JPS60138301A - Steam generator for fast breeder reactor - Google Patents

Steam generator for fast breeder reactor

Info

Publication number
JPS60138301A
JPS60138301A JP58250316A JP25031683A JPS60138301A JP S60138301 A JPS60138301 A JP S60138301A JP 58250316 A JP58250316 A JP 58250316A JP 25031683 A JP25031683 A JP 25031683A JP S60138301 A JPS60138301 A JP S60138301A
Authority
JP
Japan
Prior art keywords
steam generator
shroud
fast breeder
steam
sodium
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
JP58250316A
Other languages
Japanese (ja)
Inventor
古村 史朗
巖 大島
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
Nippon Genshiryoku Jigyo KK
Nippon Atomic Industry Group Co Ltd
Original Assignee
Toshiba Corp
Nippon Genshiryoku Jigyo KK
Nippon Atomic Industry Group 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 Toshiba Corp, Nippon Genshiryoku Jigyo KK, Nippon Atomic Industry Group Co Ltd filed Critical Toshiba Corp
Priority to JP58250316A priority Critical patent/JPS60138301A/en
Publication of JPS60138301A publication Critical patent/JPS60138301A/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

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  • Production Of Liquid Hydrocarbon Mixture For Refining Petroleum (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】 [発明の技術分野〕 本発明は高速増殖炉用蒸気発生器に関する。[Detailed description of the invention] [Technical field of invention] The present invention relates to a steam generator for a fast breeder reactor.

[発明の技術的背景コ ナトリウムの如ぎ液体金属を一次冷却材、二次冷却祠と
する高速増殖炉において、炉心の発生熱を一次冷却材を
介して中間熱交換器に伝達し、この中間熱交換器と蒸気
発生装置の間を二次冷却材ぐ伝熱させるようにし−Cい
る。
[Technical background of the invention] In a fast breeder reactor that uses a liquid metal such as conodium as a primary coolant and a secondary cooling tank, the heat generated in the core is transferred to an intermediate heat exchanger via the primary coolant. A secondary coolant is used to transfer heat between the heat exchanger and the steam generator.

第1図は従来の高速増殖炉の二次冷Mj系およびそのイ
」局装置の概略構成を示すもので、−次冷nJ系1から
中間熱交換器2に導入された一次冷却材は中間熱交換器
2丙にJ′3いて二次冷却材に原子炉芹生熱を伝熱りる
Figure 1 shows the schematic configuration of the secondary cooling Mj system and its i' station equipment of a conventional fast breeder reactor. J'3 is in heat exchanger 2 and transfers reactor raw heat to the secondary coolant.

この伝熱ににって過熱された二次冷)l]trAはボッ
1〜レグ3およびホラ1〜レグ止弁4を経て過だ)器5
に流入し、さらにり【−1スオーバー配管6から蒸発器
7に導入され、タービン駆動用過熱蒸気を発生させC自
身は冷7J1された後、コールドレグ止弁8、膨張タン
ク9を経て循環ポンプ10に至り、ここで再び加圧され
くコールドレグ11を通し°C中間熱交換器2に導入さ
れる。
The secondary cooling (l)trA superheated by this heat transfer passes through the bottom 1 to leg 3 and the hole 1 to leg stop valve 4) vessel 5
It is further introduced into the evaporator 7 from the swover pipe 6, generates superheated steam for driving the turbine, and after being cooled 7J1, it passes through the cold leg stop valve 8 and the expansion tank 9 to the circulation pump. 10, where it is again pressurized and introduced into the °C intermediate heat exchanger 2 through the cold leg 11.

二次冷却材との熱交換により発生した過熱蒸気は破1f
A20で示すようにタービン21に導入され、これを駆
動した後、復水器22で復水化され、さらに給水加熱器
23で熱交換された後、円び蒸発器7に導入される。
The superheated steam generated by heat exchange with the secondary coolant breaks down to 1f.
As shown at A20, the water is introduced into the turbine 21, driven, and then condensed in the condenser 22, further heat-exchanged in the feed water heater 23, and then introduced into the circular evaporator 7.

