JPS6168596A - Feedwater heater for nuclear reactor - Google Patents
Feedwater heater for nuclear reactorInfo
- Publication number
- JPS6168596A JPS6168596A JP59190363A JP19036384A JPS6168596A JP S6168596 A JPS6168596 A JP S6168596A JP 59190363 A JP59190363 A JP 59190363A JP 19036384 A JP19036384 A JP 19036384A JP S6168596 A JPS6168596 A JP S6168596A
- Authority
- JP
- Japan
- Prior art keywords
- turbine
- steam
- main steam
- pipe
- 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.)
- Pending
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
Landscapes
- Absorbent Articles And Supports Therefor (AREA)
- Discharge Heating (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〕 本発明は原子炉給水加熱装置に係る。[Detailed description of the invention] [Technical field of invention] The present invention relates to a nuclear reactor feedwater heating device.
原子力発電プラントにおいては、原子炉で発生した蒸気
またはこの蒸気により水を加熱して発生させた蒸気をタ
ービンに送り、発電機を駆動して電力を発生させている
。タービンを通った蒸気は、復水器により復水とされ給
水加熱器、給水ポンプ等を経て原子炉または蒸気発生器
に戻される。In a nuclear power plant, steam generated in a nuclear reactor or steam generated by heating water with this steam is sent to a turbine to drive a generator to generate electricity. The steam that has passed through the turbine is converted into condensate by a condenser, and is returned to the nuclear reactor or steam generator via a feed water heater, a feed water pump, etc.
この復給水をタービンからの抽気蒸気により給水加熱器
で加熱昇温して高温水とすることによって、プラントの
熱効率の向上をはかっている。The thermal efficiency of the plant is improved by heating this return water with steam extracted from the turbine in a feed water heater to create high-temperature water.
ところでタービンの制御は電気式油圧制御装置（Ｅ Ｈ
Ｃ）によって行われている。この装置は主蒸気圧力を一
定に保つようにタービン蒸気加減弁およびタービンバイ
パス弁の開度を調節する。By the way, the turbine is controlled by an electro-hydraulic control device (EH
C). This device adjusts the openings of the turbine steam control valve and turbine bypass valve to keep the main steam pressure constant.
例えば、タービンの速度が上昇した場合には、Ｅｌ−Ｉ
Ｃの働きによりタービン蒸気加減弁を閉じてタービン
への蒸気を絞ると共に、タービンバイパス弁を開いて過
剰の蒸気を復水器にバイパスする。For example, if the turbine speed increases, El-I
C closes the turbine steam control valve to throttle the steam to the turbine, and opens the turbine bypass valve to bypass excess steam to the condenser.
タービンバイパス容量が１００％に満たないプラントで
は、プラントの異常によってタービン蒸気加減弁が全閉
した場合には、タービンバイパス弁が全開しても主蒸気
の逃げ場がなく、主蒸気圧力が上昇する。そのため原子
炉圧力高または中性子束高のインタロック（論理回路）
が働き、原子炉スクラムに至る。In a plant where the turbine bypass capacity is less than 100%, if the turbine steam control valve is fully closed due to an abnormality in the plant, there is no place for the main steam to escape even if the turbine bypass valve is fully opened, and the main steam pressure increases. Therefore, an interlock (logic circuit) for high reactor pressure or high neutron flux
works, leading to a reactor scram.
これに対しタービンバイパス容量１００％のプラントで
は、タービン蒸気加減弁が全閉してもタービンバイパス
弁が前回すれば、主蒸気全量を復水器にバイパスさせる
ことができるので、前記の原子炉圧力高または中性子束
高による原子炉スクラムを生じることはなく、そのター
ビンの所内単独運転に移行することができる、。On the other hand, in a plant with 100% turbine bypass capacity, even if the turbine steam control valve is fully closed, if the turbine bypass valve closes last time, the entire amount of main steam can be bypassed to the condenser. There will be no reactor scram due to high or high neutron flux, and the turbine can be transitioned to in-station islanding.
