JPH08110392A - Reactor water supply facility - Google Patents

Reactor water supply facility

Info

Publication number
JPH08110392A
JPH08110392A JP7210425A JP21042595A JPH08110392A JP H08110392 A JPH08110392 A JP H08110392A JP 7210425 A JP7210425 A JP 7210425A JP 21042595 A JP21042595 A JP 21042595A JP H08110392 A JPH08110392 A JP H08110392A
Authority
JP
Japan
Prior art keywords
water supply
pump
reactor
pumps
water
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
Application number
JP7210425A
Other languages
Japanese (ja)
Inventor
Tadashi Fujii
正 藤井
Shiyouichirou Kinoshita
詳一郎 木下
Junichi Akatsu
純一 赤津
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Hitachi Ltd
Original Assignee
Hitachi Ltd
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP7210425A priority Critical patent/JPH08110392A/en
Publication of JPH08110392A publication Critical patent/JPH08110392A/en
Pending legal-status Critical Current

Links

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin

Landscapes

  • Structures Of Non-Positive Displacement Pumps (AREA)
  • Control Of Non-Positive-Displacement Pumps (AREA)

Abstract

PURPOSE: To standardize water supply pumps and improve maintainability and arrangement of components by providing more water supply pumps with almost the same capacity than a specific number. CONSTITUTION: This reactor water supply equipment is constituted of 4 or more systems of water supply pumps 11 to 14 with ca. 33% capacity of rated flowrate per a system. The pumps 11 to 14 are driven with motors 15 to 18. The rotation shaft of the motors 15 to 17 are connected to the corresponding rotation shaft of pumps 11 to 13 by way of corresponding fluid coupling 19 to 21. Each fluid coupling 19 to 21 variably controls transmission torque and changes the revolution number of the pumps 11 to 13. The pump 14 is operated in a constant speed with the motor 18 by way of a speed increaser 23 and water supply rate is controlled with a control valve 90 in the discharge side. In the front and back of the pumps 11 to 14, gate valves 81 to 88 are provided. Among four systems, one system of the pump 14 driven with the motor 18 is a standby system and is in standby state during normal operation. Other three systems of pumps 11 to 13 are operating systems driven in normal operation.

Description

【発明の詳細な説明】Detailed Description of the Invention

【0001】[0001]

【産業上の利用分野】本発明は、原子炉プラントの冷却
系設備に係り、原子炉への給水流量を制御する原子炉給
水設備に関する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a cooling system facility for a nuclear reactor plant, and more particularly to a reactor water supply facility for controlling the flow rate of water supplied to the reactor.

【0002】[0002]

【従来の技術】原子炉プラント、例えば700MWe級
以上の沸騰水型原子炉においては、原子炉への給水設備
として、図2に示すように、常用として定格流量の50
%容量の蒸気タービン駆動給水ポンプを2系統、起動停
止時やタービン駆動給水ポンプ1基故障時の予備として
起動する定格流量の25%容量の電動機駆動給水ポンプ
を2系統組み合わせた構成が一般的である。
2. Description of the Related Art In a reactor plant, for example, a boiling water reactor of 700 MWe class or higher, as a water supply facility for the reactor, as shown in FIG.
A typical configuration is a combination of two systems of a steam turbine driven feed water pump of% capacity and two systems of an electric motor driven feed water pump of 25% capacity of the rated flow rate, which is started as a backup when starting / stopping or when one turbine drive water feed pump fails. is there.

