JPH068905B2 - Cooling water supply system for boiling water reactor - Google Patents
Cooling water supply system for boiling water reactorInfo
- Publication number
- JPH068905B2 JPH068905B2 JP59227257A JP22725784A JPH068905B2 JP H068905 B2 JPH068905 B2 JP H068905B2 JP 59227257 A JP59227257 A JP 59227257A JP 22725784 A JP22725784 A JP 22725784A JP H068905 B2 JPH068905 B2 JP H068905B2
- Authority
- JP
- Japan
- Prior art keywords
- drain
- water
- reactor
- feed water
- pressure
- 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 - Lifetime
Links
Classifications
-
- Y—GENERAL 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
-
- Y—GENERAL 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Physical Or Chemical Processes And Apparatus (AREA)
Description
【発明の詳細な説明】 〔発明の利用分野〕 本発明は、沸騰水型原子炉の冷却水供給装置に関するも
のである。Description: FIELD OF THE INVENTION The present invention relates to a cooling water supply device for a boiling water reactor.
従来の沸騰水型原子炉の冷却水供給装置を、第２図に基
づいて説明する。第２図に示す冷却水供給装置は、「タ
ービン・発電機講座」、ｐ２９〜３３、昭和５３年４月
（社団法人 火力発電技術協会）に示されているもので
ある。A conventional cooling water supply device for a boiling water reactor will be described with reference to FIG. The cooling water supply device shown in FIG. 2 is shown in “Turbine / Generator Course”, p29-33, April 1978 (The Thermal Power Generation Technology Association).
沸騰水型原子炉の原子炉圧力容器１で発生した蒸気は、
主蒸気配管２０により高圧タービン２及び低圧タービン
４に導かれてそれらを駆動した後に、復水器６により凝
縮される。３は、湿分分離器である。復水器６で得られ
た蒸気の凝縮水（沸騰水型原子炉の冷却水）は、低圧復
水ポンプ７で昇圧されてろ過器８、復水脱塩器９を通
り、再び高圧復水ポンプ１０で昇圧されて低圧給水加熱
器１２，１３，１４及び１５で順次昇温される。その
後、低圧給水加熱器１５から吐出された冷却水は、給水
ポンプ１１でさらに昇圧されて高圧給水加熱器１６及び
１７で昇温され、原子炉圧力容器１へ供給される。The steam generated in the reactor pressure vessel 1 of the boiling water reactor is
After being guided to the high-pressure turbine 2 and the low-pressure turbine 4 by the main steam pipe 20 and driving them, they are condensed by the condenser 6. 3 is a moisture separator. Condensed water of steam (cooling water for a boiling water reactor) obtained in the condenser 6 is boosted by the low-pressure condensate pump 7, passes through the filter 8 and the condensate demineralizer 9, and is again high-pressure condensate. The pressure is increased by the pump 10 and is sequentially increased by the low pressure feed water heaters 12, 13, 14 and 15. After that, the cooling water discharged from the low-pressure feed water heater 15 is further increased in pressure by the feed water pump 11, heated by the high-pressure feed water heaters 16 and 17, and supplied to the reactor pressure vessel 1.
低圧給水加熱器１２〜１５には、低圧タービン４から抽
気された蒸気が供給される。この抽気蒸気は、低圧給水
加熱器１２〜１５に供給される冷却水（前述した蒸気の
凝縮水）の加熱源になつている。高圧給水加熱器１６及
び１７には、高圧タービン２または主蒸気配管２０から
抽気した蒸気を冷却水の加熱用として供給されている。
高圧給水加熱器１６及び１７から吐出された抽気蒸気の
ドレン及び湿分分離器３にて分離された湿分のドレン
は、ドレンタンク１８に導かれてポンプ１９にて昇圧さ
れ、給水ポンプ１１と低圧給水加熱器１４との間の冷却
水供給管２１に導入されている。このように高圧給水加
熱器１６及び１７から吐出された抽気蒸気のドレン（高
温）を低圧給水加熱器１５の下流側で冷却水供給管２１
に供給しているので、沸騰水型原子炉の熱効率の向上が
図れる。The steam extracted from the low-pressure turbine 4 is supplied to the low-pressure feed water heaters 12 to 15. The extracted steam serves as a heating source of the cooling water (condensed water of the steam described above) supplied to the low-pressure feed water heaters 12 to 15. The steam extracted from the high-pressure turbine 2 or the main steam pipe 20 is supplied to the high-pressure feed water heaters 16 and 17 for heating the cooling water.
