the steady rest member 109 or the hanging frame 10B in the above-described embodiments 1 to 3, it may be supported in a suspended state from the roof slab 102.

〔発明の効果〕〔Effect of the invention〕

本発明による高速増殖炉は原子炉容器を設け、この原子
炉容器の上部開口を閉塞するルーフスラブを設は上記原
子炉容器内に炉心を設は上記原子炉容器内に上記炉心を
支持する炉心支持構造物を設け、この炉心支持構造物を
前記ルーフスラブより吊り下ける吊り胴を設け、この吊
り胴外周面と前記原子炉容器内周面との間に中間熱交換
器を設け、この中間熱交換器を取り囲むように中間熱交
換器シェルを設け、この中間熱タ換器シェル内および前
記吊り胴内部を連通ずる連通管を設けた構成であや。
The fast breeder reactor according to the present invention includes a reactor vessel, a roof slab that closes an upper opening of the reactor vessel, a reactor core within the reactor vessel, and a reactor core that supports the reactor core within the reactor vessel. A support structure is provided, a suspension shell for suspending the core support structure from the roof slab is provided, an intermediate heat exchanger is provided between the outer circumferential surface of the suspension structure and the inner circumferential surface of the reactor vessel, and An intermediate heat exchanger shell is provided to surround the heat exchanger, and a communication pipe is provided to communicate the inside of the intermediate heat exchanger shell and the inside of the suspension shell.

すなわち中間熱交換器外周を中間熱交換器シェルで取り
囲み吊り胴内部と中間熱交換器シエ11− 11o・・・中間熱交換器シェル、111・・・連通管
That is, the outer periphery of the intermediate heat exchanger is surrounded by an intermediate heat exchanger shell, and the inside of the suspension shell and the intermediate heat exchanger shells 11-11o...intermediate heat exchanger shell, 111...communicating pipes.

ルとを連通管で連通させ高温の冷却材を直接中間熱交換
器に送るものである。
The high-temperature coolant is directly sent to the intermediate heat exchanger by communicating with the intermediate heat exchanger through a communication pipe.

したがって高温冷却材は吊り胴内部から中間熱交換器シ
ェル内へ連通管を介して直接通流するので従来のように
原子炉容器や振れ止め部材に高温冷却材が直接接触する
ことはなく原子炉容器や振れ止め部材に大きな熱応力が
生じることもない。また吊り胴、連通管および中間熱交
換器シェルにて従来の隔壁機能をも構成していCるので
構成を簡単にすることができる等その効果は大である。
Therefore, the high-temperature coolant flows directly from the inside of the suspension shell into the intermediate heat exchanger shell via the communication pipe, so the high-temperature coolant does not come into direct contact with the reactor vessel or steady rest members, as in the case of conventional reactor vessels. No large thermal stress is generated in the container or the steady rest member. In addition, since the hanging body, the communicating pipe, and the intermediate heat exchanger shell also perform the conventional partition wall function, the structure can be simplified and other effects are great.

の縦断面図である。FIG.

101・・・原子炉容器、102・・・ルーフスラブ、
103・・・炉心、104・・・炉心支持構造物、10
5・・・中間熱交換器、10B・・・帛り胴、12−
101... Reactor vessel, 102... Roof slab,
103... Core, 104... Core support structure, 10
5... Intermediate heat exchanger, 10B... Woven cylinder, 12-

Claims (2)

【特許請求の範囲】[Claims] (1)原子炉容器と、この原子炉容器の上部開口を閉塞
するルーフスラブと、上記原子炉容器内に設けられた炉
心と、上記原子炉容器内に設けられ上記炉心を支持する
炉心支持構造物と、この炉心支持構造物を前記ルーフス
ラブより吊り下げる吊り胴と、この吊り胴外周面と前記
原子炉容器内周面との間に設けられた中間熱交換器と、
この中間熱交換器を取り囲むように設けられた中間熱交
換器シェルと、この中間熱交換器シェル内と前記吊り胴
内部とを連通ずる連通管とを具備したことを特徴とする
高速増殖炉。
(1) A reactor vessel, a roof slab that closes the upper opening of the reactor vessel, a core provided within the reactor vessel, and a core support structure provided within the reactor vessel that supports the core. a suspension shell for suspending the core support structure from the roof slab; an intermediate heat exchanger provided between the outer peripheral surface of the suspension shell and the inner peripheral surface of the reactor vessel;
A fast breeder reactor comprising: an intermediate heat exchanger shell provided to surround the intermediate heat exchanger; and a communication pipe that communicates the inside of the intermediate heat exchanger shell with the inside of the hanging shell.
(2)上記連通管は可撓性を有していることを特徴とす
る特許請求の範囲第1項記載の高速増殖炉。
(2) The fast breeder reactor according to claim 1, wherein the communication pipe has flexibility.
JP57084319A 1982-05-19 1982-05-19 Fast breeder Pending JPS58201089A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57084319A JPS58201089A (en) 1982-05-19 1982-05-19 Fast breeder

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57084319A JPS58201089A (en) 1982-05-19 1982-05-19 Fast breeder

Publications (1)

Publication Number Publication Date
JPS58201089A true JPS58201089A (en) 1983-11-22

Family

ID=13827184

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57084319A Pending JPS58201089A (en) 1982-05-19 1982-05-19 Fast breeder

Country Status (1)

Country Link
JP (1) JPS58201089A (en)

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