【0003】タービン駆動給水ポンプは、主タービンに
流入する蒸気を抽気してポンプに直結されたタービンを
駆動し、その蒸気流量を制御することによりタービン回
転数を調整して給水流量を制御する。また、電動機駆動
給水ポンプは、定速の電動機で駆動され、ポンプの吐出
側に設けた給水調整弁の開度を調整することにより給水
流量を制御する。このような沸騰水型原子炉の給水設備
は、以下のような制御系を備えている。給水流量,主蒸
気流量及び原子炉水位の3種類の信号を水位制御器に取
り入れて、水位設定値と比較判断し、タービン駆動給水
ポンプの速度制御、あるいは電動機駆動給水ポンプの給
水調整弁の開度制御を行うことで、給水流量を自動的に
調整し、あらかじめ定めた原子炉水位を保つように制御
する。
The turbine-driven feed water pump extracts the steam flowing into the main turbine to drive the turbine directly connected to the pump, and controls the steam flow rate to adjust the turbine rotation speed to control the feed water flow rate. The electric motor driven water supply pump is driven by a constant speed electric motor, and controls the water supply flow rate by adjusting the opening of a water supply adjustment valve provided on the discharge side of the pump. The water supply system for such a boiling water reactor is equipped with the following control system. Incorporating three kinds of signals of feed water flow rate, main steam flow rate and reactor water level into the water level controller and comparing and judging with the water level set value, speed control of the turbine driven water feed pump or opening of the water feed adjustment valve of the electric motor driven water feed pump. Temperature control, the feed water flow rate is automatically adjusted and controlled so as to maintain a predetermined reactor water level.

【0004】また、特開平6−3491 号公報に記載のよう
に、サイリスタインバータを用いた回転数可変の同期電
動機で駆動する常用の給水ポンプと、回転数固定の誘導
電動機で駆動する予備の給水ポンプで構成する例もあ
る。
Further, as described in Japanese Patent Application Laid-Open No. 6-3491, a common water supply pump driven by a synchronous motor having a variable rotation speed using a thyristor inverter, and an auxiliary water supply driven by an induction motor having a fixed rotation speed. There is also an example of a pump.

【0005】[0005]

【発明が解決しようとする課題】上記のタービン駆動給
水ポンプと電動機駆動給水ポンプを組み合わせた原子炉
給水設備においては、タービン駆動方式に関して以下の
ような課題がある。
DISCLOSURE OF THE INVENTION Problems to be Solved by the Invention In the reactor water supply system in which the turbine driven water supply pump and the electric motor driven water supply pump are combined, there are the following problems regarding the turbine drive system.

【0006】タービン駆動給水ポンプは、駆動用の蒸気
を抽気する主タービンや、タービンから排気された蒸気
を凝縮する主復水器に近接して配置されている。このた
め、給水ポンプが配置される領域の放射線線量が高く、
しゃへい設計上通常運転中は立入り不要の領域に区分さ
れる。したがって、原子炉の運転中、機器へ接近するこ
とはできず、運転中の保守作業は実施できない。また、
主タービン及び主復水器との配置上の制約を受けるた
め、タービン建屋内での配置の自由度が制限される。さ
らに、タービン駆動給水ポンプの制御に必要な潤滑油
系,油圧制御系などは部品点数が多く、保守点検作業量
が増加する。
The turbine-driven feed water pump is arranged in the vicinity of a main turbine that extracts steam for driving and a main condenser that condenses steam discharged from the turbine. Therefore, the radiation dose in the area where the water supply pump is located is high,
Due to the shield design, it is divided into areas that do not require entry during normal operation. Therefore, the equipment cannot be accessed during the operation of the reactor, and maintenance work cannot be performed during the operation. Also,
Due to restrictions on the arrangement of the main turbine and the main condenser, the degree of freedom of arrangement within the turbine building is limited. Further, the lubricating oil system and hydraulic control system required for controlling the turbine-driven feed water pump have a large number of parts, which increases the amount of maintenance and inspection work.

【0007】これに加え、上記のタービン駆動給水ポン
プと電動機駆動給水ポンプを組み合わせた原子炉給水設
備においては、常用系統の給水ポンプと待機系統の給水
ポンプの容量が異なっているため、2種類の給水ポンプ
の製造が必要となる。
In addition to this, in the reactor water supply system in which the turbine driven water supply pump and the electric motor driven water supply pump are combined, the capacity of the water supply pump of the normal system is different from that of the water supply pump of the standby system. It is necessary to manufacture a water supply pump.