The drain of the extracted steam discharged from the high-pressure feed water heaters 16 and 17 and the drain of the moisture separated by the moisture separator 3 are guided to the drain tank 18 and boosted in pressure by the pump 19, and supplied to the feed pump 11. It is introduced into the cooling water supply pipe 21 between the low-pressure feed water heater 14. In this way, the drain (high temperature) of the extracted steam discharged from the high-pressure feed water heaters 16 and 17 is provided at the downstream side of the low-pressure feed water heater 15 with the cooling water supply pipe 21.
Is supplied to the boiling water reactor, the thermal efficiency of the boiling water reactor can be improved.
本発明の目的は、熱効率が高くしかも原子炉容器内への
放射化される物質の持込み量を低減できる沸騰水型原子
炉の冷却水供給装置を提供することにある。An object of the present invention is to provide a cooling water supply device for a boiling water reactor, which has high thermal efficiency and can reduce the carry-in amount of the substance to be activated into the reactor vessel.
本発明の特徴は、給水ポンプより下流側にある高圧給水
加熱器のドレンを、不純物除去手段を介して給水ポンプ
のサクシヨン側に戻すことにある。A feature of the present invention is that the drain of the high-pressure feed water heater downstream of the feed water pump is returned to the suction side of the feed water pump through the impurity removing means.
本発明は、従来の沸騰水型原子炉の冷却水供給装置を検
討することによつてなされたものである。The present invention has been made by considering a conventional cooling water supply device for a boiling water reactor.
従来の冷却水供給装置では、高圧給水加熱器のドレン水
を給水ポンプの上流側で冷却水供給管に直接戻してく
る。このため、高圧給水加熱器のシエル側（冷却水は高
圧給水加熱器の伝熱管内を通る）で発生した鉄クラツド
等の不純物が原子炉圧力容器内に持込まれる。原子炉圧
力容器内に入つた鉄クラツドが、炉心の燃料棒表面に付
着して放射化される。放射化された鉄クラツドが、燃料
棒表面から離れて、原子炉圧力容器内面または再循環系
配管の内面に付着してそれらの表面線量率を上昇させる
原因となる。このように本発明は、鉄クラツド等の炉心
内で放射化される物質が高圧給水加熱器内で腐食等によ
り生じることに着目してなされたものである。In the conventional cooling water supply device, the drain water of the high-pressure feed water heater is returned directly to the cooling water supply pipe upstream of the water supply pump. Therefore, impurities such as iron cladding generated on the shell side of the high-pressure feed water heater (cooling water passes through the heat transfer pipe of the high-pressure feed water heater) are brought into the reactor pressure vessel. The iron cladding that has entered the reactor pressure vessel adheres to the surface of the fuel rods in the core and is activated. The activated iron cladding separates from the surface of the fuel rods and adheres to the inner surface of the reactor pressure vessel or the inner surface of the recirculation system piping, causing their surface dose rates to rise. As described above, the present invention has been made by paying attention to the fact that a substance such as an iron clad that is activated in the core is generated by corrosion or the like in the high-pressure feed water heater.
本発明の実施例である沸騰水型原子炉の冷却水供給装置
を第１図に基づいて説明する。A cooling water supply device for a boiling water reactor, which is an embodiment of the present invention, will be described with reference to FIG.
