JPS5819598A - Reactor protecting device - Google Patents
Reactor protecting deviceInfo
- Publication number
- JPS5819598A JPS5819598A JP56118165A JP11816581A JPS5819598A JP S5819598 A JPS5819598 A JP S5819598A JP 56118165 A JP56118165 A JP 56118165A JP 11816581 A JP11816581 A JP 11816581A JP S5819598 A JPS5819598 A JP S5819598A
- Authority
- JP
- Japan
- Prior art keywords
- main steam
- turbine
- pressure
- reactor
- valve
- 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
- 238000002955 isolation Methods 0.000 claims description 18
- 238000011144 upstream manufacturing Methods 0.000 claims 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 5
- 241000196324 Embryophyta Species 0.000 description 4
- 230000008901 benefit Effects 0.000 description 2
- 238000009835 boiling Methods 0.000 description 2
- 235000010575 Pueraria lobata Nutrition 0.000 description 1
- 241000219781 Pueraria montana var. lobata Species 0.000 description 1
- 230000002159 abnormal effect Effects 0.000 description 1
- 230000005856 abnormality Effects 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 239000012528 membrane Substances 0.000 description 1
- 230000001052 transient effect Effects 0.000 description 1
- 230000001960 triggered effect Effects 0.000 description 1
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
- Protection Of Generators And Motors (AREA)
- Vehicle Body Suspensions (AREA)
- Particle Accelerators (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】
本発明は原子炉保護装置に係り、４１にタービン）リッ
プや発電機負荷しゃ断時に生ずる主蒸気管内の瞬間的な
圧力低下によつ【主蒸気隔離弁が閉鎖されることを防止
でするようにした原子炉保護装置Ｋ１１ｆ葛。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a nuclear reactor protection device, in which the main steam isolation valve is closed due to an instantaneous pressure drop in the main steam pipe that occurs when the turbine lip or generator load is cut off. The reactor protection device K11f kudzu was designed to prevent this from happening.
沸騰水Ｗ１原子カプラントにおいては、タービントリッ
プ時にタービン主蒸気止め弁を閉鎖させるし、また発電
機負荷しゃ断時にはタービン主蒸気加減弁を急速閉鎖さ
せ、これによりタービンおよび発電機を保護し同時Ｋｊ
［子炉をスクラムさせて原子炉の安全性を維持して−す
る。In the boiling water W1 atomic coupler plant, the turbine main steam stop valve is closed when the turbine trips, and the turbine main steam control valve is rapidly closed when the generator load is cut off, thereby protecting the turbine and generator and simultaneously reducing the Kj
[Maintain the safety of the reactor by scramming the child reactor.]
また、蒸気全容量のタービンバイパス管を有するプラン
ジにおいては、発電機負荷しゃ断時にタービン主蒸気加
減弁を急速閉鎖させると同時にバイパス弁を開放し全量
の蒸気をバイパス弁を通して復水Ｏへ流し、これｋより
原子炉をスクラムさせず所内単独運転に移行することが
できるようになっている。In addition, in a plunge that has a turbine bypass pipe with full steam capacity, when the generator load is cut off, the turbine main steam control valve is rapidly closed, the bypass valve is simultaneously opened, and the entire amount of steam is allowed to flow through the bypass valve to condensate O. k, it is now possible to shift to isolated operation within the reactor without scramming the reactor.
このよ５なターピノ主蒸気止め弁の閉鎖やタービン主蒸
気加減弁の急速閉鎖による主蒸気しゃ断時には、主蒸気
１内に圧力振動が発生し、圧力波となって主蒸気管内を
伝搬する。そして、この圧力波のため、タービン入口圧
力は、主蒸気しゃ断電後過渡的に大きく振動する。When the main steam is shut off by closing the terpino main steam stop valve or rapidly closing the turbine main steam control valve, pressure vibrations occur within the main steam 1 and propagate in the main steam pipe as pressure waves. Due to this pressure wave, the turbine inlet pressure oscillates transiently and greatly after the main steam power is cut off.
