JPS607167B2 - feed water heater system - Google Patents
feed water heater systemInfo
- Publication number
- JPS607167B2 JPS607167B2 JP15450077A JP15450077A JPS607167B2 JP S607167 B2 JPS607167 B2 JP S607167B2 JP 15450077 A JP15450077 A JP 15450077A JP 15450077 A JP15450077 A JP 15450077A JP S607167 B2 JPS607167 B2 JP S607167B2
- Authority
- JP
- Japan
- Prior art keywords
- feed water
- feedwater
- water heater
- heater
- heater system
- 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
Links
Landscapes
- Engine Equipment That Uses Special Cycles (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
【発明の詳細な説明】
本発明は給水加熱器システムに係り、特に沸騰水形原子
力発電所に使用するのに好適な給水加熱器システムに関
する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to feedwater heater systems, and more particularly to feedwater heater systems suitable for use in boiling water nuclear power plants.
従来の沸騰水形原子力発電所に使用されている給水加熱
器システムは、第1図に示すように、原子炉1で発生し
た原子炉蒸気を高圧タービン2から抽気して原子炉給水
の加熱源とする高圧第1、第2給水加熱器8,9と、そ
れを低圧タービン4から柚気して加熱源とする低圧第1
〜第4給水加熱器10〜13とよりなり、これらの給水
加熱器内で凝固した原子炉蒸気は、順次次段の給水加熱
器に導ぴいて、給水加熱器ドレンポンプ14でタービン
主復水器5のドライウェル部へ導びき、また、原子炉蒸
気中に含されている酸素、水素、希ガス等の非凝縮ガス
も順次次段の給水加熱器に導びし、て、最後にそれの空
間部に導び〈ようにしてある。As shown in Figure 1, the feedwater heater system used in conventional boiling water nuclear power plants extracts reactor steam generated in a nuclear reactor 1 from a high-pressure turbine 2 and uses it as a heating source for reactor feedwater. high-pressure first and second feed water heaters 8 and 9, and a low-pressure first feed water heater that uses aqueous air from the low-pressure turbine 4 as a heating source.
~Fourth feedwater heaters 10 to 13, and the reactor steam solidified in these feedwater heaters is sequentially guided to the next stage of feedwater heaters and sent to the turbine main condensate by the feedwater heater drain pump 14. In addition, non-condensable gases such as oxygen, hydrogen, and rare gases contained in the reactor steam are also successively introduced to the feedwater heater in the next stage, and finally, It is designed to lead to the space of
なお、第1図において、3は湿分分離器、6は復水脱塩
器、7は復水ポンプ、15は給水ポンプで、点線矢印は
蒸気または非凝縮ガスの流れ、実線矢印は給水または凝
縮した蒸気の流れを示している。しかし、このように接
続された給水加熱器システムでは、例えば、高圧第1給
水加熱器8で発生した凝縮水と非凝縮ガスが、高圧第2
給水加熱器9での給水の加熱用として再び使用されるの
で、非凝縮ガスは、第2図に示す給水加熱器の加熱器胴
体17内で凝縮水中にむりやり溶け込まされるというこ
とが起る。In Fig. 1, 3 is a moisture separator, 6 is a condensate demineralizer, 7 is a condensate pump, and 15 is a water supply pump, the dotted line arrow indicates the flow of steam or non-condensable gas, and the solid line arrow indicates the flow of water supply or water supply. It shows the flow of condensed steam. However, in a feed water heater system connected in this way, for example, condensed water and non-condensable gas generated in the high pressure first feed water heater 8 are transferred to the high pressure second feed water heater system.
Since it is used again for heating the feedwater in the feedwater heater 9, it occurs that the non-condensable gas is forced to dissolve into the condensate water in the heater body 17 of the feedwater heater shown in FIG.