原子炉圧力容器１で発生した蒸気は、主蒸気配管２０に
より、高圧タービン２、湿分分離器３及び低圧タービン
４へと送られる。５は、発電機である。低圧タービン４
から排出された蒸気は、復水器６で凝縮されて冷却水と
して冷却水供給管２１により原子炉圧力容器１に戻され
る。冷却水供給管２１は、原子炉圧力容器１及び復水器
６に接続され、それらの間では低圧復水ポンプ７、ろ過
器（ろ過脱塩器）８、復水脱塩器９、高圧復水ポンプ１
０、低圧給水加熱器１２〜１５、給水ポンプ１１、高圧
給水加熱器１６及び１７をこの順序で順次連絡してい
る。冷却水供給管２１内を流れる冷却水は、低圧給水加
熱器１２〜１５及び高圧給水加熱器１６及び１７内を通
つて加熱される。低圧給水加熱器１２〜１５のシエル側
には、抽気管２２〜２５によつて低圧タービン４から抽
気された蒸気が、冷却水の加熱用として供給される。高
圧給水加熱器１６のシエル側には、抽気管２６によつて
主蒸気配管２０より抽気された蒸気が供給される。高圧
給水加熱器１７のシエル側には、抽気管２７によつて高
圧タービン２より抽気された蒸気が供給される。The steam generated in the reactor pressure vessel 1 is sent to the high pressure turbine 2, the moisture separator 3 and the low pressure turbine 4 through the main steam pipe 20. 5 is a generator. Low pressure turbine 4
The steam discharged from the condenser is condensed in the condenser 6 and returned to the reactor pressure vessel 1 as cooling water by the cooling water supply pipe 21. The cooling water supply pipe 21 is connected to the reactor pressure vessel 1 and the condenser 6, and between them, a low pressure condensate pump 7, a filter (filter desalting device) 8, a condensate demineralizer 9, and a high pressure condenser. Water pump 1
0, the low-pressure feed water heaters 12 to 15, the feed water pump 11, and the high-pressure feed water heaters 16 and 17 are sequentially connected in this order. The cooling water flowing in the cooling water supply pipe 21 is heated by passing through the low pressure feed water heaters 12 to 15 and the high pressure feed water heaters 16 and 17. The steam extracted from the low-pressure turbine 4 through the extraction pipes 22 to 25 is supplied to the shell side of the low-pressure feed water heaters 12 to 15 for heating the cooling water. The steam extracted from the main steam pipe 20 is supplied to the shell side of the high-pressure feed water heater 16 by the extraction pipe 26. The steam extracted from the high-pressure turbine 2 is supplied to the shell side of the high-pressure feed water heater 17 through the extraction pipe 27.
低圧給水加熱器１２〜１５の隣接している相互のシエル
は、ドレン配管２８〜３０によつてそれぞれ連絡され
る。ドレンタンク１８Ａは低圧給水加熱器１２のシエル
に連絡される。制御弁３３を有するドレン配管３１は、
ドレンタンク１８Ａと復水器６を接続している。水位計
３７が、ドレンタンク１８Ａに取付けられている。ドレ
ン配管３２の一端は、ドレンタンク１８Ａと制御弁３３
の間のドレン配管３１の部分に接続される。ドレン配管
３２の他端は、復水脱塩器９と高圧復水ポンプ１０との
間の冷却水供給管２１に接続される。制御弁３４、ポン
プ３５及びろ過器３６が、ドレン配管３２に設けられ
る。Adjacent mutual shells of the low-pressure feed water heaters 12-15 are connected by drain pipes 28-30, respectively. The drain tank 18A is connected to the shell of the low-pressure feed water heater 12. The drain pipe 31 having the control valve 33 is
The drain tank 18A and the condenser 6 are connected. A water level gauge 37 is attached to the drain tank 18A. One end of the drain pipe 32 has a drain tank 18A and a control valve 33.
It is connected to the portion of the drain pipe 31 between. The other end of the drain pipe 32 is connected to the cooling water supply pipe 21 between the condensate demineralizer 9 and the high-pressure condensate pump 10. The control valve 34, the pump 35, and the filter 36 are provided in the drain pipe 32.
高圧給水加熱器１６のシエルと高圧給水加熱器１７のシ
エルは、ドレン配管４６にて連絡される。ドレンタンク
１８は、高圧給水加熱器１６のシエルに接続される。水
位計４４がドレンタンク１８に設けられている。ドレン
配管３９は、ドレンタンク１８と復水器６を連絡してい
る。制御弁４１が、ドレン配管３９に設けられる。ドレ
ンタンク１８と制御弁４１との間のドレン配管３９の部
分に、ドレン配管４０が取付けられる。ドレン配管４０
は、また、低圧給水加熱器１５と給水ポンプ１１との間
の冷却水供給管２１の部分に接続される。制御弁４２、
ポンプ１９及び不純物除去装置４３が、ドレン配管４０
に設けられる。不純物除去装置４３は、高温に耐える必
要があり、例えば電磁フイルタが用いられる。The shell of the high pressure feed water heater 16 and the shell of the high pressure feed water heater 17 are connected by a drain pipe 46. The drain tank 18 is connected to the shell of the high-pressure feed water heater 16. A water level gauge 44 is provided in the drain tank 18. The drain pipe 39 connects the drain tank 18 and the condenser 6. A control valve 41 is provided in the drain pipe 39. A drain pipe 40 is attached to a portion of the drain pipe 39 between the drain tank 18 and the control valve 41. Drain piping 40
Is also connected to the portion of the cooling water supply pipe 21 between the low pressure feed water heater 15 and the feed water pump 11. Control valve 42,
The pump 19 and the impurity removing device 43 are connected to the drain pipe 40.