ホットレグ止弁4の上流側と膨張タンク9の間には過熱
器5および蒸発器7をバイパスするようにして空気冷却
器30が設けられ−Cいる。
An air cooler 30 is provided between the upstream side of the hot leg stop valve 4 and the expansion tank 9 so as to bypass the superheater 5 and the evaporator 7.

この空気冷ムij器3oは原子炉崩壊熱を散逸さける補
助炉心冷却系を構成するものひ、ホットレグ止弁4の上
流側から分岐した分岐管31を流れる二次冷却材は冷却
ブロア32にょっ゛c2気冷却器30内に導入される空
気によって冷IJ+された後、コールドレグ配管33お
よびこのコールドレグ配管33に介挿したコールドレグ
調整弁3/Iを軽−C膨張タンク9内に送り込まれる。
This air cooling system 3o constitutes an auxiliary core cooling system to avoid dissipating reactor decay heat.The secondary coolant flowing through a branch pipe 31 branched from the upstream side of the hot leg stop valve 4 is passed through a cooling blower 32. After being cooled by the air introduced into the c2 air cooler 30, the cold leg piping 33 and the cold leg regulating valve 3/I inserted in the cold leg piping 33 are sent into the light-C expansion tank 9.

前述の膨張タンク9は二次冷却材の膨張収縮を吸収−リ
−ることを主目的とじて使用されるものである。この膨
張、タンクとオーハーフ]」−タンク4゜の間はオーバ
ーフロー調節弁41を備えたオーバーフロー配管42と
、吸上げポンプ43を介挿した吸上げ配管44ぐ接続さ
れている。また膨張タンク9の出口側のコールドレグ配
管35とオーハーフ[1−タンク40どの間はドレン弁
45を備えたドレン管46’r連結されている。
The above-mentioned expansion tank 9 is used primarily to absorb and release the expansion and contraction of the secondary coolant. During this expansion, an overflow pipe 42 having an overflow control valve 41 and a suction pipe 44 having a suction pump 43 are connected between the tank and the tank 4°. Further, a cold leg pipe 35 on the outlet side of the expansion tank 9 and a drain pipe 46'r equipped with a drain valve 45 are connected between the OHALF [1 and the tank 40].

オーハーフ1−1−タンク4oには、止弁47を備えた
連通管−′133を介しで液体ナトリウム貯蔵用のA−
バー71−1−タンク49が連結されている。なJ3、
ル“6服タンク983よびΔ−バーフロータンク40.
49内のニ丁次冷7.11材液面上にはアルゴンガスの
如き不活性ガスがカバーガスとして封入され、図示を省
略した配管系によって連通されている。
A-1 for storing liquid sodium is connected to OHALF 1-1-tank 4o via a communicating pipe-'133 equipped with a stop valve 47.
Bar 71-1 and tank 49 are connected. Na J3,
6 clothes tank 983 and Δ-bar flow tank 40.
An inert gas such as argon gas is sealed as a cover gas above the liquid surface of the 7.11 material in the cooling chamber 49, and is communicated by a piping system (not shown).

一方、過熱器5 J>よび蒸発器7の二次冷却月出入ロ
部にはそれぞれ破裂板51a、51.52;i 、52
bが接続され(いる。
On the other hand, rupture discs 51a, 51, 52;
b is connected.

これらの破裂板は、過熱器5または蒸発器7において、
万一蒸気や水が漏洩し、二次冷却材である液体ナトリウ
ム反応してもナトリウム−水反応生成物によって、二次
冷却系の圧ツノが異常値に達しないよう安全弁としC機
能するもので、各破裂板31a 、31b 、52a 
、52b (1)二次側ハソれぞれ連結配管53を介し
く反応生成物収納タンク54に接続されている。また、
反応生成物収納タンク54の上端には大気放出用破裂板
55、逆止弁56おJ:び点火器5を備えた大気放出f
R58が設【プられている。
These rupture discs are installed in the superheater 5 or evaporator 7,
In the unlikely event that steam or water leaks and reacts with liquid sodium, which is the secondary coolant, the sodium-water reaction product acts as a safety valve to prevent the pressure horn in the secondary cooling system from reaching an abnormal value. , each rupture disc 31a, 31b, 52a
, 52b (1) The secondary side pipes are each connected to a reaction product storage tank 54 via a connecting pipe 53. Also,
At the upper end of the reaction product storage tank 54, there is provided an atmospheric release rupture plate 55, a check valve 56, and an igniter 5.
R58 is installed.

