JPS6394190A - Decay heat removing system of fast breeder reactor - Google Patents

Decay heat removing system of fast breeder reactor

Info

Publication number
JPS6394190A
JPS6394190A JP61237838A JP23783886A JPS6394190A JP S6394190 A JPS6394190 A JP S6394190A JP 61237838 A JP61237838 A JP 61237838A JP 23783886 A JP23783886 A JP 23783886A JP S6394190 A JPS6394190 A JP S6394190A
Authority
JP
Japan
Prior art keywords
decay heat
reactor
air
power recovery
fast breeder
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
JP61237838A
Other languages
Japanese (ja)
Inventor
健一 橋詰
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
Toshiba Corp
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 filed Critical Toshiba Corp
Priority to JP61237838A priority Critical patent/JPS6394190A/en
Publication of JPS6394190A publication Critical patent/JPS6394190A/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
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Heat-Exchange Devices With Radiators And Conduit Assemblies (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) [Abstract] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

【発明の詳細な説明】 〔発明の目的〕 (産業上の利用分野) 本発明は高速増殖炉に関し、特に空気の自然通風により
崩壊熱を除去する高速増幅炉の崩壊熱除去系に関する。
DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Industrial Application Field) The present invention relates to a fast breeder reactor, and more particularly to a decay heat removal system for a fast breeder reactor that removes decay heat by natural ventilation of air.

(従来の技術) 高速増殖炉の崩壊熱を除去する方法として空気の自然通
壁を利用する方法が考えられている。第2図はそのよう
な崩壊熱除去系を示したものである。図示しない炉心を
囲む安全容器(υは原子炉室■の中に収納されている。
(Prior Art) As a method for removing decay heat from a fast breeder reactor, a method using a natural air passage wall has been considered. Figure 2 shows such a decay heat removal system. A safety vessel (not shown) surrounding the reactor core (υ) is housed in the reactor room ■.

安全容器の外側はシュラウド■で囲まれており、その底
部は通気孔(へ)が原子炉室内に開口し、その上部は排
気ダクト■に連通している。さらに原子炉室には空気取
入口0を有する吸気ダクト■が連通している。このよう
な構成の崩壊熱除系では安全容器を介して伝達される炉
心からの崩壊熱によってシュラウド内の空気が加熱昇温
され、排気ダクトの煙突効果によって外部に排出される
。すなわち、空気Aは空気取入ロ0→吸気ダクト■→原
子炉室■→通気孔(イ)→排気ダクト■の経路で自然通
風を生じ、崩壊熱を無動力で除去することができるので
、崩壊熱除去系の簡素化による設備費の低減の他に固有
の安全性を増大する特徴がある。しかしながらその反面
、崩壊熱を無動力で自然通風だけにより除去するために
は排気ダクトの高さを高くして煙突効果を確保する必要
があり、そうすると定常運転時において安全容器を必要
以上に冷却してしまい。本来は熱出力として利用できる
熱を無駄に外部にすててしまうという欠点があった。
The outside of the safety vessel is surrounded by a shroud (■), the bottom of which has a vent opening into the reactor chamber, and the top of which communicates with the exhaust duct (■). Furthermore, an intake duct (2) having an air intake port 0 communicates with the reactor room. In a decay heat removal system having such a configuration, the air in the shroud is heated and heated by the decay heat from the core transmitted through the safety vessel, and is discharged to the outside by the chimney effect of the exhaust duct. In other words, air A generates natural ventilation along the route of air intake B0 → intake duct ■ → reactor room ■ → ventilation hole (A) → exhaust duct ■, and decay heat can be removed without power. In addition to reducing equipment costs due to the simplification of the decay heat removal system, it has features that increase inherent safety. On the other hand, however, in order to remove decay heat only by natural ventilation without power, it is necessary to increase the height of the exhaust duct to ensure a chimney effect, which would cool the safety container more than necessary during steady operation. It's over. The drawback was that heat that could originally be used as heat output was wasted outside.

(発明が解決しようとする問題点) 本発明は上記欠点を解決するためのもので、定常運転時
には安全容器を必要以上に冷却せず外部に捨てられる熱
エネルギーを回収利用し、炉停止時には崩壊熱を十分に
除去できる高速増幅炉の崩壊熱除去系を提供することを
目的とする。
(Problems to be Solved by the Invention) The present invention is intended to solve the above-mentioned drawbacks. During steady operation, the safety container is not cooled more than necessary, and the thermal energy that is discarded outside is recovered and used, and when the reactor is shut down, it collapses. The purpose of the present invention is to provide a decay heat removal system for a fast amplification reactor that can sufficiently remove heat.