そのため、前段の給水加熱器において高放射能が流入す
ると、次段以降の低放射能が流入する給水加熱器の機器
表面線量率が高放射能が流入する前段のものと等しくな
る。したがって、低圧給水加熱器10〜13の機器表面
線量率が、高放射能が流入する高圧給水加熱器8,9と
同じになるという現象が起る。そのため運転中の状態を
チェックするため、運転員が給水加熱器に近ずし、たと
きに放射能被ばくを受けるという問題を生ずる。なお、
第2図において、16は水室、18は熱交換チューブ、
19は仕切板、20は給水流入ノズル、21は給水流出
ノズル、22は蒸気流入ノズル、23は凝縮水流出ノズ
ル、24はペントノズルである。本発明は上記に鑑みて
なされたものであって、その目的とするところは、機器
表面線量率を低減することができる給水加熱器システム
を提供することにある。Therefore, when high radioactivity flows into the feed water heater in the previous stage, the equipment surface dose rate of the feed water heaters in the subsequent stages into which low radioactivity flows becomes equal to that of the previous stage into which high radioactivity flows. Therefore, a phenomenon occurs in which the device surface dose rate of the low-pressure feedwater heaters 10 to 13 becomes the same as that of the high-pressure feedwater heaters 8 and 9 into which high radioactivity flows. This creates the problem that when operators get close to the feedwater heater to check its operating status, they are exposed to radiation. In addition,
In Fig. 2, 16 is a water chamber, 18 is a heat exchange tube,
19 is a partition plate, 20 is a feed water inflow nozzle, 21 is a feed water outflow nozzle, 22 is a steam inflow nozzle, 23 is a condensed water outflow nozzle, and 24 is a pent nozzle. The present invention has been made in view of the above, and an object of the present invention is to provide a feed water heater system that can reduce the equipment surface dose rate.
本発明の特徴は、それぞれの給水加熱器のペントノズル
をタービン主復水器に直接接続し、凝縮水中への非凝縮
ガスの溶け込みを低減させるとともに、前段の給水加熱
器の非凝縮ガスとは無関係にして給水加熱器表面線量率
を低減するようにした点にある。A feature of the present invention is that the pent nozzle of each feedwater heater is directly connected to the turbine main condenser, which reduces the dissolution of non-condensable gas into the condensed water and is independent of the non-condensable gas of the preceding feedwater heater. The main point is that the dose rate on the surface of the feed water heater is reduced.
以下本発明を第3図に示した実施例および第4図を用い
て詳細に説明する。The present invention will be described in detail below with reference to the embodiment shown in FIG. 3 and FIG. 4.
第3図は本発明の給水加熱器システムの一実施例を示す
構成図で、第3図において、第1図と同一部分は同じ符
号で示し、説明を省略する。FIG. 3 is a configuration diagram showing an embodiment of the feed water heater system of the present invention. In FIG. 3, the same parts as in FIG.
第1図と異なるところは、高圧第1、第2給水加熱器8
,9および低圧第1〜第4給水加熱器10〜13のペン
トノズル24(第2図参照)をそれぞれ独立に流量制御
弁25を介してタービン主復水器5に直接接続するよう
にし、凝縮水中への非凝縮ガスの溶け込みを低減させる
とともに、一度分離した非凝縮ガスが次段の給水加熱器
内の凝縮水に再び溶け込むことがないようにした点にあ
る。上託した実施例のような給水加熱器システムにする
と、タービン主復水器5の負圧により、それぞれの給水
加熱器8〜13内も負圧となり、給水加熱器胴体内圧力
と機器表面線量率の主要線源となる放射性質N16の溶
け込み量との間に、第4図に示す関係があるから、NI
Bの凝縮水中への溶け込み量を抵滅することができる。
したがって、給水加熱器表面線量率は低下し、また、従
来のように前段の給水加熱器のペントノズル24を次段
の給水加熱器のペントノズル24に接続した場合のよう
な、前段の給水加熱器に高放射能が流入したときに、低
放射能が流入している次段以降の給水加熱器の表面線量
率が高放射能が流入している給水加熱器のそれと同じに
なるということがなくなる。そのため、給水加熱器を設
置してある部屋の空気中の放射能濃度(給水加熱器に設
けた弁からの漏洩に起因する)も低減し、運転員の放射
能被ばくを低減することができる。なお、給水加熱器の
ペントノズル24の口径および長さによって、給水加熱
器内の負圧の大きさを容易に設定することができ、また
、それを流量制御弁25を用いて行なうこともできる。
そして、給水加熱器内に流入する原子炉蒸気は、通常運
転中一定流量であるから、給水加熱器8〜13のペント
ノズル24をタービン主復水器5へ直接接続しても、ベ
ントノズル24を流れる非凝縮ガスの流量はほぼ一定で
あり、タービン主復水器5の運転に何ら支障をきたすこ
とはない。以上説明したように、本発明によれば、凝縮
水に溶け込む放射性物質を含む非凝縮ガスの量を低減で
きるから、これが線源となっている給水加熱器の表面線
量率が低下し、放射能被ばくを低減できるという顕著な
効果がある。The difference from Figure 1 is that the high pressure first and second feed water heaters 8
. This is to reduce the dissolution of non-condensable gas into the water heater, and to prevent the once-separated non-condensable gas from dissolving into the condensed water in the next-stage feed water heater. In the case of a feedwater heater system such as the one in the entrusted example, the negative pressure in the turbine main condenser 5 also creates negative pressure in each of the feedwater heaters 8 to 13, which reduces the pressure inside the feedwater heater body and the radiation dose on the surface of the equipment. Since there is a relationship shown in Figure 4 between the penetration amount of radioactive N16, which is the main source of radiation, the NI
The amount of B dissolved into condensed water can be reduced.