一方、原子炉の異常減圧や冷却材流水値上のため、ター
ビン入口圧力がある稠度紙（なったとき膜装置によって
制御される。その結果、主蒸気しゃ断時に過渡的なター
ビン入口圧力の振動が発生すると、上記保護装置が作動
して主蒸気隔離弁を全閉してしまう、このようにして一
時的な圧力変動にもか工わらず主蒸気隔離弁が全閉され
れば原子炉はタービン系統からは隔離されてしまう、そ
し℃一旦原子炉が隔離されると、それに続（一連の原子
炉４止操作が繁雑となりプラント運転員の負担を増大さ
せるという問題がある。On the other hand, due to the abnormal depressurization of the reactor and the increase in the coolant flow value, the turbine inlet pressure is controlled by the membrane device. If this occurs, the above-mentioned protection device will operate and fully close the main steam isolation valve.In this way, if the main steam isolation valve is fully closed despite temporary pressure fluctuations, the reactor will be closed to the turbine. Once a nuclear reactor is isolated from the system, there is a problem in that a series of operations to shut down the reactor becomes complicated and increases the burden on plant operators.
また、全容量タービンバイパス管を有するプラントにお
い℃、タービントリップや発電機負荷しゃ断が生じた際
にタービン主蒸気加減弁の急速閉鎖時の圧力波により主
蒸気隔離弁が全閉されると、前述の場合と同様に原子炉
はスクラム状態におちいり、全容量タービンバイパスシ
ステムのメリツシが生かされな（なってしまう。In addition, in a plant with a full capacity turbine bypass pipe, when the main steam isolation valve is fully closed due to the pressure wave caused by the rapid closing of the turbine main steam control valve when a turbine trip or generator load cutoff occurs, the above-mentioned As in the previous case, the reactor would fall into a scram state, and the benefits of the full capacity turbine bypass system would not be utilized.
そこで、本発明の目的は従来機量が有する上述の問題点
を解消し、主蒸気管内の一時的な圧力低下に応答して主
蒸気隔離弁が不必要に閉鎖されることを回避し１厘子炉
停止操作の繁雑さを防止することがで會るよ５にした原
子炉保護装置を提供することにある。SUMMARY OF THE INVENTION It is therefore an object of the present invention to solve the above-mentioned problems of conventional equipment, and to avoid unnecessary closure of the main steam isolation valve in response to a temporary pressure drop in the main steam pipe. It is an object of the present invention to provide a nuclear reactor protection device that can prevent complicated operations for shutting down a sub-reactor.
以下本発ｖＪＫよる原子炉保護装置の一実施例を第１図
を参照して説明する。An embodiment of the nuclear reactor protection device based on the vJK of the present invention will be described below with reference to FIG.
図において、符号１は原子炉圧力容器を示し、この原子
炉圧力容器１内で発生した蒸気は、主蒸気管２を通って
タービン３へ送られ、このタービン３で仕事をしたのち
、復水器４へ送られ凝縮して水となる。復水器４で復水
された水は、復給水配管５を通って原子炉圧力容器ｌへ
還流する。In the figure, reference numeral 1 indicates the reactor pressure vessel. Steam generated in the reactor pressure vessel 1 is sent to the turbine 3 through the main steam pipe 2, and after doing work in the turbine 3, it is condensed. It is sent to vessel 4 and condensed to become water. The water condensed in the condenser 4 flows back to the reactor pressure vessel l through the condensate water pipe 5.
また、上記主蒸気管２の管路上には、主蒸気隔離弁６、
タービン主蒸気止め弁７およびタービン主蒸気加減弁８
がそれぞれ配設されている。この主蒸気隔離弁６とター
ビン主蒸気止め弁７との間の主蒸気管２よりタービンバ
イパス管９が分岐導出され、このバイパス管９はバイパ
ス弁ｉｏｔ’介ｔ、。Further, on the pipe path of the main steam pipe 2, a main steam isolation valve 6,
Turbine main steam stop valve 7 and turbine main steam control valve 8
are arranged respectively. A turbine bypass pipe 9 is branched out from the main steam pipe 2 between the main steam isolation valve 6 and the turbine main steam stop valve 7, and this bypass pipe 9 is connected to the bypass valve iot'.