第2図は第1図の蒸気発生器7(−例とし−C蒸光器)
の詳細を一部側面C゛示す縦断面図である。
Figure 2 shows the steam generator 7 in Figure 1 (-as an example--C steamer)
It is a vertical cross-sectional view partially showing details of the side view C'.

冷ム1目号は上部人口配餘・60から蒸発器本体7a内
に流入し、本体7aの下部に設けた出[]へd管61か
ら流出−リ−る。給水は本体7aの下部に設【プた人口
部62から流入し、伝熱管67部r熱交換が行なわれ、
水体7aの上部に設()I〔出口部63から蒸気どなつ
−C流出づる。蒸発器本体7aの出]」、入1」配管6
0.61にはそれぞれ破裂板52a1521〕が設けら
れており、連絡配管53を介しC反応生成収納タンク5
/Iに接続されている。
Cold air 1 flows into the evaporator main body 7a from the upper distribution valve 60 and flows out from the d pipe 61 to an outlet provided at the lower part of the main body 7a. The water supply flows from the artificial part 62 installed in the lower part of the main body 7a, and heat exchange is performed by the heat exchanger tube 67 part.
A steam outlet is provided at the upper part of the water body 7a. Out]”, in 1” piping 6 of evaporator main body 7a
0.61 are each equipped with a rupture disc 52a1521], and are connected to the C reaction production storage tank 5 via the connecting pipe 53.
/I is connected.

上述のように(14成した高速増殖炉の二次冷却装F7
においで、原子炉の通常運転時には循環ポンプ10で循
環される二次冷却材は中間熱交換器2におい(原子′y
J’iの発生熱を伝熱された後、過熱器5おJ、び蒸発
器7にa3い−C放熱し、タービン21を含も発電設値
1へ熱を伝える。
As mentioned above, the secondary cooling system of the fast breeder reactor F7
During normal operation of the reactor, the secondary coolant circulated by the circulation pump 10 smells in the intermediate heat exchanger 2 (atomic 'y
After the heat generated by J'i is transferred, the heat is radiated to the superheater 5, the evaporator 7, and the evaporator 7, and the heat is transferred to the power generation equipment 1 including the turbine 21.

このような状態C1過熱器5または蒸発器7−rすl・
リウムー水−反応が生じた場合には、破裂板51a、5
1b、52a、52bのいずれかが破裂し、反応生成物
が連結配管53を経由しC反応生成物収容タンク54に
至り、そこで分回された気体は大気放出用破裂板55を
破り、外気逆流前1L川の逆止弁56を流過し、可紫(
カス成分は点火器57t’着火、燃焼した後、人気中に
放出される。
In such a state C1 superheater 5 or evaporator 7-r.
If a lium-water reaction occurs, the rupture discs 51a, 5
1b, 52a, or 52b ruptures, the reaction product passes through the connecting pipe 53 and reaches the C reaction product storage tank 54, where the separated gas ruptures the atmosphere release rupture plate 55 and causes the outside air to flow back. Flowing past the check valve 56 of the previous 1L river, the purple color (
After the scum components are ignited by the igniter 57t' and burned, they are released into the air.

「青石技術の問題点」 しかしながら、−L J シた蒸気発生器、りなわら過
熱器5または蒸発器7内で蒸気または水が′、ll−リ
ウム側へ漏洩した場合、ナ1〜リウムー水反応によつC
発生する反応生成ガスにより圧力が急増し、その結果、
破裂4N51a 、51b 、52a 、52− わが
破壊され、反応生成物は反応生成物収容タンク54へ移
行覆るが、以下に)ボベる欠点があった。
``Problems with blue stone technology'' However, if steam or water leaks to the -LJ-shita steam generator, Rinawara superheater 5 or evaporator 7 to the ',ll-lium side, the sodium-lium-water reaction will occur. Yotsu C
The resulting reaction product gas causes a sudden increase in pressure, resulting in
Rupture 4N51a, 51b, 52a, 52- The 4Ns were destroyed and the reaction product moved to the reaction product storage tank 54 and covered it, but there was a drawback (see below) that it was blown away.