【0008】また、前記特開平6−3491 号公報に記載の
例では、電動機で全ての給水ポンプを駆動する方式とな
っているが、常用系統における給水ポンプ1台当りの容
量は定格の給水流量の50%としている。しかし、例え
ば1350MWe級の大型炉に適用する場合には、給水
ポンプを駆動する電動機の単機容量が約11000kW
となり現状の製作実績値を上回ってしまう。小型の電動
機をタンデム化することにより、電動機容量を増加させ
ることは可能だが、配置スペースや物量・コストの増加
となり好ましくない。
Further, in the example described in the above-mentioned Japanese Patent Laid-Open No. 6-3491, all the water supply pumps are driven by an electric motor, but the capacity per water supply pump in the regular system is the rated water supply flow rate. 50% of However, when applied to a large reactor of 1350 MWe class, for example, the capacity of the electric motor for driving the feed water pump is about 11000 kW.
Will exceed the current production record. It is possible to increase the capacity of the electric motor by making the small electric motor tandem, but this is not preferable because it increases the installation space, the quantity and cost.

【0009】本発明の目的は、給水ポンプの標準化と、
機器の保守性・配置性の向上を可能とする原子炉給水設
備を提供することにある。
The object of the present invention is to standardize the water supply pump and
It is to provide a reactor water supply facility that can improve the maintainability and layout of equipment.

【0010】[0010]

【課題を解決するための手段】上記の目的は、給水ポン
プ及び給水流量調整弁を含む1系統の待機系統、及び給
水ポンプを含む少なくとも3系統の常用系統を原子炉給
水経路に並列に装備した原子炉給水設備であって、前記
各給水ポンプは電動機で駆動される給水ポンプであって
互いにほぼ等しい容量を有する給水ポンプであり、前記
常用系統のうち少なくとも2系統は、前記給水ポンプの
回転数を制御するポンプ回転数可変手段を備えているこ
とを特徴とした原子炉給水設備によって達成される。
[Means for Solving the Problems] The above object is to equip a reactor water supply path with in parallel a single standby system including a water supply pump and a water supply flow rate adjusting valve, and at least three service systems including a water supply pump. A reactor water supply facility, wherein each of the water supply pumps is a water supply pump driven by an electric motor and has a substantially equal capacity to each other, and at least two systems of the regular system are rotation speeds of the water supply pump. It is achieved by a reactor water supply facility characterized in that it is provided with a pump rotation speed varying means for controlling the.

【0011】[0011]

【作用】各系統の各給水ポンプの容量をほぼ等しく設定
したことにより、各系統において同一仕様の給水ポンプ
を使用できるようになり、給水ポンプの標準化が可能に
なる。このため、給水ポンプの製造も容易になる。
[Function] By setting the capacities of the water supply pumps of the respective systems to be substantially equal to each other, the water supply pumps having the same specifications can be used in the respective systems, and the water supply pump can be standardized. Therefore, the manufacturing of the water supply pump becomes easy.

【0012】また、従来のタービン駆動給水ポンプと電
動機駆動給水ポンプの組み合わせとは異なり、全ての給
水ポンプを電動機駆動としたことにより、電動機の基数
が増加するが、給水ポンプ駆動用のタービンや蒸気配管
・弁が削除できる。
Further, unlike the conventional combination of the turbine driven water feed pump and the electric motor driven water feed pump, since all the water feed pumps are driven by the electric motor, the number of electric motors increases, but the turbine or steam for driving the water feed pump is increased. Pipes and valves can be deleted.

【0013】このため、給水ポンプを主タービンや主復
水器と分離して放射線量が低い領域に配置でき、配置の
自由度が向上する。これに加え、しゃへい設計上の要求
が低減するため、運転中機器への接近性が改善され給水
設備の保守性が向上する。電動機やポンプの回転数を調
整する機器の部品数は、タービン駆動方式に比べ少な
く、保守点検作業量も低減する。
Therefore, the water supply pump can be separated from the main turbine and the main condenser in the region where the radiation dose is low, and the degree of freedom of arrangement is improved. In addition to this, since the requirements for the shield design are reduced, the accessibility to the equipment during operation is improved and the maintainability of the water supply facility is improved. Compared to the turbine drive system, the number of parts of the equipment that adjusts the rotation speed of the electric motor and pump is smaller, and the maintenance and inspection work volume is also reduced.