〔発明の構成〕[Structure of the invention]

(問題点を解決するための手段) 本発明は空気取入口と原子炉室を結ぶ吸気ダクトの内部
に空気タービンを設け、さらにこの空気タービンの回転
軸に断続可能な動力回収システムを設けたことを特徴と
する高速増幅炉の崩壊熱除去系である。
(Means for Solving the Problems) The present invention provides an air turbine inside the intake duct that connects the air intake and the reactor room, and further provides an intermittent power recovery system on the rotating shaft of the air turbine. This is a decay heat removal system for a fast amplification reactor that is characterized by:

(作 用) 上記構成において、炉停止時には動力回収システムを断
とすれば空気タービンは空転して通風抵抗が減少するの
で、崩壊熱を十分に除去することができる。一方、定常
運転時には動力回収システムを続とすれば、空気タービ
ンがら動力が回収されるので通風抵抗は増大し、自然通
風量が抑制されて安全容器を必要以上には冷却すること
なく、また、外部に捨てられる熱エネルギーを回収利用
できる作用効果を発揮する。
(Function) In the above configuration, when the power recovery system is cut off when the reactor is shut down, the air turbine idles and ventilation resistance is reduced, so that decay heat can be sufficiently removed. On the other hand, if the power recovery system is used during steady operation, the power is recovered from the air turbine, which increases ventilation resistance, suppresses the amount of natural ventilation, and prevents the safety container from being cooled more than necessary. It exhibits the effect of recovering and utilizing heat energy that would otherwise be discarded to the outside.

(実施例) 以下本発明の一実施例を第1図を引用しながら説明する
。なおこの図において第2図と同一構成要素には同一番
号を符してその説明を省略する。
(Example) An example of the present invention will be described below with reference to FIG. In this figure, the same components as those in FIG. 2 are designated by the same numbers and their explanations will be omitted.

第1図が第2図と異なる点は空気取入口と原子炉室との
間に空気タービン動力回収システム旦を設けたことであ
る。この空気タービン動力回収システムは吸気ダクト■
内に設けた空気タービン■、この回転軸に順次接続され
た電磁クラッチ(10)、変速機(11)および動力回
収機(12)とから成る。
The difference between FIG. 1 and FIG. 2 is that an air turbine power recovery system is provided between the air intake and the reactor chamber. This air turbine power recovery system uses the intake duct■
It consists of an air turbine (1) installed inside, an electromagnetic clutch (10), a transmission (11), and a power recovery machine (12) connected sequentially to this rotating shaft.

電磁クラッチは通電時続、非通電侍所が望ましい1次に
上記実施例の作用について説明する。定常運転時には電
磁クラッチには通電されて空気タービン■と動力回収機
が接続され自然通風から動力回収が行なわれる。このと
き空気タービンで動力が回収されているため吸気ダクト
内の通風抵抗は増大し、自然通風量が抑制されている。
It is preferable that the electromagnetic clutch be energized only once and not energized.Firstly, the operation of the above embodiment will be explained. During steady operation, the electromagnetic clutch is energized, connecting the air turbine (1) and the power recovery machine, and recovering power from natural ventilation. At this time, since the power is recovered by the air turbine, the ventilation resistance in the intake duct increases, and the amount of natural ventilation is suppressed.

炉停止時には電磁クラッチは非通電になり、空気タービ
ンと動力回収機が切り離されるので、空気タービンは空
転し、この結果、吸気ダクト内の通風抵抗は減少して自
然通風量が増大する。なお上記実施例において動力回収
機(12)は発電機のほかに水ポンプ、送風ブロワ、冷
凍機用圧縮機などであっても良い、また、変速機(11
)は必らずしも必要としない。
When the furnace is shut down, the electromagnetic clutch is de-energized and the air turbine and power recovery machine are disconnected, so the air turbine idles, resulting in a decrease in ventilation resistance in the intake duct and an increase in the amount of natural ventilation. In addition, in the above embodiment, the power recovery machine (12) may be a water pump, an air blower, a compressor for a refrigerator, etc. in addition to the generator, and the power recovery machine (12) may be a water pump, an air blower, a compressor for a refrigerator, etc.
) is not necessarily required.