て復水器４へ接続されている。そして、前記主蒸気管２
を流れる蒸気の圧力は、タービン主蒸気止め弁７の入口
直両に設けられた圧力検出器１１で検出され、検出され
た圧力信号は破線で示した信号ラインＬｔＫより原子炉
保護装置肪へ送られる。この原子炉保護装置１３は、主
蒸気圧力が一定値以下となったとき、主蒸気隔離弁２を
全閉させる信号を主蒸気隔離弁２に対して送る機能を有
するとともに、瞬間的な圧力低下信号で閉動作をしない
よう、タイマ一手段による遅蔦回路１４が組込まれて−
する。and is connected to the condenser 4. And the main steam pipe 2
The pressure of the steam flowing through the turbine main steam stop valve 7 is detected by pressure detectors 11 installed on both sides of the inlet, and the detected pressure signal is sent to the reactor protection system via a signal line LtK indicated by a broken line. It will be done. This reactor protection device 13 has the function of sending a signal to the main steam isolation valve 2 to fully close the main steam isolation valve 2 when the main steam pressure falls below a certain value, and also has the function of sending a signal to the main steam isolation valve 2 to fully close the main steam isolation valve 2. A delay circuit 14 using a timer is incorporated to prevent the closing operation from being triggered by a signal.
do.
以下このように構成された本発明による原子炉保護装置
の動作を説明する。The operation of the nuclear reactor protection device according to the present invention configured as described above will be explained below.
原子カプラントの通常運転中、原子炉圧力容器１で発生
した蒸気は、主蒸気管２を通ってタービン３へ送られる
。しかし、タービン発電機系の異常発生時や負荷しゃ断
時等には、タービン主蒸気止め弁７の閉鎖やタービン主
蒸気加減弁８の急速閉鎖によって、タービン３への主蒸
気供給がしゃ断される。During normal operation of the nuclear couplant, steam generated in the reactor pressure vessel 1 is sent to the turbine 3 through the main steam pipe 2. However, when an abnormality occurs in the turbine generator system or when the load is cut off, the main steam supply to the turbine 3 is cut off by closing the turbine main steam stop valve 7 or rapidly closing the turbine main steam control valve 8.
ところで、主蒸気の急激なしゃ断時には、主蒸気管２内
で発生する圧力の過渡的な振動により瞬間的にタービン
入口圧力が低下する。この低下した圧力が圧力検出器１
１で検出され、予め定められた値以下になると「タービ
ン入ロ圧力低」の信号が原子炉保護装置１３へ入力され
る。しかし、この圧力低下が主蒸気の急激なしゃ断によ
る一時的なものである場合嬶、「タービン入ロ圧力低」
の信号が入力されても主蒸気隔離弁６を全閉させる指令
信号は送られない。「タービン入ロ圧力低」のイ
信号が瞬間的なものであるか否かは、夕〜マーによる遅
蔦回路１４や入力回路の不滅帯等により容易に判別でき
る。そして、「タービン入ロ圧力低」の信号がある程度
連続的に入力された場合にのみ、この装量りが作動して
主蒸気隔離弁６を全閉させる。By the way, when the main steam is abruptly shut off, the turbine inlet pressure drops instantaneously due to the transient vibration of the pressure generated within the main steam pipe 2. This reduced pressure is detected by the pressure detector 1.
1, and when the pressure falls below a predetermined value, a signal indicating "turbine entry pressure low" is input to the reactor protection device 13. However, if this pressure drop is temporary due to a sudden cutoff of the main steam, then "turbine entry pressure is low."
Even if this signal is input, a command signal to fully close the main steam isolation valve 6 is not sent. Whether or not the "Turbine input pressure low" signal is instantaneous can be easily determined from the delay circuit 14 of the evening and timer, the indestructible band of the input circuit, and the like. Then, only when the signal "Turbine entry pressure low" is input continuously to some extent, this charging is activated and the main steam isolation valve 6 is fully closed.