【0014】さらに、給水ポンプを4台以上とすること
により、1系統あたりのポンプ容量を低減しているの
で、大型炉に適用する場合においても、製作実績範囲内
の電動機で対応できるため、製作性も容易であり、タン
デム化のような物量の過度な増大が抑制できる。
Further, since the pump capacity per system is reduced by using four or more water supply pumps, even when it is applied to a large reactor, an electric motor within the actual production range can be used. The property is also easy, and it is possible to suppress an excessive increase in the amount of material such as tandemization.

【0015】当初給水流量が少ないので原子炉起動時の
給水に当たっては、給水ポンプの可変速よる給水流量の
調整が流量調整弁によるそれよりも制御応答性が低いの
で、流量調整が待機系統乃至は待機系統を含む複数の系
統の稼働と待機系等の流量調整弁の開度によって成され
る。
Since the feed water flow rate is small at the beginning, the control response of the feed water flow rate adjustment by the variable speed of the feed water pump is lower than that by the flow rate adjusting valve, so that the flow rate adjustment is performed in the standby system or It is configured by the operation of a plurality of systems including the standby system and the opening of the flow rate adjusting valve of the standby system and the like.

【0016】[0016]

【実施例】本発明の一実施例である原子炉給水設備を、
図1,図3及び図4により説明する。
[Example] A reactor water supply system according to an embodiment of the present invention,
This will be described with reference to FIGS. 1, 3 and 4.

【0017】対象とする原子炉給水設備は、図1に示す
ように1系統あたりの容量が定格流量の約33%容量の
給水ポンプ11〜14の4系統で構成される。給水ポン
プ11〜14は、電動機15〜18で駆動される。各電
動機15〜18の回転軸は、対応する流体継手19〜2
1を介して対応する給水ポンプ11〜13の回転軸に連
結される。各流体継手は、電動機から給水ポンプへの伝
達トルクを可変調整する。従って、流体継手を用いるこ
とにより給水ポンプの回転数を変えることができる。具
体的には、流体継手19〜21のすくい管の位置を変更
することで給水ポンプ11〜13の回転数が可変調整可
能に制御される。また、給水ポンプ14は、増速機23
を介して電動機18により一定速度で運転される。給水
ポンプ14の吐出側に設けた給水調整弁90の開度を制
御することによって、給水ポンプ14から吐出された給
水流量を調整する。
As shown in FIG. 1, the target reactor water supply system is composed of four systems of water supply pumps 11 to 14 each having a capacity of about 33% of the rated flow rate. The water supply pumps 11 to 14 are driven by electric motors 15 to 18. The rotary shafts of the electric motors 15-18 correspond to the corresponding fluid couplings 19-2.
1 is connected to the rotary shafts of the corresponding water supply pumps 11 to 13. Each fluid coupling variably adjusts the transmission torque from the electric motor to the water supply pump. Therefore, the rotational speed of the water supply pump can be changed by using the fluid coupling. Specifically, the rotational speeds of the water supply pumps 11 to 13 are variably adjustable by changing the positions of the rake pipes of the fluid couplings 19 to 21. In addition, the water supply pump 14 is a gearbox 23.
It is operated at a constant speed by the electric motor 18 via. By controlling the opening degree of the water supply adjusting valve 90 provided on the discharge side of the water supply pump 14, the flow rate of the water supply discharged from the water supply pump 14 is adjusted.

【0018】給水ポンプ11〜14の前後には、仕切弁
81〜88を設けている。4系統のうち、電動機18で
駆動される給水ポンプ14の1系統は、待機系統であっ
て通常運転時には待機状態にある。残りの給水ポンプ1
1〜13の3系統は、通常運転時に駆動される常用系統
である。
Gate valves 81 to 88 are provided before and after the water supply pumps 11 to 14, respectively. Of the four systems, one system of the water supply pump 14 driven by the electric motor 18 is a standby system and is in a standby state during normal operation. Remaining water supply pump 1
The three systems 1 to 13 are normal systems that are driven during normal operation.

