JPS6217084B2 - - Google Patents
Info
- Publication number
- JPS6217084B2 JPS6217084B2 JP9095282A JP9095282A JPS6217084B2 JP S6217084 B2 JPS6217084 B2 JP S6217084B2 JP 9095282 A JP9095282 A JP 9095282A JP 9095282 A JP9095282 A JP 9095282A JP S6217084 B2 JPS6217084 B2 JP S6217084B2
- Authority
- JP
- Japan
- Prior art keywords
- steam
- turbine
- bypass valve
- valve
- 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
Links
- 230000003628 erosive effect Effects 0.000 claims description 9
- 238000005536 corrosion prevention Methods 0.000 claims description 8
- 230000002265 prevention Effects 0.000 claims description 7
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 8
- 238000010586 diagram Methods 0.000 description 4
- 230000000694 effects Effects 0.000 description 2
- 229920006395 saturated elastomer Polymers 0.000 description 2
- 238000007789 sealing Methods 0.000 description 2
- 238000009835 boiling Methods 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000011084 recovery Methods 0.000 description 1
Classifications
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
- F01D—NON-POSITIVE DISPLACEMENT MACHINES OR ENGINES, e.g. STEAM TURBINES
- F01D25/00—Component parts, details, or accessories, not provided for in, or of interest apart from, other groups
- F01D25/007—Preventing corrosion
Landscapes
- Engineering & Computer Science (AREA)
- Mechanical Engineering (AREA)
- General Engineering & Computer Science (AREA)
- Control Of Turbines (AREA)
Description
【発明の詳細な説明】
〔発明の技術分野〕
本発明は、タービンプラントのタービンバイパ
ス系統のタービンバイパス弁浸蝕防止装置に係
り、特に湿り蒸気の逆流による前記バイパス弁弁
棒の浸蝕を防止するタービンバイパス弁浸蝕防止
装置に関する。DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to a turbine bypass valve erosion prevention device for a turbine bypass system of a turbine plant, and particularly to a turbine bypass valve corrosion prevention device for preventing erosion of the bypass valve valve stem due to backflow of wet steam. This invention relates to a bypass valve erosion prevention device.
従来のタービンバイパス弁浸蝕防止装置として
特公昭56−13161号に示すものがあるが、このも
のを原子力タービンプラントに適用したものを第
1図により説明する。
As a conventional turbine bypass valve corrosion prevention device, there is one shown in Japanese Patent Publication No. 13161/1983, and an application of this device to a nuclear power turbine plant will be explained with reference to FIG.
第1図は従来のタービンバイパス弁浸蝕防止装
置を示す系統図であり、原子炉1と、前記原子炉
1で発生した蒸気を高圧タービン2へ送る主蒸気
管3と、前記主蒸気管3の途中に設けた主蒸気止
め弁4および主蒸気加減弁5と、前記高圧タービ
ン2で仕事をした蒸気を低圧タービン6へ送る高
圧排気管7と、前記高圧排気管7の途中に設けた
湿分分離器8および中間蒸気止め弁9と、タービ
ン軸に結合された発電機10と、前記低圧タービ
ン6で仕事をした蒸気を復水にする復水器11
と、前記復水を給水ポンプ12により原子炉1へ
供給する給水管13と、主蒸気管3から分岐して
バイパス弁14へ主蒸気を送るバイパス入口管1
5と、タービンバイパス弁14を通つた蒸気を復
水器11へ送るバイパス出口管16と、バイパス
弁弁棒17と、前記弁棒17から外部へ蒸気が漏
れるのを防止するため、前記弁棒17から高圧排
気管7に向つて開く逆止弁18を備えた第1リー
ク回路19と、復水器11に接続された第2リー
ク回路20と、蒸気発生器21に接続された第3
リーク回路22とを備えている。 FIG. 1 is a system diagram showing a conventional turbine bypass valve corrosion prevention device, which includes a nuclear reactor 1, a main steam pipe 3 that sends steam generated in the reactor 1 to a high-pressure turbine 2, and A main steam stop valve 4 and a main steam control valve 5 provided in the middle, a high pressure exhaust pipe 7 that sends the steam that has worked in the high pressure turbine 2 to the low pressure turbine 6, and a moisture control valve provided in the middle of the high pressure exhaust pipe 7. A separator 8, an intermediate steam stop valve 9, a generator 10 coupled to the turbine shaft, and a condenser 11 that condenses the steam that has done work in the low-pressure turbine 6.
, a water supply pipe 13 that supplies the condensate to the reactor 1 by a water supply pump 12, and a bypass inlet pipe 1 that branches from the main steam pipe 3 and sends main steam to a bypass valve 14.