しかし乍ら、タービン蒸気加減弁が全閉されているため
、給水加熱器への抽気蒸気は遮断されてしまい、その結
果原子炉への給水温度が低下し、炉心入口サブクールが
増加し原子炉に正の反応度が印加されることとなり、中
性子束の上昇を１Ｇき、結局原子炉スクラムに至るおそ
れがある。However, since the turbine steam control valve is fully closed, the bleed steam to the feedwater heater is cut off, resulting in a drop in the temperature of the feedwater to the reactor, an increase in the core inlet subcooling, and A positive reactivity will be applied, which will increase the neutron flux by 1G, which may eventually lead to a reactor scram.
プラントの稼１１］率、信頼性を向上させるには不要な
原子炉スクラムをできるだけ避けることが必要である。In order to improve plant operating efficiency and reliability, it is necessary to avoid unnecessary reactor scrams as much as possible.
また、上記のように正の反応度が印加されることは燃料
の健全性の面からも好ましくない。Further, it is not preferable to apply a positive reactivity as described above from the viewpoint of the health of the fuel.
本発明は上記の事情に基きなされてものであってタービ
ンバイパス容ｆｉ１００％の原子ノコプラントにおいて
プラントの異常によるタービン蒸気加減弁全閉じる時に
も給水の加熱を行なうことができる原子炉給水加熱装置
を１ｑることを目的とする。The present invention has been made based on the above-mentioned circumstances, and provides a reactor feed water heating device that can heat the feed water even when the turbine steam control valve is fully closed due to plant abnormality in an atomic saw plant with a turbine bypass capacity of 100%. The purpose is to do 1q.
本発明の原子炉給水加熱装置は、主蒸気管の主蒸気止弁
上流に主蒸気ヘッダを設け、この主蒸気ヘッダと、給水
加熱器にタービンから抽出した蒸気を供給する抽気管と
を、配管内にプラント異常時に全開で気る抽気弁及び主
蒸気を減圧するための減圧オリフィスを有しタービンを
介さず直接主蒸気を抽気蒸気どして給水加熱器に供給で
きることを特徴どする。In the reactor feedwater heating device of the present invention, a main steam header is provided upstream of the main steam stop valve in the main steam pipe, and the main steam header and the bleed pipe that supplies steam extracted from the turbine to the feedwater heater are connected to the piping. It is characterized by having a bleed valve that is fully open in the event of a plant abnormality and a depressurizing orifice for reducing the pressure of the main steam, so that the main steam can be directly bleed and supplied to the feed water heater without going through a turbine.
本発明の一実施例を図面を参照して説明する。 An embodiment of the present invention will be described with reference to the drawings.
図面は本発明をタービンバイパス容量１００％の′ｇ８
１１！！木型原子炉（ＢＷＲ）に適用した実施例を示す
。ＢＷＲｌで発生した蒸気は主蒸気管２、主蒸気ヘッダ
３、主蒸気止弁４、タービン蒸気加減弁５を経て高圧タ
ービン６に送られ、高圧タービン６で仕事をした蒸気は
湿分分離器７、組合せインタセプト弁８を経て低圧ター
ビン９に入り、ここで仕事をした後、復水器１０で復水
となる。復水は復水ポンプ１１により低圧給水型加熱器
１２〜１５に送られ、ここで加熱昇温され原子炉給水ポ
ンプ１６．１７によって加圧されて高圧給水加熱器１８
．１つに送られ、ここでさらに加熱昇温されてＢＷＲ１
に給水される。The drawing shows the present invention at 100% turbine bypass capacity'g8
11! ! An example applied to a wooden nuclear reactor (BWR) will be shown. The steam generated in the BWRl is sent to the high pressure turbine 6 via the main steam pipe 2, main steam header 3, main steam stop valve 4, and turbine steam control valve 5, and the steam that has done work in the high pressure turbine 6 is sent to the moisture separator 7. , enters the low-pressure turbine 9 via the combination intercept valve 8, and after doing work there becomes condensate in the condenser 10. The condensate is sent to low-pressure feed water heaters 12 to 15 by a condensate pump 11, heated and heated there, and pressurized by reactor feed water pumps 16 and 17 to a high-pressure feed water heater 18.
．． BWR1, where it is further heated and heated to BWR1.
is supplied with water.
またタービン蒸気加減弁５が閉じて過剰な蒸気が発生し
た場合には主蒸気圧力を一定に保つためＥＨＣの働きに
よりタービンバイパス弁３２が開いて過剰蒸気をタービ
ンバイパス管３１を経て復水器１０にバイパスする。Furthermore, when the turbine steam control valve 5 is closed and excess steam is generated, the EHC operates to open the turbine bypass valve 32 to keep the main steam pressure constant, and the excess steam is passed through the turbine bypass pipe 31 to the condenser 10. Bypass to.