It is provided in. The impurity removing device 43 needs to withstand high temperatures, and for example, an electromagnetic filter is used.
沸騰水型原子炉の起動時、コントローラ３８及び４５の
作用により制御弁３４及び４２は閉され、制御弁３３及
び４１は開されている。ポンプ３５及び１９は、停止し
ている。このため、低圧給水加熱器１３〜１５に供給さ
れた抽気蒸気は、冷却水を加熱することによつて凝縮さ
れ、ドレン配管２８，２９及び３０を通つて低圧給水加
熱器１２のシエル内に導かれる。抽気管２２及びドレン
配管２８により低圧給水加熱器１２のシエル内に導かれ
た蒸気及びドレンは、低圧給水加熱器１２のドレンとな
つてドレンタンク１８Ａに導かれる。ドレンタンク１８
Ａ内のドレンは、ドレン配管３１により復水器６に排出
される。また、抽気管２７によつて高圧給水加熱器１７
のシエルに供給された蒸気は、ドレンとなつてドレン配
管４６を通して高圧給水加熱器１６のシエル内に導かれ
る。抽気管２６より高圧給水加熱器１６のシエル内に導
かれた抽気された蒸気は、ドレンとなりドレン配管４６
により供給されたドレンとともにドレンタンク１８に排
出される。このドレンタンク１８内のドレンは、ドレン
配管３９を通して復水器６に導かれる。このように沸騰
水型原子炉の起動時にドレンタンク１８及び１８Ａに流
入したドレンは、復水器６に導かれて冷却水（凝縮水）
に混入され、ろ過器８及び復水脱塩器９により浄化され
る。沸騰水型原子炉の起動時においては、抽気蒸気量が
少ないので、各々の給水加熱器のドレンを復水器６に導
入しても支障がない。When the boiling water reactor is started, the control valves 34 and 42 are closed and the control valves 33 and 41 are opened by the action of the controllers 38 and 45. Pumps 35 and 19 are stopped. Therefore, the extracted steam supplied to the low-pressure feed water heaters 13 to 15 is condensed by heating the cooling water, and is introduced into the shell of the low-pressure feed water heater 12 through the drain pipes 28, 29 and 30. Get burned. The steam and drain introduced into the shell of the low-pressure feed water heater 12 through the extraction pipe 22 and the drain pipe 28 are led to the drain tank 18A together with the drain of the low-pressure feed water heater 12. Drain tank 18
The drain in A is discharged to the condenser 6 through the drain pipe 31. Further, the high pressure feed water heater 17 is connected by the extraction pipe 27.
The steam supplied to the shell of the above is connected to the drain and introduced into the shell of the high-pressure feed water heater 16 through the drain pipe 46. The extracted steam introduced into the shell of the high-pressure feed water heater 16 from the extraction pipe 26 becomes a drain and the drain pipe 46.
It is discharged to the drain tank 18 together with the drain supplied by. The drain in the drain tank 18 is guided to the condenser 6 through the drain pipe 39. In this way, the drain that has flowed into the drain tanks 18 and 18A at the time of starting the boiling water reactor is guided to the condenser 6 and cooled water (condensed water).
And is purified by the filter 8 and the condensate demineralizer 9. Since the amount of extracted steam is small at the time of starting the boiling water reactor, there is no problem even if the drain of each feed water heater is introduced into the condenser 6.