〔発明の効果〕〔Effect of the invention〕

本発明によれば炉停止時には崩壊熱を十分に除去し、定
常運転時には安全容器を必要以上には冷却しない崩壊熱
除去系を実現することができる。
According to the present invention, it is possible to realize a decay heat removal system that sufficiently removes decay heat when the reactor is shut down and does not cool the safety vessel more than necessary during steady operation.

定常運転時には空気タービン動力回収システムにより得
られる動力で発電を行うほか、原子炉建屋空調用冷凍機
圧縮機駆動、ルーフスラブ冷却用の水ポンプまたはガス
循環ブロワ駆動などに利用でき、所内動力低減に寄与で
きる。さらに、空気タービンと動力回収機との間に通電
時続の電磁クラッチを設けておけば、たとえば電源喪失
事故時には自動的に電磁クラッチが断となり空気タービ
ンが動力回収機から切り離されるので自然通風量が自動
的に増大して崩壊熱を除去するから固有の安全性を増す
効果を有する。
During steady operation, the power obtained from the air turbine power recovery system is used to generate electricity, and can also be used to drive chiller compressors for reactor building air conditioning, water pumps or gas circulation blowers for cooling roof slabs, etc., reducing in-house power consumption. I can contribute. Furthermore, if a energized electromagnetic clutch is installed between the air turbine and the power recovery machine, for example, in the event of a power loss accident, the electromagnetic clutch will automatically disconnect and the air turbine will be separated from the power recovery machine, resulting in natural ventilation. It has the effect of increasing inherent safety because it automatically increases and removes decay heat.

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

第1図は本発明の一実施例を示す断面図、第2図は従来
例を示す断面図である。 1・・・安全容器、   2・・・原子炉室、3・・・
シュラウド、  4・・・通気孔、5・・・排気ダクト
、   6・・・空気取入口、7・・・吸気ダクト、 一β−・・・空気タービン動力回収システム9・・・空
気タービン、 10・・・W1磁クラッチ11・・・変
速機、    12・・・動力回収機。 代理人 弁理士  則 近 憲 体 間     竹 花 喜久男 第 ・1・°図 第2図
FIG. 1 is a sectional view showing one embodiment of the present invention, and FIG. 2 is a sectional view showing a conventional example. 1...Safety vessel, 2...Reactor room, 3...
Shroud, 4...Vent hole, 5...Exhaust duct, 6...Air intake port, 7...Intake duct, 1β-...Air turbine power recovery system 9...Air turbine, 10 ...W1 magnetic clutch 11...transmission, 12...power recovery machine. Agent Patent Attorney Nori Chika Kikuo Tama Takehana No. 1・°Fig. 2

Claims (1)

【特許請求の範囲】[Claims] 高速増殖炉の炉外を空気の自然通風で冷却し崩壊熱を除
去するものにおいて、空気取入口と原子炉室との間に空
気タービンによる動力回収システムを設けたことを特徴
とする高速増幅炉の崩壊熱除去系。
A fast breeder reactor that cools the outside of the reactor by natural air ventilation to remove decay heat, and is characterized in that a power recovery system using an air turbine is installed between an air intake port and a reactor chamber. decay heat removal system.
JP61237838A 1986-10-08 1986-10-08 Decay heat removing system of fast breeder reactor Pending JPS6394190A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP61237838A JPS6394190A (en) 1986-10-08 1986-10-08 Decay heat removing system of fast breeder reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP61237838A JPS6394190A (en) 1986-10-08 1986-10-08 Decay heat removing system of fast breeder reactor

Publications (1)

Publication Number Publication Date
JPS6394190A true JPS6394190A (en) 1988-04-25

Family

ID=17021160

Family Applications (1)

Application Number Title Priority Date Filing Date
JP61237838A Pending JPS6394190A (en) 1986-10-08 1986-10-08 Decay heat removing system of fast breeder reactor

Country Status (1)

Country Link
JP (1) JPS6394190A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5043136A (en) * 1990-06-21 1991-08-27 General Electric Company Passive cooling safety system for liquid metal cooled nuclear reactors
US5049353A (en) * 1989-04-21 1991-09-17 Westinghouse Electric Corp. Passive containment cooling system

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5049353A (en) * 1989-04-21 1991-09-17 Westinghouse Electric Corp. Passive containment cooling system
US5043136A (en) * 1990-06-21 1991-08-27 General Electric Company Passive cooling safety system for liquid metal cooled nuclear reactors

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