以上の説明から明らかなよ５に、本発明によれば、主蒸
気管内の圧力を入力信号とし、一時的な圧力低下信号に
対しては応答しない回路を設けたかも、比較的に発生頻
度が高いと考えられるタービントリップ時や負荷しゃ断
時に無用な主蒸気隔離弁の全閉を回避することができる
。したがつ【。As is clear from the above explanation, according to the present invention, a circuit that uses the pressure in the main steam pipe as an input signal and does not respond to a temporary pressure drop signal may be provided, but the frequency of occurrence is relatively low. It is possible to avoid unnecessary full closure of the main steam isolation valve at the time of a turbine trip or load cutoff, which is considered to be a high risk. Gakatsu [.
原子炉隔離の頻度を減少させることが可能となり、運転
員のプラント停止操作の繁雑化を陳ぎ運転員の負担を軽
減することができるという大きな利点がある。This has the great advantage of reducing the frequency of reactor isolation, reducing the complexity of plant shutdown operations for operators, and reducing the burden on operators.
図は、本発明による原子炉保護装置を設けた沸騰水型原
子力発電プラントの概略構成図である。
１・・・原子炉圧力容器、２・・・主蒸気管、３・・・
タービン、６・・・主蒸気隔離弁、７・・リーピｙ主蒸
気止め弁、８・・・タービン主蒸気加減弁、９・・・タ
ーインバイパス管、 １Ｇ・−・バイパス弁、１１−・
・圧力検出器、１３・・・原子炉保護装置、１４・・・
遅蔦回路。The figure is a schematic configuration diagram of a boiling water nuclear power plant equipped with a reactor protection device according to the present invention. 1... Reactor pressure vessel, 2... Main steam pipe, 3...
Turbine, 6...Main steam isolation valve, 7...Reapy main steam stop valve, 8...Turbine main steam control valve, 9...Tine bypass pipe, 1G...Bypass valve, 11-...
・Pressure detector, 13... Reactor protection device, 14...
Late ivy circuit.
Claims (1)
き上記主蒸気管上に原子炉側より主蒸気隔離弁および主
蒸気加減弁を組込んだものにおいて、上記主蒸気上め弁
の上流側の圧力を検出し。 この圧力信号を原子炉保護回路に供給し、その出力信号
で主蒸気′隔離弁を開閉制御し、さらに上記保護回路中
に圧力の一時的な変動に対して弁を不作動する回路を組
込んだことを％黴とする原子炉保護装置。[Scope of Claims] A main steam isolation valve and a main steam control valve are installed on the main steam pipe from the reactor side by introducing the steam generated in the nuclear reactor into the main steam pipe 2 through the main steam pipe. Detects the pressure on the upstream side of the upper valve. This pressure signal is supplied to the reactor protection circuit, and the output signal is used to control the opening and closing of the main steam isolation valve, and a circuit that disables the valve in response to temporary fluctuations in pressure is incorporated into the protection circuit. A nuclear reactor protection device that eliminates mold.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56118165A JPS5819598A (en) | 1981-07-28 | 1981-07-28 | Reactor protecting device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56118165A JPS5819598A (en) | 1981-07-28 | 1981-07-28 | Reactor protecting device |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS5819598A true JPS5819598A (en) | 1983-02-04 |
Family
ID=14729712
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP56118165A Pending JPS5819598A (en) | 1981-07-28 | 1981-07-28 | Reactor protecting device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5819598A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB2524901A (en) * | 2014-04-02 | 2015-10-07 | Harman Becker Automotive Sys | Loudspeaker |
-
1981
- 1981-07-28 JP JP56118165A patent/JPS5819598A/en active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB2524901A (en) * | 2014-04-02 | 2015-10-07 | Harman Becker Automotive Sys | Loudspeaker |
| GB2524901B (en) * | 2014-04-02 | 2016-04-27 | Harman Becker Automotive Systems Gmbh | Loudspeaker |
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