【0019】図3は、図1に示す実施例の原子炉給水設
備を用いた沸騰水型原子炉プラントの概略系統を示す。
給水系の給水ポンプ11〜13によって昇圧された冷却
水は、給水配管59を通り高圧給水加熱器58で所定の
給水温度まで加熱された後、原子炉51に供給される。
冷却水は、炉心で加熱されて蒸気となり、主蒸気配管6
0により高圧タービン52に供給される。高圧タービン
52から吐出された蒸気は、湿分分離加熱器53を経由
して低圧タービン54に導かれる。低圧タービン54か
ら吐出された蒸気は、復水器55で凝縮されて復水とな
り、復水ポンプ56,低圧給水加熱器57を経て、給水
系の給水ポンプに戻る構成となっている。
FIG. 3 shows a schematic system of a boiling water reactor plant using the reactor water supply system of the embodiment shown in FIG.
The cooling water whose pressure has been increased by the water supply system water supply pumps 11 to 13 passes through the water supply pipe 59, is heated to a predetermined water supply temperature by the high-pressure water supply heater 58, and is then supplied to the nuclear reactor 51.
The cooling water is heated in the core to become steam, and the main steam pipe 6
0 to the high pressure turbine 52. The steam discharged from the high-pressure turbine 52 is guided to the low-pressure turbine 54 via the moisture separation heater 53. The steam discharged from the low-pressure turbine 54 is condensed into a condensate by the condenser 55, passes through the condensate pump 56, the low-pressure feed water heater 57, and returns to the feed water pump of the feed water system.

【0020】また、給水ポンプ11〜14の下流側配管
に設けられた流量計71〜74,原子炉51に設けた水
位計75,主蒸気配管60に設けられた流量計76から
の信号をもとに、流体継手19〜21のすくい管位置を
制御して給水ポンプ11〜13の回転数を調整する、あ
るいは給水ポンプ14から吐出される給水に対しては給
水調整弁90の開度を調整することによって、原子炉5
1に供給する給水流量を制御する給水制御系77を備え
ている。このような給水流量の制御は、原子炉51内の
水位を制御することになる。
Signals from the flowmeters 71 to 74 provided in the downstream pipes of the water supply pumps 11 to 14, the water level meter 75 provided in the reactor 51, and the flowmeter 76 provided in the main steam pipe 60 are also output. In addition, the rake pipe positions of the fluid couplings 19 to 21 are controlled to adjust the rotation speeds of the water supply pumps 11 to 13, or the opening of the water supply adjustment valve 90 is adjusted for the water supplied from the water supply pump 14. The reactor 5
1 is provided with a water supply control system 77 for controlling the flow rate of water supply. Such control of the feed water flow rate controls the water level in the nuclear reactor 51.

【0021】本実施例は、原子炉の起動時に給水を開始
する場合には、まず、待機系である給水ポンプ14を起
動し、給水調整弁90の開度を徐々に増大させ、原子炉
に供給する給水流量を増加させる。仕切弁84及び88
は全開の状態にある。他の仕切弁81〜83,85〜8
7は、全閉となっており、給水ポンプ11〜13は停止
している。給水調整弁90が全開になったとき、給水流
量は33%となる。その後、常用系の一系統の給水ポン
プ、例えば給水ポンプ11を起動する。仕切弁81及び
85は全開にされる。給水制御系77によって流体継手
19のすくい管位置を制御することによって、給水ポン
プ11の回転数が徐々に増加する。回転数の増加により
給水流量も対応して増加する。給水ポンプ11からの給
水流量が33%になったとき、次に、給水ポンプ12を
起動する。仕切弁82及び86は全開である。給水ポン
プ12は給水ポンプ11と同様に回転数が徐々に増加さ
れる。給水ポンプ12による給水流量の増加は、給水制
御系77によって給水調整弁90の開度減少をもたら
す。しかし、トータルの給水流量は66%に保持され
る。給水ポンプ12から吐出される給水流量が33%に
達したとき、給水調整弁90は全閉となり、仕切弁84
及び88も全閉となる。このようにして、原子炉の起動
時に待機系等の給水系から常用系統の給水系への切り替
えが終了する。その後は、常用系統の給水系の残りの給
水ポンプ13が起動され、給水流量は100%となる。仕
切弁83及び87は全開である。なお、原子炉停止時
は、この逆の操作で、給水流量が減少される。
In this embodiment, when water supply is started when the reactor is started, first, the water supply pump 14 which is a standby system is started to gradually increase the opening degree of the water supply adjusting valve 90, and Increase the supply water flow rate. Gate valves 84 and 88
Is fully open. Other gate valves 81-83, 85-8
7 is fully closed, and the water supply pumps 11 to 13 are stopped. When the water supply adjusting valve 90 is fully opened, the water supply flow rate is 33%. After that, the water supply pump of one system of the regular system, for example, the water supply pump 11 is started. Gate valves 81 and 85 are fully opened. By controlling the rake pipe position of the fluid coupling 19 by the water supply control system 77, the rotation speed of the water supply pump 11 is gradually increased. As the number of rotations increases, the water supply flow rate will correspondingly increase. When the water supply flow rate from the water supply pump 11 reaches 33%, the water supply pump 12 is then activated. Gate valves 82 and 86 are fully open. Like the water supply pump 11, the water supply pump 12 gradually increases in rotational speed. The increase in the water supply flow rate by the water supply pump 12 causes the water supply control system 77 to decrease the opening degree of the water supply adjusting valve 90. However, the total water supply flow rate is maintained at 66%. When the water supply flow rate discharged from the water supply pump 12 reaches 33%, the water supply adjustment valve 90 is fully closed and the sluice valve 84
And 88 are also fully closed. In this way, the switching from the water supply system such as the standby system to the water supply system of the regular system is completed when the reactor is started. After that, the remaining water supply pump 13 of the water supply system of the regular system is activated, and the water supply flow rate becomes 100%. Gate valves 83 and 87 are fully open. When the reactor is shut down, the flow rate of feed water is reduced by the reverse operation.