5, a bypass outlet pipe 16 for sending the steam that has passed through the turbine bypass valve 14 to the condenser 11, a bypass valve valve stem 17, and a bypass valve stem 17 for preventing steam from leaking from the valve stem 17 to the outside. a first leak circuit 19 equipped with a check valve 18 that opens from 17 toward the high-pressure exhaust pipe 7; a second leak circuit 20 connected to the condenser 11; and a third leak circuit 20 connected to the steam generator 21.
A leak circuit 22 is provided.
タービンの正常運転中は前記バイパス弁14は
閉じられていて前記原子炉1で発生したわずかに
湿つた飽和蒸気は主蒸気管3から高圧タービン2
に流入する蒸気を遮断するために設けられた主蒸
気止め弁4と、高圧タービン2に流入する蒸気量
を加減するために設けられた主蒸気加減弁5を通
つて高圧タービン2に流入する。高圧タービン2
で仕事をした蒸気は、高圧排気管7を通り湿分分
離器8に入つて湿分を除去されてから、中間蒸気
止め弁9を通つて低圧タービン6に流入する。低
圧タービン6で仕事をした蒸気は、復水器11に
入り復水となつて、給水ポンプ12により給水管
13を通つて原子炉1に供給される。 During normal operation of the turbine, the bypass valve 14 is closed and the slightly moist saturated steam generated in the reactor 1 is passed from the main steam pipe 3 to the high pressure turbine 2.
Steam flows into the high-pressure turbine 2 through a main steam stop valve 4 provided to shut off steam flowing into the high-pressure turbine 2 and a main steam control valve 5 provided to adjust the amount of steam flowing into the high-pressure turbine 2 . High pressure turbine 2
The steam that has done work passes through the high-pressure exhaust pipe 7 and enters the moisture separator 8 to remove moisture, and then flows into the low-pressure turbine 6 through the intermediate steam stop valve 9. The steam that has done work in the low-pressure turbine 6 enters the condenser 11 and becomes condensed water, which is then supplied to the nuclear reactor 1 through the water supply pipe 13 by the water supply pump 12.
なお、タービンバイパス弁14を開く必要が生
じるのは次の2つの場合である。 Note that the turbine bypass valve 14 needs to be opened in the following two cases.
まず、第1の場合は、原子炉1を起動するとき
である。原子炉1で発生した蒸気を逃がす系統が
ないと原子炉1を起動することができない。この
ため、原子炉1を起動し高圧タービン2および低
圧タービン6に蒸気を送り込むまでの間はタービ
ンバイパス弁14を開けて原子炉1で発生した蒸
気を復水器11へ逃がす。そして主蒸気加減弁5
を開けるに従つてバイパス弁14は閉じられるよ
うにしている。 First, the first case is when the nuclear reactor 1 is started. The reactor 1 cannot be started unless there is a system to release the steam generated in the reactor 1. For this reason, the turbine bypass valve 14 is opened until the reactor 1 is started and steam is sent to the high-pressure turbine 2 and low-pressure turbine 6, and the steam generated in the reactor 1 is released to the condenser 11. and main steam control valve 5
As the bypass valve 14 is opened, the bypass valve 14 is closed.
第2の場合は、タービンの正常運転中に主蒸気
止め弁4または、主蒸気加減弁5が急に閉つたと
きである。特に沸騰水形原子炉では、その性質上
原子炉1で発生した蒸気の圧力を一定に抑える必
要があるが、正常運転中のタービンバイパス弁1
4が閉つている状態で主蒸気止め弁4または、主
蒸気加減弁5が急に閉じると原子炉1で発生する
蒸気圧力が急上昇するのでタービンバイパス弁1
4を開いて圧力上昇を抑えるようにしている。 The second case is when the main steam stop valve 4 or the main steam control valve 5 suddenly closes during normal operation of the turbine. In particular, in a boiling water reactor, it is necessary to keep the pressure of steam generated in the reactor 1 constant due to its nature, but during normal operation the turbine bypass valve 1
If the main steam stop valve 4 or the main steam control valve 5 suddenly closes while the turbine bypass valve 4 is closed, the steam pressure generated in the reactor 1 will rise rapidly.
4 is opened to suppress the pressure rise.
