JPS6243156B2 - - Google Patents

Info

Publication number
JPS6243156B2
JPS6243156B2 JP54066760A JP6676079A JPS6243156B2 JP S6243156 B2 JPS6243156 B2 JP S6243156B2 JP 54066760 A JP54066760 A JP 54066760A JP 6676079 A JP6676079 A JP 6676079A JP S6243156 B2 JPS6243156 B2 JP S6243156B2
Authority
JP
Japan
Prior art keywords
cooling system
auxiliary core
air cooler
core cooling
piping
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
JP54066760A
Other languages
Japanese (ja)
Other versions
JPS55159196A (en
Inventor
Kenji Mori
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 JP6676079A priority Critical patent/JPS55159196A/en
Publication of JPS55159196A publication Critical patent/JPS55159196A/en
Publication of JPS6243156B2 publication Critical patent/JPS6243156B2/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
    • 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

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 本発明は液体金属冷却高速増殖炉において、2
次冷却系を共用する補助炉心冷却装置に関するも
のである。
DETAILED DESCRIPTION OF THE INVENTION The present invention provides a liquid metal cooled fast breeder reactor with two
This relates to an auxiliary core cooling system that shares a secondary cooling system.

従来、液体金属冷却高速増殖炉の2次冷却系共
用型の補助炉心冷却装置の一例としては第1図に
示すような蒸気発生器バイパス型の系統構成のも
のがある。この補助炉心冷却装置は、2次主冷却
系ホツトレグ配管5より分岐した補助炉心冷却装
置配管8、空気冷却器7、空気冷却器出口止め弁
15、空気冷却器出口流調弁16等より構成さ
れ、2次主冷却系コールドレグ配管6とはミキシ
ングテイー17にて合流するものである。一方、
2次主冷却系配管には蒸気発生器1を隔離するた
め、蒸気発生器入口止め弁14、蒸気発生器出口
止め弁13が設置されている。
Conventionally, as an example of an auxiliary core cooling system for a liquid metal cooled fast breeder reactor that is shared with the secondary cooling system, there is a steam generator bypass type system configuration as shown in FIG. This auxiliary core cooling system is composed of an auxiliary core cooling system piping 8 branched from the secondary main cooling system hot leg piping 5, an air cooler 7, an air cooler outlet stop valve 15, an air cooler outlet flow control valve 16, etc. , and the secondary main cooling system cold leg piping 6 at a mixing tee 17. on the other hand,
A steam generator inlet stop valve 14 and a steam generator outlet stop valve 13 are installed in the secondary main cooling system piping to isolate the steam generator 1.

補助炉心冷却装置は、原子炉停止後の崩壊熱を
中間熱交換器3を介して1次主冷却系より除去
し、その熱を2次主冷却系循環ポンプ2により空
気冷却器7へ輪送し、最終的に大気へ逃す機能を
持つている。
The auxiliary core cooling system removes decay heat after reactor shutdown from the primary main cooling system via the intermediate heat exchanger 3, and transfers the heat to the air cooler 7 by the secondary main cooling system circulation pump 2. It has the function of finally escaping into the atmosphere.

本発明は上記の補助炉心冷却装置の運転制御性
をさらに増すと共に、よりコンパクトで合理的な
設計でかつ高い信頼性を有する補助炉心冷却装置
を提供するものである。すなわち、第1の目的と
するところは、補助炉心冷却装置の待機運転時の
空気冷却器出口温度の制御性の問題、管側の偏流
の問題等をなくした運転制御性の良い補助炉心冷
却装置を得ることにある。次に第2の目的は、蒸
気発生器を隔離する系統構成のため必然妥的に必
要となる種々の弁並びに補助系の配管・弁を減ら
したコンパクトで合理的な設計の補助炉心冷却装
置を得ることにある。更に第3の目的は、上記2
つの目的を満足しながらかつ補助炉心冷却装置起
動時の熱過渡条件をできる限り緩和させた補助炉
心冷却装置を得ることにある。
The present invention further increases the operational controllability of the above-mentioned auxiliary core cooling system, and provides an auxiliary core cooling system that is more compact, has a rational design, and has high reliability. In other words, the first objective is to create an auxiliary core cooling system with good operational controllability that eliminates problems such as the controllability of the air cooler outlet temperature during standby operation of the auxiliary core cooling system and the problem of uneven flow on the tube side. It's about getting. The second objective is to create a compact and rationally designed auxiliary core cooling system that reduces the number of various valves and auxiliary system piping and valves that are inevitably necessary for the system configuration that isolates the steam generator. It's about getting. Furthermore, the third purpose is to
An object of the present invention is to obtain an auxiliary core cooling system that satisfies the following objectives and also alleviates as much as possible the thermal transient conditions at the time of starting the auxiliary core cooling system.