沸騰水型原子炉が起動されて原子炉出力が増大するにつ
れて発生する蒸気量が増えしかも原子炉圧力容器１に供
給される冷却水量も増大する。このため、冷却水の加熱
に要する抽気蒸気量も増大し、ドレンタンク１８及び１
８Ａに排出される各給水加熱器のドレン量が増大してド
レンタンク１８及び１８Ａ内のドレン水位が上昇する。
ドレンタンク１８及び１８Ａ内のドレン水位は、水位計
４４及び３７にて計測され、計測値がコントローラ４５
及び３８にそれぞれ伝えられる。ドレンタンク１８Ａ内
のドレン水位が所定レベルに達すると、コントローラ３
８は、制御弁３３を閉にし、制御弁３４を開にするとと
もにポンプ３５を駆動させる。ドレンタンク１８内のド
レン水位が所定レベルに達すると、コントローラ４５
は、制御弁４１を閉にし、制御弁４２を開にするととも
にポンプ１９を駆動させる。As the boiling water reactor is started and the reactor output increases, the amount of steam generated increases and the amount of cooling water supplied to the reactor pressure vessel 1 also increases. For this reason, the amount of extraction steam required to heat the cooling water also increases, and the drain tanks 18 and 1
The drain amount of each feed water heater discharged to 8A increases, and the drain water level in the drain tanks 18 and 18A rises.
The drain water level in the drain tanks 18 and 18A is measured by the water level gauges 44 and 37, and the measured value is the controller 45.
And 38 respectively. When the drain water level in the drain tank 18A reaches a predetermined level, the controller 3
The control valve 8 closes the control valve 33, opens the control valve 34, and drives the pump 35. When the drain water level in the drain tank 18 reaches a predetermined level, the controller 45
Closes the control valve 41, opens the control valve 42, and drives the pump 19.
ポンプ３５が駆動されるとドレンタンク１８Ａ内のドレ
ン水は、ドレン配管３２によつて復水脱塩器９の下流側
で冷却水供給管２１に供給される。その際、ドレン水に
含まれている鉄クラツド等の不純物は、ろ過器３６によ
つて取除かれる。従つて、ドレン配管３２により冷却水
供給管２１に供給されるドレン水は、不純物を含まない
清浄な状態になつている。ポンプ１９が駆動されると、
ドレンタンク１８内のドレン水は、ドレン配管４０によ
つて低圧給水加熱器１５の下流側で冷却水供給管２１に
供給される。ドレン水内に含まれている鉄クラツド等の
不純物は、不純物除去装置４３で除去される。このよう
な状態は、沸騰水型原子炉が所定の原子炉出力（例えば
定格１００％出力）で運転されている期間の間、継続さ
れる。When the pump 35 is driven, the drain water in the drain tank 18A is supplied to the cooling water supply pipe 21 on the downstream side of the condensate demineralizer 9 by the drain pipe 32. At that time, impurities such as iron clad contained in the drain water are removed by the filter 36. Therefore, the drain water supplied to the cooling water supply pipe 21 by the drain pipe 32 is in a clean state containing no impurities. When the pump 19 is driven,
The drain water in the drain tank 18 is supplied to the cooling water supply pipe 21 on the downstream side of the low pressure feed water heater 15 by the drain pipe 40. Impurities such as iron cladding contained in the drain water are removed by the impurity removing device 43. Such a state is continued while the boiling water reactor is operating at a predetermined reactor power (for example, rated 100% power).
沸騰水型原子炉の原子炉出力を低下してその運転を停止
する場合、原子炉出力の低下につれて抽気蒸気量が減少
する。このため、ドレンタンク１８及び１８Ａ内のドレ
ン水位が低下する。それらのドレン水位が、前述の所定
レベルよりも低下すると、コントローラ４５及び３８の
作用によつて制御弁４１及び３３を開にし、ポンプ１９
及び３５を停止させるとともに制御弁４２及び３５を閉
にする。その後、沸騰水型原子炉が停止するまでドレン
タンク１８及び１８Ａ内のドレン水は、ドレン配管３９
及び３１を介して復水器６に排出される。When the reactor output of a boiling water reactor is reduced and its operation is stopped, the amount of extracted steam decreases as the reactor output decreases. For this reason, the drain water level in the drain tanks 18 and 18A is lowered. When their drain water level drops below the aforementioned predetermined level, the control valves 41 and 33 are opened by the action of the controllers 45 and 38, and the pump 19
And 35 are stopped and the control valves 42 and 35 are closed. After that, the drain water in the drain tanks 18 and 18A is drain pipe 39 until the boiling water reactor is stopped.
And 31 to be discharged to the condenser 6.
このような本実施例によれば、以下のような効果が得ら
れる。これらは、電気出力１１０万kWの沸騰水型原子炉
を例にしたものである。According to this embodiment, the following effects can be obtained. These are examples of a boiling water reactor with an electric output of 1.1 million kW.