なお、低圧給水加熱器１２〜１５には低圧タービン９か
ら蒸気を抽出する第１の抽気管２０により、また高圧給
水加熱器１８．１９には高圧タービン６から蒸気を抽出
する第２の抽気管２１によりそれぞれ加熱用の蒸気が供
給されている。而して各油気管２０，２１には主蒸気へ
ラダ３から分岐し、中間部に抽気弁２２をそなえた第３
の抽気管２３がそれぞれ接続されている。なお第３の抽
気管２３の第１の抽気管２０に連なる分岐管内には減圧
オリフィス２４が設けである。Note that the low-pressure feedwater heaters 12 to 15 are connected to a first bleed pipe 20 for extracting steam from the low-pressure turbine 9, and the high-pressure feedwater heaters 18 and 19 are connected to a second bleed pipe for extracting steam from the high-pressure turbine 6. Steam for heating is supplied by 21, respectively. Each oil air pipe 20, 21 has a third pipe branched from the rudder 3 to the main steam and equipped with a bleed valve 22 in the middle.
bleed pipes 23 are connected to each. Note that a decompression orifice 24 is provided in a branch pipe of the third air bleed pipe 23 that is connected to the first air bleed pipe 20.
またＥ ｌ−Ｉ Ｃには、タービン蒸気加減弁５の全期
時に抽気弁２２を全開させる機能を持たせておく。Further, the E l-I C is provided with a function of fully opening the bleed valve 22 when the turbine steam control valve 5 is in full operation.
また、減圧オリフィス２４は、復水器１０を出た直後で
圧力が低い復水を加熱するのに適当な圧力まで主蒸気を
減圧するものである。Further, the pressure reduction orifice 24 reduces the pressure of the main steam to a pressure suitable for heating the condensate, which has a low pressure immediately after leaving the condenser 10.
図中、２５は給水管、２６は給水加熱器ドレン管、２７
は復水管、２８．２９はドレン冷却器、３０はフラッシ
ュタンク、３１はバイパス管、３２はバイパス弁、３３
は発電機をそれぞれ示している。In the figure, 25 is a water supply pipe, 26 is a water heater drain pipe, 27
is a condensate pipe, 28.29 is a drain cooler, 30 is a flash tank, 31 is a bypass pipe, 32 is a bypass valve, 33
indicate the respective generators.
上記構成の本発明装置においては、プラントに異常が発
生して蒸気加減弁５が全閉されると同時に抽気弁２２が
全問され、高圧給水加熱器１８．１９には主蒸気がその
まま、また低圧給水加熱器１２〜１５には減圧された主
蒸気が供給される。In the apparatus of the present invention having the above configuration, when an abnormality occurs in the plant and the steam control valve 5 is fully closed, all the bleed valves 22 are closed, and the main steam is supplied to the high pressure feed water heaters 18 and 19 as is. Depressurized main steam is supplied to the low pressure feed water heaters 12 to 15.
従って、各給水加熱器はその機能を失うことはなく、Ｂ
ＷＲに供給される給水の温度が低下することはない。そ
のため、炉心入口サブクールの増加はなく、それに基ず
く正の反応度の印加もない。Therefore, each feed water heater does not lose its functionality and B
The temperature of the water supplied to the WR does not drop. Therefore, there is no increase in the core inlet subcool, and no positive reactivity is applied based on it.
以上説明したように、本実施例によればプラントの異常
によりタービン蒸気加減弁が全閉した場合でも、給水加
熱器の機能を喪失することなく、不要な原子炉スクラム
を回避することができる。As described above, according to this embodiment, even if the turbine steam control valve is fully closed due to an abnormality in the plant, unnecessary reactor scram can be avoided without losing the function of the feed water heater.
本発明によればプラントの異常により給水加昇温した給
水を原子炉に供給することができる。According to the present invention, feed water whose temperature has been increased due to an abnormality in a plant can be supplied to a nuclear reactor.