Therefore, the feedwater heater surface dose rate decreases, and the feedwater heater surface dose rate decreases, and the feedwater heater surface dose rate decreases. When high radioactivity flows in, there is no possibility that the surface dose rate of the feed water heaters of the next stage and subsequent stages into which low radioactivity flows will be the same as that of the feed water heaters into which high radioactivity flows. Therefore, the radioactivity concentration in the air in the room where the feedwater heater is installed (due to leakage from the valve installed in the feedwater heater) is also reduced, making it possible to reduce the radiation exposure of operators. Note that the magnitude of the negative pressure within the feed water heater can be easily set by the diameter and length of the pent nozzle 24 of the feed water heater, and this can also be done using the flow rate control valve 25.
Since the reactor steam flowing into the feedwater heater has a constant flow rate during normal operation, even if the pent nozzles 24 of the feedwater heaters 8 to 13 are directly connected to the turbine main condenser 5, the vent nozzles 24 The flow rate of the flowing non-condensable gas is almost constant, and does not cause any trouble in the operation of the turbine main condenser 5. As explained above, according to the present invention, it is possible to reduce the amount of non-condensed gas containing radioactive substances that dissolves in condensed water, which reduces the surface dose rate of the feed water heater, which is a radiation source, and increases radioactivity. It has the remarkable effect of reducing radiation exposure.
第1図は従来の給水加熱器システムの構成図、第2図は
給水加熱器の概略構造図、第3図は本発明の給水加熱器
システムの一実施例を示す構成図、第4図は給水加熱器
胴体内圧力と凝縮水中へのN16の溶け込み量との関係
線図である。
1・・・・・・原子炉、2・・・・・・高圧タービン、
4・・・・・・低,圧タービン、5…・・・タービン主
復水器、7・・…・復水ポンプ、8,9・・・…高圧第
1、第2給水加熱器、10〜13・・・・・・低圧第1
〜第4給水放熱器、14・・・・・・ドレンポンプ、1
5・・・・・・給水ポンプ、17・・・・・・給水加熱
器胴体、24・・・・・・ベントノズル。
糸′図糸Z図
衆3図
稀ム図Fig. 1 is a block diagram of a conventional feed water heater system, Fig. 2 is a schematic structural diagram of a feed water heater system, Fig. 3 is a block diagram showing an embodiment of the feed water heater system of the present invention, and Fig. 4 is a block diagram of a conventional feed water heater system. It is a relationship diagram between the pressure inside the feed water heater body and the amount of N16 dissolved into condensed water. 1...Nuclear reactor, 2...High pressure turbine,
4...Low pressure turbine, 5...Turbine main condenser, 7...Condensate pump, 8, 9...High pressure first and second feed water heaters, 10 ~13...Low pressure 1st
~4th water supply radiator, 14...Drain pump, 1
5... Water supply pump, 17... Water heater body, 24... Vent nozzle. Ito'zu Ito Z Zushu 3 Zumuzu
Claims (1)
おいて、前記それぞれの給水加熱器のベントノズルをタ
ービン復水器に直接接続したことを特徴とする給水加熱
器システム。1. A feedwater heater system comprising a plurality of feedwater heaters, characterized in that a vent nozzle of each of the feedwater heaters is directly connected to a turbine condenser.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP15450077A JPS607167B2 (en) | 1977-12-23 | 1977-12-23 | feed water heater system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP15450077A JPS607167B2 (en) | 1977-12-23 | 1977-12-23 | feed water heater system |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5487302A JPS5487302A (en) | 1979-07-11 |
| JPS607167B2 true JPS607167B2 (en) | 1985-02-22 |
Family
ID=15585592
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP15450077A Expired JPS607167B2 (en) | 1977-12-23 | 1977-12-23 | feed water heater system |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS607167B2 (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH06212907A (en) * | 1992-08-14 | 1994-08-02 | Westinghouse Electric Corp <We> | Steam turbine device, method for improving efficiency thereof, and steam turbine heat recovery device |
-
1977
- 1977-12-23 JP JP15450077A patent/JPS607167B2/en not_active Expired
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5487302A (en) | 1979-07-11 |
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