ツなわら、従来の蒸気発生器ひは、破裂板の取付けは蒸
気発生器の出入口配管に分岐させて設置されでいる。そ
のため、蒸気発生器内でナトリウム−水反応が生じた場
合、まず非圧縮性のナトリウムが大Mlに放出された後
、反応生成ガスが初めて蒸気発生器内から反応生成物収
納タンク54側へ放出される。これは二次系内の圧力を
迅速に低減させるという観点にJ3い−C非常に大きな
問題となる。
However, in conventional steam generators, the rupture disc is installed by branching into the inlet and outlet piping of the steam generator. Therefore, when a sodium-water reaction occurs in the steam generator, incompressible sodium is first released into large ml, and then the reaction product gas is first released from the steam generator to the reaction product storage tank 54 side. be done. This becomes a very big problem from the viewpoint of quickly reducing the pressure in the secondary system.

つまり、非圧縮のす1〜リウム放出は、二次系内の圧力
低減にはあまり影響しないため、ナトリウムを放出して
いる間の圧力の減少は緩やかである。
In other words, since the incompressible release of sodium does not significantly affect the pressure reduction in the secondary system, the pressure decreases slowly while sodium is released.

そのため、二次系に設置されCいる他の機器および配管
等に高圧力が伝播し、その結果、機器および配管等を破
損させる可能性があり、原子炉の安全性を確保すること
からも大ぎな問題となる。
As a result, high pressure may propagate to other equipment and piping installed in the secondary system, resulting in damage to the equipment and piping, which is a major concern from the perspective of ensuring the safety of the reactor. This is a serious problem.

[発明の目的] 本発明は背傾技桁にa31=ノる上述の如き不都合を除
去すべくなされたもので、蒸気発生器内でナトリウム−
水反応が発生し高圧の反応生成物が生成されでも迅速に
高圧の反応生成物を反応生成物収納タンク内へ放t]1
することが可能な高速増殖炉用蒸気発生器を提供づるも
のである。
[Object of the Invention] The present invention has been made to eliminate the above-mentioned disadvantages caused by the back-tilting girder, and is aimed at eliminating sodium-
Even if a water reaction occurs and a high-pressure reaction product is produced, the high-pressure reaction product is quickly released into the reaction product storage tank]1
The present invention provides a steam generator for a fast breeder reactor that can be used in a fast breeder reactor.

[発明の概要1 すなわち本発明は゛、蒸気発生器本体に配置されてい内
部シュラウドを、その上端および下端を11じて中空の
円筒状容器どし、この内部シュラウドの中央近傍にナト
リウムの流入または流出が可能な多数の流路孔を設ける
とともに、内部シュラウドの上部または上部または両部
に破裂板が介挿されCいる連絡配管を接続してなる蒸気
発生器である。本発明にJ:って従来の蒸気発生器C′
問題となつCいた点を解決している。
[Summary of the Invention 1] That is, the present invention provides an internal shroud disposed in a steam generator main body, the upper and lower ends of which are formed into a hollow cylindrical container, and sodium inflow or outflow near the center of the internal shroud. This is a steam generator that has a large number of flow passage holes that allow for a rupture plate to be inserted in the upper part of the inner shroud, and a rupture disc inserted in the upper part or both parts of the inner shroud, and connected to connecting pipes. According to the present invention, J: the conventional steam generator C'
This solves a number of problematic points.

[発明の実施例] 以下第3図(15よび第4図を参照して本発明の各々の
実施例を31明する。
[Embodiments of the Invention] Each embodiment of the present invention will be explained below with reference to FIG. 3 (FIG. 15 and FIG. 4).

第3図は本発明に係る蒸気発生器の第1の実施例を示し
たしのC1第2図と同一部分は同一符号で示し、−重複
りる部分の説明を省略する。
FIG. 3 shows a first embodiment of a steam generator according to the present invention. Parts that are the same as those in FIG.