以下図面を参照して本発明の一実施例を説明す
る。
An embodiment of the present invention will be described below with reference to the drawings.

第2図は本発明の補助炉心冷却装置の系統構成
を示すものである。この図からわかるように、本
発明の補助炉心冷却装置は、2次主冷却系のコー
ルドレグ配管6より分岐した補助炉心冷却装置配
管8、空気冷却器7等より構成され、ミキシング
テイー17により再度コールドレグ配管6に合流
するものである。一方、補助炉心冷却装置配管8
の分岐とミキシングテイー17の間の2次主冷却
系配管には2次主冷却系止め弁26が設置され
る。
FIG. 2 shows the system configuration of the auxiliary core cooling device of the present invention. As can be seen from this figure, the auxiliary core cooling system of the present invention is composed of an auxiliary core cooling system piping 8 branched from the cold leg piping 6 of the secondary main cooling system, an air cooler 7, etc., and the mixing tee 17 cools the cold leg again. It joins the pipe 6. On the other hand, auxiliary core cooling system piping 8
A secondary main cooling system stop valve 26 is installed in the secondary main cooling system piping between the branch of the mixing tee 17 and the mixing tee 17 .

本発明の補助炉心冷却装置運転時には蒸気発生
器1は隔離されることがないので、冷却材のイン
ベントリー保持のためのオーバーフロー汲上げは
蒸気発生器1に対して行なう。
Since the steam generator 1 is not isolated during operation of the auxiliary core cooling system of the present invention, overflow pumping for maintaining coolant inventory is performed for the steam generator 1.

次に作用を説明する。このように構成されてい
る補助炉心冷却装置は、原子炉事故停止時の崩壊
熱除去を行なうものである。すなわち、原子炉が
トリツプすると、2次主冷却系循環ポンプ2はポ
ニーモータによる低速回転運転に移行し、2次主
冷却系止め弁26は閉止される。空気冷却器7
は、空気冷却器入口温度の上昇を検知して送風機
9を立上げ、同時に入口ダンパ10、出口ダンパ
12を全開とし、その後、ベーン10による空気
冷却器出口温度一定制御を行なう。一方、空気冷
却器7の待機運転時には、送風機9は停止し、ベ
ーン10、入口ダンパ11、出口ダンパ12を全
閉する。この時の空気冷却器7の放散熱量は定格
除熱容量の高々3%程度である。また、空気冷却
器7の管側流量は補助炉心冷却装置と2次主冷却
系止め弁26の圧力損失のバランスより決定され
るが、主系統流量の10%程度の流量が流れること
になる。従つて、空気冷却器7での温度降下は
高々10数度となり、ミキシングテイー17にはそ
の温度差が常時かかることになるが構造設計上問
題となる値ではない。
Next, the effect will be explained. The auxiliary core cooling system configured in this manner removes decay heat during a nuclear reactor accident shutdown. That is, when the nuclear reactor trips, the secondary main cooling system circulation pump 2 shifts to low-speed rotational operation by the pony motor, and the secondary main cooling system stop valve 26 is closed. air cooler 7
detects a rise in the air cooler inlet temperature, starts up the blower 9, simultaneously fully opens the inlet damper 10 and outlet damper 12, and then controls the air cooler outlet temperature to be constant using the vane 10. On the other hand, during standby operation of the air cooler 7, the blower 9 is stopped and the vane 10, inlet damper 11, and outlet damper 12 are fully closed. The amount of heat dissipated by the air cooler 7 at this time is about 3% of the rated heat removal capacity at most. Further, the flow rate on the tube side of the air cooler 7 is determined by the balance of pressure loss between the auxiliary core cooling device and the secondary main cooling system stop valve 26, but the flow rate is about 10% of the main system flow rate. Therefore, the temperature drop in the air cooler 7 is about 10 degrees at most, and this temperature difference is constantly applied to the mixing tee 17, but this is not a problem in terms of structural design.