次に、前記2つの場合のタービンバイパス弁1
4が開いたとき、前記弁棒17の囲りに入り込ん
だ高圧の蒸気は、逆止弁20を開き第1リーク回
路19を通つて少し圧力の低い高圧排気管7にリ
ークする。さらにリークする蒸気は、第2リーク
回路20を通つて復水器11にリークする。 Next, the turbine bypass valve 1 in the above two cases
4 opens, the high-pressure steam that has entered around the valve stem 17 opens the check valve 20 and leaks through the first leak circuit 19 to the high-pressure exhaust pipe 7 whose pressure is slightly lower. Further leaking steam leaks to the condenser 11 through the second leak circuit 20.
また、第3リーク回路22には、蒸気発生器2
1で発生させた復水器11より少し圧力が高く大
気圧より圧力が低い放射能に汚染されていない蒸
気を供給する。この蒸気は第2リーク回路20を
通つて復水器11にリークし、放射能に汚染され
た内部の蒸気が外部に漏れないように完全にシー
ルするようにしている。そしてタービンの正常運
転中タービンバイパス弁14が閉つているとき、
第1リーク回路19には逆止弁18を備えている
ので、高圧排気管7から第1リーク回路19を通
つてタービンバイパス弁14側に蒸気が逆流する
こともない。 Further, the third leak circuit 22 includes a steam generator 2
To supply steam that is not contaminated with radioactivity and has a pressure slightly higher than that of the condenser 11 generated in step 1 and lower than atmospheric pressure. This steam leaks to the condenser 11 through the second leak circuit 20, and is completely sealed to prevent radioactively contaminated steam from leaking to the outside. When the turbine bypass valve 14 is closed during normal operation of the turbine,
Since the first leak circuit 19 is provided with the check valve 18, steam does not flow back from the high-pressure exhaust pipe 7 through the first leak circuit 19 to the turbine bypass valve 14 side.
しかしながら、前記の従来のタービンバイパス
弁浸蝕防止装置は、前記逆止弁18が正常運転中
は閉つているから、長時間にわたり滞留した蒸気
がドレン化する。そのため、前記逆止弁18のス
テイツクを生じ、第1リーク回路19がふさがつ
てリーク回路が十分確保されなくなり、第2リー
ク回路20および第3リーク回路22の圧力のバ
ランスが破られて放射能に汚染された蒸気が漏れ
る欠点があつた。
However, in the conventional turbine bypass valve erosion prevention device described above, since the check valve 18 is closed during normal operation, steam that remains for a long time becomes a drain. As a result, the check valve 18 becomes stuck, the first leak circuit 19 is blocked, and the leak circuit is not sufficiently secured, and the pressure balance in the second leak circuit 20 and the third leak circuit 22 is broken, resulting in radioactivity. The drawback was that contaminated steam leaked out.
本発明は、前述した従来のものにおける欠点を
除去し、タービンバイパス系統にオリフイスが付
設されているリーク回路を備えたことによつて、
タービンバイパス弁弁棒の浸蝕を防止し、さら
に、内部の蒸気を完全にシールするタービンバイ
パス弁浸蝕防止装置を提供することを目的とす
る。
The present invention eliminates the drawbacks of the conventional system described above, and by providing a leak circuit with an orifice attached to the turbine bypass system,
It is an object of the present invention to provide a turbine bypass valve corrosion prevention device that prevents corrosion of a turbine bypass valve valve stem and also completely seals internal steam.
前述した目的は、本発明によれば、タービンプ
ラントのタービンバイパス系統のタービンバイパ
ス弁弁棒から漏洩蒸気を復水器へ導くためのリー
ク回路を有するタービンバイパス弁浸蝕防止装置
において、前記リーク回路にオリフイスが付設さ
れているリーク回路を備えて、正常運転中のター
ビンバイパス弁全閉状態においても蒸気がバイパ
ス弁に逆流しないようにしたことによつて達成さ
れる。
According to the present invention, the above-mentioned object is a turbine bypass valve corrosion prevention device having a leak circuit for guiding leaked steam from a turbine bypass valve valve stem of a turbine bypass system of a turbine plant to a condenser. This is achieved by providing a leak circuit with an orifice to prevent steam from flowing back into the bypass valve even when the turbine bypass valve is fully closed during normal operation.
以下、本発明を図面に示す実施例により説明す
る。なお、前述した従来のものと同一の構成につ
いては、図面中に同一の符号を付し、その説明は
省略する。
The present invention will be explained below with reference to embodiments shown in the drawings. Note that the same components as those of the conventional device described above are denoted by the same reference numerals in the drawings, and the explanation thereof will be omitted.
第2図は本発明のタービンバイパス弁浸蝕防止
装置の一実施例を原子力タービンプラントに適用
した状態を示す系統図であり、オリフイス23が
付設され弁棒17の周りから復水器11に接続さ
れた第1リーク回路19を備えている。 FIG. 2 is a system diagram showing a state in which an embodiment of the turbine bypass valve erosion prevention device of the present invention is applied to a nuclear power turbine plant. A first leak circuit 19 is provided.