第3図が第2図と異なる点は、本体7内に配置された内
部シュラウド68の上部80および下部81を閉塞して
、その上部80および下部81の壁面にそれぞれ連絡管
53a 、53bを接続し、これらの連絡管53a 、
53bにそれぞれ破裂板42a、52bを設けて第1図
に示す連絡配管53に接続したことにある。破裂管42
a 、52bは本体7の上端板を異通して設けられCい
る。また、内部シュラウド68の中央部には多数の小孔
を石スるナトリウムの流路孔70が設けられCいる。
The difference between FIG. 3 and FIG. 2 is that the upper part 80 and lower part 81 of the internal shroud 68 disposed in the main body 7 are closed, and the communication pipes 53a and 53b are connected to the walls of the upper part 80 and lower part 81, respectively. These connecting pipes 53a,
53b are provided with rupture discs 42a and 52b, respectively, and connected to the connecting pipe 53 shown in FIG. Rupture tube 42
a and 52b are provided through the upper end plate of the main body 7. Further, in the center of the inner shroud 68, there is provided a passage hole 70 for sodium passing through a large number of small holes.

第4図は本発明の他の実施例を示したちのC1第3図と
同一部分には同一符号を示し重複りる部分の説明を省略
Jる。
FIG. 4 shows another embodiment of the present invention. Components that are the same as those in FIG.

第4図が第3図と異なる点は、内部シュラウド68の下
部81にドレン孔72を設りるととしに、連絡’R53
a、53bを本体7aの下部側面から導出し−C破裂板
52a、52bを設りたことにある。
The difference between FIG. 4 and FIG. 3 is that when a drain hole 72 is provided in the lower part 81 of the internal shroud 68,
a, 53b are led out from the lower side of the main body 7a, and -C rupture discs 52a, 52b are provided.

第3図および第4図においで符号60は蒸気発生器本体
7aに接続された入口配管であり、同じく61はナトリ
ウム出口配管である。水系(より−i〜リウムの流れと
は逆に給水管62から流入し、伝熱管・67部Ml−リ
ウムとの熱交換を行な(1、蒸気出口管63から流出し
て蒸気はタービン系へ運ばれる。 − 前述したように、本体7a内の中心部には内部シコラウ
ド6Bが配置され、上端および下端を生りじ中空の円筒
容器を形成している。そし”にの内部シュラウド68の
上部80および下部81に(、t、破裂板52a 、5
21+が介挿された連絡配管53a、5311が接Wt
され(いる。まlコ、内81Sシュラウド68の中央近
傍にはナトリウムの流入まlこ(よ流出が可能な流路孔
が設けである。
In FIGS. 3 and 4, reference numeral 60 is an inlet pipe connected to the steam generator main body 7a, and 61 is a sodium outlet pipe. The water system (from the water system -i~ flows in from the water supply pipe 62 in the opposite direction to the flow of lithium, and exchanges heat with the heat exchanger tube 67 part Ml-lium. (1) The steam flows out from the steam outlet pipe 63 and the steam flows into the turbine system. - As mentioned above, an internal shroud 6B is arranged at the center within the main body 7a, forming a hollow cylindrical container with an upper end and a lower end. The upper part 80 and the lower part 81 (,t, rupture disc 52a, 5
21+ is inserted, the connecting pipe 53a and 5311 are connected to Wt.
Near the center of the inner 81S shroud 68, there is a passage hole through which sodium can flow in and out.

−シシ何らかの理由により、伝熱管67が破1(4シ、
水または蒸気がブー1〜リウム側に漏洩し、ブー1−1
ノウム一水反応が発生した場合、反応生成カスにJこり
蒸気発生器本体7a内は高圧となり、その結果、破裂板
52a 、52bのいずれかまl〔は両名力く破壊する
。これにJ二り、蒸気発生器内゛C発生した高圧のナト
リウム−水反応生成ガスはナトリウムとともに内部シュ
ラウド68の中央部に設けられた流路70を通り、直ら
”に反応生成物収納タンク54へ放出Jることができ、
蒸気発生器内の圧力を迅速に低減することが可能となる
- For some reason, the heat exchanger tube 67 broke 1 (4).
Water or steam leaks from Boo 1 to Boo 1-1.
When the nitrogen-water reaction occurs, the pressure inside the steam generator main body 7a becomes high due to the residue produced by the reaction, and as a result, either or both of the rupture discs 52a and 52b are violently destroyed. In addition, the high-pressure sodium-water reaction product gas generated in the steam generator passes through a flow path 70 provided in the center of the internal shroud 68 together with sodium, and directly flows into the reaction product storage tank 54. can be released to
It becomes possible to quickly reduce the pressure within the steam generator.