本発明の補助炉心冷却装置は以上の説明のよう
に構成されているため待機運転時にも空気冷却器
管側の流量は十分確保されているので、待機運転
時の空気冷却器出口温度制御の必要もなく、空気
冷却器管側の偏流の恐れもない。又、系統の弁の
数も削限されており、蒸気発生器を隔離しないた
め、補助系の系統構成もコンパクトである。更
に、空気冷却器出口温度は常に一定温度以下に保
持されるので、2次主冷却系配管6、2次冷却系
循環ポンプ2、中間熱交換器3等に対する熱過渡
条件は緩和され、系統の信頼性が向上する。
Since the auxiliary core cooling system of the present invention is configured as described above, a sufficient flow rate on the air cooler tube side is ensured even during standby operation, so it is necessary to control the air cooler outlet temperature during standby operation. There is no risk of drifting on the air cooler tube side. Furthermore, the number of valves in the system is reduced, and the steam generator is not isolated, so the system configuration of the auxiliary system is also compact. Furthermore, since the air cooler outlet temperature is always maintained below a certain temperature, the thermal transient conditions for the secondary main cooling system piping 6, the secondary cooling system circulation pump 2, the intermediate heat exchanger 3, etc. are relaxed, and the system Improved reliability.

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

第1図は従来の2次冷却系共用型の補助炉心冷
却装置を示す系統図、第2図は本発明の2次冷却
系共用型補助炉心冷却装置の一実施例を示す系統
図である。 1……蒸気発生器、2……2次主冷却系循環ポ
ンプ、3……中間熱交換器、5……2次主冷却系
ホツトレグ配管、6……2次主冷却系コールドレ
グ配管、7……空気冷却器、8……補助炉心冷却
装置配管、9……送風機、10……ベーン、11
……入口ダンパ、12……出口ダンパ、18……
オーバーフロータンク、26……2次主冷却系止
め弁。
FIG. 1 is a system diagram showing a conventional auxiliary core cooling system for shared secondary cooling systems, and FIG. 2 is a system diagram showing an embodiment of the auxiliary core cooling system for shared secondary cooling systems of the present invention. 1... Steam generator, 2... Secondary main cooling system circulation pump, 3... Intermediate heat exchanger, 5... Secondary main cooling system hot leg piping, 6... Secondary main cooling system cold leg piping, 7... ...Air cooler, 8...Auxiliary core cooling system piping, 9...Blower, 10...Vane, 11
...Inlet damper, 12...Outlet damper, 18...
Overflow tank, 26... Secondary main cooling system stop valve.

Claims (1)

【特許請求の範囲】 1 液体金属冷却高速増殖炉の2次冷却装置配管
に設置した弁と、この弁をバイパスする流路と、
この流路に設置した空気冷却器とから構成される
ことを特徴とする補助炉心冷却装置。 2 液体金属冷却高速増殖炉の2次冷却装置の蒸
気発生器出口の配管に設置した弁と、この弁をバ
イパスする流路と、この流路に設置した空気冷却
器とから構成されることを特徴とする特許請求の
範囲第1項記載の補助炉心冷却装置。
[Claims] 1. A valve installed in the secondary cooling device piping of a liquid metal cooled fast breeder reactor, and a flow path that bypasses this valve;
An auxiliary core cooling device characterized by comprising an air cooler installed in this flow path. 2. It consists of a valve installed in the steam generator outlet piping of the secondary cooling system of a liquid metal cooled fast breeder reactor, a flow path that bypasses this valve, and an air cooler installed in this flow path. An auxiliary core cooling device according to claim 1, characterized in that:
JP6676079A 1979-05-31 1979-05-31 Auxiliary reactor core cooling device Granted JPS55159196A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP6676079A JPS55159196A (en) 1979-05-31 1979-05-31 Auxiliary reactor core cooling device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP6676079A JPS55159196A (en) 1979-05-31 1979-05-31 Auxiliary reactor core cooling device

Publications (2)

Publication Number Publication Date
JPS55159196A JPS55159196A (en) 1980-12-11
JPS6243156B2 true JPS6243156B2 (en) 1987-09-11

Family

ID=13325152

Family Applications (1)

Application Number Title Priority Date Filing Date
JP6676079A Granted JPS55159196A (en) 1979-05-31 1979-05-31 Auxiliary reactor core cooling device

Country Status (1)

Country Link
JP (1) JPS55159196A (en)

Also Published As

Publication number Publication date
JPS55159196A (en) 1980-12-11

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