したがつて、タービンの正常運転中の前記バイ
パス弁14が閉じられているときに、前記湿つた
飽和蒸気がタービンバイパス弁14に逆流するこ
とはない。そのためバイパス弁弁棒17の浸蝕作
用は生じない。 Therefore, when the bypass valve 14 is closed during normal operation of the turbine, the moist saturated steam does not flow back into the turbine bypass valve 14. Therefore, no erosion of the bypass valve stem 17 occurs.
次に、タービンバイパス弁14が開く前記2つ
の場合、タービンバイパス弁14が開いたとき、
前記弁棒17の囲りに入り込んだ高圧の蒸気は、
オリフイス23が付設された第1リーク回路19
を通つて復水器11にリークする。さらにリーク
する蒸気は第2リーク回路20を通つて復水器1
1にリークする。通常、弁棒17の囲りからのリ
ークは高圧の蒸気がリークしてくる第1リーク回
路19の量が多く、第2リーク回路20の量は第
1リーク回路19の量よりもかなり少い量になつ
ている。この第1リーク回路19を直接復水器1
1に接続すると蒸気の比容積が過大になり、第1
リーク回路19を通る体積流量が大きくなる。そ
して、流速が過大になるか、または、流速を遅く
するため回路の断面積が大きくなつたりする。そ
れを抑えるため、オリフイス23が付設された第
1リーク回路19によつて、この第1リーク回路
19のオリフイス22前まではリークする蒸気の
圧力を高め、蒸気の比容積を小さくしている。な
お前記第1リーク回路19を通る蒸気の流量はタ
ービンバイパス弁14の内部圧力と、弁棒17の
径等によつて決まるから前記オリフイス23の前
の圧力は、オリフイス23の大きさによつて任意
に設定できる。そのため、第1リーク回路19を
高圧排気管7に接続している従来のものと全く同
じシール条件とすることも可能である。 Next, in the two cases where the turbine bypass valve 14 opens, when the turbine bypass valve 14 opens,
The high-pressure steam that has entered the area around the valve stem 17 is
First leak circuit 19 with orifice 23 attached
leaks to the condenser 11 through the Further leaking steam passes through the second leak circuit 20 to the condenser 1
Leak to 1. Normally, the amount of leakage from around the valve stem 17 is large in the first leakage circuit 19 from which high-pressure steam leaks, and the amount in the second leakage circuit 20 is considerably smaller than the amount in the first leakage circuit 19. It's getting bigger. This first leak circuit 19 is connected directly to the condenser 1
If connected to 1, the specific volume of steam will become excessive, and the 1st
The volumetric flow rate through the leakage circuit 19 increases. Then, the flow velocity becomes excessive, or the cross-sectional area of the circuit becomes large in order to slow down the flow velocity. In order to suppress this, the first leak circuit 19 provided with the orifice 23 increases the pressure of the leaking steam up to the point before the orifice 22 of the first leak circuit 19, thereby reducing the specific volume of the steam. Note that the flow rate of steam passing through the first leak circuit 19 is determined by the internal pressure of the turbine bypass valve 14 and the diameter of the valve rod 17, so the pressure in front of the orifice 23 is determined by the size of the orifice 23. Can be set arbitrarily. Therefore, it is also possible to provide exactly the same sealing conditions as in the conventional system in which the first leak circuit 19 is connected to the high-pressure exhaust pipe 7.
また、タービンバイパス弁14が開くときは、
大量の蒸気を復水器11へ捨てるときであるから
第1リーク回路19を高圧排気管7に接続してい
なくても熱回収に影響はない。反対に、高圧排気
管7から第1リーク回路19を通つて蒸気が逆流
することがなくなり、熱効率が向上する。 Furthermore, when the turbine bypass valve 14 opens,
Since this is when a large amount of steam is dumped into the condenser 11, heat recovery is not affected even if the first leak circuit 19 is not connected to the high pressure exhaust pipe 7. On the contrary, steam does not flow back from the high-pressure exhaust pipe 7 through the first leak circuit 19, and thermal efficiency is improved.