なお、第4図に承り実施例では、第3図で説明した作用
効果については同様に期待できるととしに、内内部シュ
ラウド68下端部に設()たドレン孔72により内部シ
ュラウド68内に存在するす1−リウムをドレン′りる
ことも可能な構成どなっている。
In addition, in the embodiment shown in FIG. 4, the function and effect explained in FIG. The structure is such that it is possible to drain the 1-lium.

「発明の効果J 以」一連へたように本発明に係る高速増殖炉用蒸気発生
器によれば、伝熱管に破損が生じブトリウムー水反応に
より高圧の圧縮性反応住成刀スが発生しても直ちに反応
生成収納タンク内へそれを放出りることができ、その結
果、二次系内のハーカ上賃を迅速にしかも安全に低減で
きる。従っ・Cに次系(浅器a3よび配管への影響を防
止できることは勿論のこと、原子炉の安全性J3よび稼
動率向上に寄与でき、非富に大きな効果を奏する。
``Effects of the Invention J'' As described above, according to the steam generator for a fast breeder reactor according to the present invention, the heat transfer tubes are damaged and high-pressure compressible reaction gas is generated due to the butryum-water reaction. It is also possible to immediately release the reaction product into the storage tank, and as a result, the amount of heat in the secondary system can be quickly and safely reduced. Therefore, it is possible not only to prevent the influence on the next system (shallow vessel A3 and piping), but also to contribute to the safety of the reactor J3 and the improvement of the operation rate, which has a great effect on the economy.

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

第1図は従来の高速増殖炉の二次系を概略的に示す系統
図、第2図は従来の蒸気発生器を一部側面で示す縦断面
図、第3図および第4図は本発明に係る高速増M’i力
j用熱気発生器のそれぞれの実施例を一部側面で示TI
縦断面図である。 1・・・・・・・・・・・・−次冷N)系2・・・・・
・・・・・・・中間熱交換器3・・・・・・・・・・・
・ホットレグ4・・・・・・・・・・・・ホットレグ止
弁5・・・・・・・・・・・・過熱器 6・・・・・・・・・・・・クロスオーバー配管7・・
・・・・・・・・・・蒸発器 8・・・・・・・・・・・・二1−ルドレグ止弁9・・
・・・・・・・・・・l1iQ 張タンク10・・・・
・・・・・・・・循環ポンプ11・・・・・・・・・・
・・コールドレグ20・・・・・・・・・・・・破線 21・・・・・・・・・・・・タービン22・・・・・
・・・・・・・復水器 23・・・・・・・・・・・・給水加熱器30・・・・
・・・・・・・・空気冷却器31・・・・・・・・・・
・・分岐管 32・・・・・・・・・・・・冷h1ゾロア33・・・
・・・・・・・・・コールドレグ配管3/l・・・・・
・・・・・・・コールドレグ調整弁40・・・・・・・
・・・・・オーバーフ[]−タンク52a、52b−破
裂板 53・・・・・・・・・・・・連絡配管60・・・・・
・・・・・・・す1〜リウム入ロ配管61・・・・・・
・・・・・・す1〜リウム出ロ配管62・・・・・・・
・・・・給水配管 63・・・・・・・・・・・・蒸気出口配管6/′I・
・・・・・・・・・・h3気出ロ管台65・・・・・・
・・・・・・熱遮蔽板66・・・・・・・・・・・ブー
 1−リウム分配板67・・・・・・・・・・・・伝熱
管 68・・・・・・・・・・・・内部シュラウド69・・
・・・・・・・・・・給水入口管台70・・・・・・・
・・・・・流路孔 71・・・・・・・・・・・・然気発生器本体72・・
・・・・・・・・・・ナトリウムドレン孔80・・・・
・・・・・・・・内部シュラウド上部81・・・・・・
・・・・・・内部シュラウド下部代理人弁理士 須 山
 In。 第2図 几 第3図
Fig. 1 is a system diagram schematically showing the secondary system of a conventional fast breeder reactor, Fig. 2 is a vertical sectional view partially showing a conventional steam generator from the side, and Figs. 3 and 4 are the invention of the present invention. A partial side view of each embodiment of the hot air generator for high speed increase M'i
FIG. 1......-Next cooling N) system 2...
・・・・・・Intermediate heat exchanger 3・・・・・・・・・・・・
・Hot leg 4...Hot leg stop valve 5...Superheater 6...Crossover piping 7・・・
・・・・・・・・・Evaporator 8・・・・・・・・・・・・21-Ledreg stop valve 9...
・・・・・・・・・l1iQ Zhang tank 10・・・・
......Circulation pump 11...
・・・Cold leg 20・・・・・・・・・・・・Dotted line 21・・・・・・・・・Turbine 22・・・・・・
......Condenser 23...Feed water heater 30...
......Air cooler 31...
...Branch pipe 32... Cold h1 Zorua 33...
......Cold leg piping 3/l...
......Cold leg adjustment valve 40...
...Overflow [] - Tanks 52a, 52b - Rupture disc 53 ...... Connection piping 60 ...
......S1~Lium-filled piping 61...
...S1~Lium outlet piping 62...
...Water supply pipe 63...Steam outlet pipe 6/'I.
・・・・・・・・・h3 air outlet pipe stand 65・・・・・・
...Heat shield plate 66...Boo 1-Rium distribution plate 67...Heat transfer tube 68... ...Internal shroud 69...
・・・・・・・・・Water supply inlet pipe stand 70・・・・・・・
...Flow path hole 71...Natural air generator body 72...
......Sodium drain hole 80...
...Inner shroud upper part 81...
...Inner Shroud Lower Agent Patent Attorney Suyama In. Figure 2 Figure 3