従って正の反応度の印加による中性子束の増大から原子
炉スクラムに至ることはなく、不要な原子炉スクラムを
回避することができる。このことは、プラントの稼働率
を向上させるのみでなく、燃料健全性の点からも有利で
ある。Therefore, an increase in neutron flux due to the application of positive reactivity does not lead to reactor scram, and unnecessary reactor scram can be avoided. This not only improves plant availability but is also advantageous in terms of fuel integrity.
図は本発明一実施例の模式図である。
１・・・ＢＷＲ２・・・主蒸気管 ３・・・主蒸気ヘッ
ダ ４・・・主蒸気止め弁 ５・・・タービン蒸気加減
弁 ６・・・高圧タービン ７・・・湿分分離器８・・
・組合はインタレブト弁 ９・・・低圧タービン １０
・・・復水器 １１・・・復水ポンプ １２〜１５低圧
給水加熱器 １６・・・タービン駆動原子炉給水ポンプ
１７・・・電動機駆動原子炉給水ポンプ １８．１９
・・・高圧給水加熱器２０．２１．２３・・・抽気管
２２・・・抽気弁２４・・・減圧オリフィス ２５・・
・給水管 ２６・・・給水加熱器ドレン管 ２７・・・
復水管 ２８．２９・・・ドレン冷却器 ３０・・・フ
ラッシュタンク ３１・・・タービンバイパス管 ３２
・・・タービンバイパス弁 ３３・・・発電機
出願代理人The figure is a schematic diagram of one embodiment of the present invention. 1...BWR2...Main steam pipe 3...Main steam header 4...Main steam stop valve 5...Turbine steam control valve 6...High pressure turbine 7...Moisture separator 8.・
・Union is interlebut valve 9...Low pressure turbine 10
... Condenser 11 ... Condensate pump 12 - 15 Low-pressure feed water heater 16 ... Turbine-driven reactor feed water pump 17 ... Electric motor-driven reactor feed water pump 18.19
...High pressure feed water heater 20.21.23...Bleed pipe
22...Bleed valve 24...Reducing pressure orifice 25...
・Water supply pipe 26... Water supply heater drain pipe 27...
Condensate pipe 28.29...Drain cooler 30...Flash tank 31...Turbine bypass pipe 32
... Turbine bypass valve 33 ... Generator application agent
Claims (1)
主蒸気ヘッダと、給水加熱器にタービンから抽出した蒸
気を供給する抽気管とを、配管内にプラント異常時に全
開で気る抽気弁及び主蒸気を減圧するための減圧オリフ
ィスを有しタービンを介さず直接主蒸気を抽気蒸気とし
て給水加熱器に供給できることを特徴とする原子炉給水
加熱装置。A main steam header is installed upstream of the main steam stop valve in the main steam pipe, and this main steam header and a bleed pipe that supplies steam extracted from the turbine to the feedwater heater are connected to the main steam pipe so that the bleed air can be fully opened in the event of a plant abnormality. 1. A nuclear reactor feedwater heating device characterized by having a valve and a pressure reducing orifice for reducing the pressure of main steam, and being able to directly supply main steam as extracted steam to a feedwater heater without going through a turbine.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59190363A JPS6168596A (en) | 1984-09-11 | 1984-09-11 | Feedwater heater for nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59190363A JPS6168596A (en) | 1984-09-11 | 1984-09-11 | Feedwater heater for nuclear reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS6168596A true JPS6168596A (en) | 1986-04-08 |
Family
ID=16256936
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP59190363A Pending JPS6168596A (en) | 1984-09-11 | 1984-09-11 | Feedwater heater for nuclear reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6168596A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2009020110A (en) * | 2007-07-13 | 2009-01-29 | Ge-Hitachi Nuclear Energy Americas Llc | Method and system for controlling feed water temperature |
-
1984
- 1984-09-11 JP JP59190363A patent/JPS6168596A/en active Pending
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2009020110A (en) * | 2007-07-13 | 2009-01-29 | Ge-Hitachi Nuclear Energy Americas Llc | Method and system for controlling feed water temperature |
| US8705682B2 (en) | 2007-07-13 | 2014-04-22 | Ge-Hitachi Nuclear Energy Americas Llc | Feedwater temperature control methods and systems |
| US10163532B2 (en) | 2007-07-13 | 2018-12-25 | Ge-Hitachi Nuclear Energy Americas Llc | Feedwater temperature control methods and systems |
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