以上説明したように、本発明に係るタービンバ
イパス弁浸蝕防止装置は、タービンプラントのタ
ービンバイパス系統のタービンバイパス弁弁棒か
らの漏洩蒸気を復水器へ導くためのリーク回路を
有するタービンバイパス弁浸蝕防止装置におい
て、前記リーク回路にオリフイスが付設されてい
るリーク回路を備えたので、タービンバイパス弁
が閉つているときに、弁棒が高圧排気管からの湿
つた蒸気にさらされることがなく、弁棒の浸蝕は
防止される。また、タービンバイパス弁が開いて
いるときの弁棒からのリークに対するシール性が
低下することはないなどの優れた効果がある。
As explained above, the turbine bypass valve corrosion prevention device according to the present invention has a leak circuit for guiding leaked steam from a turbine bypass valve valve stem of a turbine bypass system of a turbine plant to a condenser. In the prevention device, the leak circuit is equipped with an orifice, so when the turbine bypass valve is closed, the valve stem is not exposed to moist steam from the high-pressure exhaust pipe, and the valve stem is prevented from being exposed to moist steam from the high-pressure exhaust pipe. Erosion of the rod is prevented. Further, there are excellent effects such as no reduction in sealing performance against leakage from the valve stem when the turbine bypass valve is open.
第1図は従来の原子力タービンプラントのター
ビンバイパス弁浸蝕防止装置を示す系統図、第2
図は本発明のタービンバイバス弁浸蝕防止装置の
一実施例を原子力タービンプラントにより示す系
統図である。
1…原子炉、2…高圧タービン、3…主蒸気
管、4…主蒸気止め弁、5…主蒸気加減弁、6…
低圧タービン、7…高圧排気管、8…湿分分離
器、9…中間蒸気止め弁、10…発電機、11…
復水器、12…給水ポンプ、13…給水管、14
…バイパス弁、15…バイパス入口管、16…バ
イパス出口管、17…バスパス弁弁棒、18…半
逆止弁、19…第1リーク回路、20…第2リー
ク回路、21…蒸気発生器、22…第3リーク回
路、23…オリフイス。
Figure 1 is a system diagram showing a conventional turbine bypass valve erosion prevention device for a nuclear turbine plant;
The figure is a system diagram showing an embodiment of the turbine bypass valve corrosion prevention device of the present invention in a nuclear power turbine plant. DESCRIPTION OF SYMBOLS 1...Nuclear reactor, 2...High pressure turbine, 3...Main steam pipe, 4...Main steam stop valve, 5...Main steam control valve, 6...
Low pressure turbine, 7... High pressure exhaust pipe, 8... Moisture separator, 9... Intermediate steam stop valve, 10... Generator, 11...
Condenser, 12... Water supply pump, 13... Water supply pipe, 14
... bypass valve, 15 ... bypass inlet pipe, 16 ... bypass outlet pipe, 17 ... bus pass valve valve stem, 18 ... half check valve, 19 ... first leak circuit, 20 ... second leak circuit, 21 ... steam generator, 22...Third leak circuit, 23...Orifice.
Claims (1)
タービンバイパス弁弁棒からの漏洩蒸気を復水器
へ導くためのリーク回路を有するタービンバイパ
ス弁浸蝕防止装置において、前記リーク回路にオ
リフイスが付設されているリーク回路を備えたこ
とを特徴とするタービンバイパス弁浸蝕防止装
置。1. A turbine bypass valve corrosion prevention device having a leak circuit for guiding leaked steam from a turbine bypass valve stem of a turbine bypass system of a turbine plant to a condenser, the leak circuit having an orifice attached to the leak circuit. A turbine bypass valve erosion prevention device characterized by comprising:
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP9095282A JPS58206809A (en) | 1982-05-28 | 1982-05-28 | Corrosion preventive device for turbine bypass valve |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP9095282A JPS58206809A (en) | 1982-05-28 | 1982-05-28 | Corrosion preventive device for turbine bypass valve |
Publications (2)
Publication Number | Publication Date |
---|---|
JPS58206809A JPS58206809A (en) | 1983-12-02 |
JPS6217084B2 true JPS6217084B2 (en) | 1987-04-16 |
Family
ID=14012811
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP9095282A Granted JPS58206809A (en) | 1982-05-28 | 1982-05-28 | Corrosion preventive device for turbine bypass valve |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS58206809A (en) |
Families Citing this family (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP2918792A1 (en) | 2014-03-13 | 2015-09-16 | Siemens Aktiengesellschaft | Steam power plant with spindle leakage steam conduit |
CN110608858B (en) * | 2019-09-04 | 2021-07-30 | 魏丽蓉 | Method for testing steam internal leakage of low-pressure bypass valve of thermal generator set |
-
1982
- 1982-05-28 JP JP9095282A patent/JPS58206809A/en active Granted
Also Published As
Publication number | Publication date |
---|---|
JPS58206809A (en) | 1983-12-02 |
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