Claims (2)

【特許請求の範囲】[Claims] (1)筒状竪形本体と、この本体の上下両端器に取着さ
れた一対のナトリウム出入口配管と、前記本体内の軸心
線に沿って配置され両端に連結・配管が接続された内部
シュラウドと、この内部シュラウドのほぼ中央部に形成
されたナトリウムの流路孔ど、前記連結配管に設けられ
た破裂板と、前記内部シュラウドに支持されかつ前記本
体内面に空間を有して設【プられた外部シュラウドぐ包
囲された伝熱管Iffと、この伝熱管群内九本し加熱蒸
気を流出する給水J5 J:び蒸気出口配管とを具備し
たことを特徴どする高速増殖炉用蒸気発生器。
(1) A cylindrical vertical body, a pair of sodium inlet and outlet pipes attached to the upper and lower ends of this body, and an interior arranged along the axis of the body and connected to both ends with connections and piping. A shroud, a sodium passage hole formed approximately at the center of the inner shroud, a rupture plate provided in the connecting pipe, and a rupture plate supported by the inner shroud and having a space on the inner surface of the main body. A steam generator for a fast breeder reactor, characterized in that it is equipped with a heat exchanger tube Iff surrounded by a closed outer shroud, a water supply J5 J: from which heated steam flows out of the nine heat exchanger tubes, and a steam outlet piping. vessel.
(2)内部シュラウドの底部にはドレン孔が形成されて
いることを特徴とする特r[請求の範囲第1r3記載の
高速増殖炉用蒸気発生器。
(2) A steam generator for a fast breeder reactor according to claim 1r3, characterized in that a drain hole is formed in the bottom of the internal shroud.
JP58250316A 1983-12-26 1983-12-26 Steam generator for fast breeder reactor Pending JPS60138301A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP58250316A JPS60138301A (en) 1983-12-26 1983-12-26 Steam generator for fast breeder reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP58250316A JPS60138301A (en) 1983-12-26 1983-12-26 Steam generator for fast breeder reactor

Publications (1)

Publication Number Publication Date
JPS60138301A true JPS60138301A (en) 1985-07-23

Family

ID=17206093

Family Applications (1)

Application Number Title Priority Date Filing Date
JP58250316A Pending JPS60138301A (en) 1983-12-26 1983-12-26 Steam generator for fast breeder reactor

Country Status (1)

Country Link
JP (1) JPS60138301A (en)

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