(1) 原子炉の熱効率の向上 本実施例によれば、高圧給水加熱器１６及び１７で発生
したドレン水（温度約１７０℃、エンタルピ約２００kc
al／kg）から給水（原子炉圧力容器１に導かれる冷却
水）に回収される熱量は、約２２０×１０６kcal／ｈで
あり、低圧給水加熱器１２〜１５で発生するドレン水
（温度約８５℃、エンタルピ約８５kcal／kg）から給水
に回収される熱量は約１４０×１０６kcal／ｈである。
従つて、沸騰水型原子炉の熱効率が向上する。(1) Improvement of thermal efficiency of nuclear reactor According to this embodiment, drain water generated in the high-pressure feed water heaters 16 and 17 (temperature about 170 ° C., enthalpy about 200 kc
The amount of heat recovered from the feed water (cooling water guided to the reactor pressure vessel 1) is approximately 220 × 10 6 kcal / h, and the drain water (temperature The amount of heat recovered from the water supply from about 85 ° C. and enthalpy of about 85 kcal / kg) is about 140 × 10 6 kcal / h.
Therefore, the thermal efficiency of the boiling water reactor is improved.
(2) 沸騰水型原子炉プラントの表面線量率の低下 従来の冷却水供給装置に比べて低圧及び高圧給水加熱器
のドレン水により冷却水供給管２１内に持込まれる鉄ク
ラツドが減少する。このため、原子炉圧力容器１内に導
入される鉄クラツド量が低減され、再循環系配管等の原
子炉圧力容器１に接続される配管の表面線量率が低下す
る。従つて、配管等の保守点検作業が容易に実施できる
ようになる。(2) Reduction of surface dose rate of boiling water reactor plant Compared with the conventional cooling water supply device, the drain water of the low-pressure and high-pressure feed water heaters reduces the iron cladding brought into the cooling water supply pipe 21. Therefore, the amount of iron cladding introduced into the reactor pressure vessel 1 is reduced, and the surface dose rate of the piping connected to the reactor pressure vessel 1 such as the recirculation system piping is reduced. Therefore, it becomes possible to easily carry out maintenance and inspection work on the piping and the like.
(3) 復水浄化設備の小型化 給水加熱器のドレン水が多量に発生する原子炉の通常運
転時に、ドレン水を復水器６ではなく復水脱塩器９より
下流側で冷却水供給管２１内に導いているので、ろ過器
８及び復水脱塩器９を通過する処理水の量が従来よりも
少なくなる。従つてろ過器８及び復水脱塩器９の処理容
量を低減できるので、これらの復水浄化設備を小型化で
きる。(3) Miniaturization of condensate purification equipment During normal operation of the reactor where a large amount of drain water is generated in the feed water heater, the drain water is supplied not to the condenser 6 but to the downstream side of the condensate demineralizer 9 Since the water is introduced into the pipe 21, the amount of treated water passing through the filter 8 and the condensate demineralizer 9 becomes smaller than in the conventional case. Therefore, since the processing capacities of the filter 8 and the condensate demineralizer 9 can be reduced, these condensate purification facilities can be downsized.
(4) 低圧給水加熱器の小型化 高圧給水加熱器１６及び１７のドレン水を低圧給水加熱
器１５の下流側に供給しているので、低圧給水加熱器を
通過する冷却水量が少なくなる。このため、低圧給水加
熱器を小型化できる。(4) Miniaturization of low-pressure feed water heater Since the drain water of the high-pressure feed water heaters 16 and 17 is supplied to the downstream side of the low-pressure feed water heater 15, the amount of cooling water passing through the low-pressure feed water heater decreases. Therefore, the low-pressure feed water heater can be downsized.
(5) ドレン水排出系の小型化 高圧給水加熱器１６及び１７のドレン水を原子炉の運転
状態、すなわちドレン水の発生量の増減に応じてドレン
水を排出する配管を切替えているので、ドレン水の発生
量に対応してドレン水を容易に排出できる。ポンプ１９
はドレン水の発生量の多い状態に基づいて仕様を設定で
きるので、ポンプ１９の運転領域を狭くすることがで
き、ポンプ１９にかかる負担が軽減される。これによ
り、ポンプ１９を小型化できる。このことは、低圧給水
加熱器１２〜１５のドレン水を排出する系統に対しても
同じことが言える。(5) Miniaturization of drain water discharge system Since the drain water of the high-pressure feed water heaters 16 and 17 is switched in accordance with the operating state of the reactor, that is, the drain water discharge pipe is changed according to the increase / decrease in the generated amount of drain water, Drain water can be easily discharged according to the amount of drain water generated. Pump 19
Since the specifications can be set based on the state in which the amount of drain water generated is large, the operating region of the pump 19 can be narrowed and the load on the pump 19 is reduced. Thereby, the pump 19 can be downsized. The same can be said for the system for discharging the drain water of the low-pressure feed water heaters 12 to 15.
本発明によれば、原子炉の熱効率を向上できるとともに
原子炉圧力容器内への放射化される物質の持込み量を低
減できる。According to the present invention, it is possible to improve the thermal efficiency of the nuclear reactor and reduce the carry-in amount of the substance to be activated into the nuclear reactor pressure vessel.
第１図は本発明の好適な一実施例の系統図、第２図は従
来装置の系統図である。 １…原子炉圧力容器、２…高圧タービン、４…低圧ター
ビン、６…復水器、１１…給水ポンプ、１２〜１５…低
圧給水加熱器、１６，１７…高圧給水加熱器、１８，１
８Ａ…ドレンタンク、２１…冷却水供給管、３１，３
２，３９，４０…ドレン配管、３３，３４，４１，４２
…制御弁、３６…ろ過器、４３…不純物除去装置。FIG. 1 is a system diagram of a preferred embodiment of the present invention, and FIG. 2 is a system diagram of a conventional device. DESCRIPTION OF SYMBOLS 1 ... Reactor pressure vessel, 2 ... High pressure turbine, 4 ... Low pressure turbine, 6 ... Condenser, 11 ... Water supply pump, 12-15 ... Low pressure feed water heater, 16, 17 ... High pressure feed water heater, 18, 1
8A ... Drain tank, 21 ... Cooling water supply pipe, 31, 3
2, 39, 40 ... Drain piping, 33, 34, 41, 42
... Control valve, 36 ... Filter, 43 ... Impurity removing device.
Claims (1)
水ポンプと、低圧給水加熱器と、復水器と、前記原子炉
圧力容器、前記高圧給水加熱器、前記給水ポンプ、前記
低圧給水加熱器及び前記復水器をこの順序で連絡する冷
却水供給管と、前記高圧給水加熱器から吐出されるドレ
ン水を前記給水ポンプと前記低圧給水加熱器との間の前
記冷却水供給管の部分に導くドレン配管とからなる沸騰
水型原子炉の冷却水供給装置において、不純物除去手段
を前記ドレン配管に設けたことを特徴とする沸騰水型原
子炉の冷却水供給装置。1. A reactor pressure vessel, a high pressure feed water heater, a feed water pump, a low pressure feed water heater, a condenser, the reactor pressure vessel, the high pressure feed water heater, the feed water pump, and the low pressure. A cooling water supply pipe that connects the water supply heater and the condenser in this order, and drain water discharged from the high pressure water supply heater between the water supply pump and the low pressure water supply heater. A cooling water supply apparatus for a boiling water nuclear reactor, comprising: a drain pipe leading to the portion of FIG. 3, wherein an impurity removing means is provided in the drain pipe.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59227257A JPH068905B2 (en) | 1984-10-29 | 1984-10-29 | Cooling water supply system for boiling water reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59227257A JPH068905B2 (en) | 1984-10-29 | 1984-10-29 | Cooling water supply system for boiling water reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS61105495A JPS61105495A (en) | 1986-05-23 |
| JPH068905B2 true JPH068905B2 (en) | 1994-02-02 |
Family
ID=16857984
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP59227257A Expired - Lifetime JPH068905B2 (en) | 1984-10-29 | 1984-10-29 | Cooling water supply system for boiling water reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH068905B2 (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP4625484B2 (en) * | 2007-06-29 | 2011-02-02 | 株式会社日立製作所 | Nuclear power plant |
-
1984
- 1984-10-29 JP JP59227257A patent/JPH068905B2/en not_active Expired - Lifetime
Also Published As
| Publication number | Publication date |
|---|---|
| JPS61105495A (en) | 1986-05-23 |
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