【0022】このように、原子炉起動時の給水流量が少
ないときに、待機系等の給水ポンプ14を起動し給水調
整弁90の開度制御により給水流量を増加させる理由
は、給水調整弁90の開度制御の方が常用系統の給水ポ
ンプの回転数制御よりも給水流量時における制御の応答
性が良く、制御性が良いからである。また、原子炉の通
常運転時(定格運転時)は、回転数制御が可能な給水ポ
ンプ11〜13を起動するので、これらの給水ポンプを
回転させる電気エネルギーを有効に利用できる。給水調
整弁90は全開状態になっても圧力損失が仕切弁81〜
88よりも大きいので、給水ポンプ14の揚程は、給水
調整弁90の圧力損失の分だけ給水ポンプ11〜13の
各揚程よりも高く設定されている。各給水ポンプの定格
給水流量は同じであるので、給水ポンプ14は、揚程が
高く設定されている分だけ給水ポンプ11〜13よりも
電気エネルギーを多く消費することになる。従って、通
常運転時においては、給水ポンプの回転数を制御して給
水制御を行う方がエネルギー効率が高い。本実施例は、
通常運転時に3系統の給水ポンプの回転数を制御するの
で、電気エネルギーを最も効率良く利用できる。
As described above, when the feed water flow rate at the time of starting the reactor is small, the reason why the feed water pump 14 such as the standby system is started to control the opening degree of the water feed adjusting valve 90 to increase the feed water flow is This is because the opening degree control has better control responsiveness and controllability at the time of the water supply flow rate than the rotation speed control of the water supply pump in the regular system. Further, during normal operation (during rated operation) of the nuclear reactor, the water supply pumps 11 to 13 whose rotation speeds can be controlled are started, so that electric energy for rotating these water supply pumps can be effectively used. Even if the water supply adjusting valve 90 is fully opened, pressure loss is caused by the gate valves 81 to 81.
Since it is larger than 88, the lift of the water supply pump 14 is set higher than the respective lifts of the water supply pumps 11 to 13 by the pressure loss of the water supply adjusting valve 90. Since the rated water supply flow rates of the respective water supply pumps are the same, the water supply pump 14 consumes more electric energy than the water supply pumps 11 to 13 because the head is set high. Therefore, during normal operation, it is more energy efficient to control the water supply by controlling the rotation speed of the water supply pump. In this embodiment,
Since the rotational speeds of the three systems of water supply pumps are controlled during normal operation, electric energy can be used most efficiently.

【0023】本実施例では、各給水ポンプ11〜14の
容量を給水設備全体の定格流量の1/3、すなわち約3
3%と等しく設定している。このため、各系統において
同一仕様の給水ポンプを使用できるようになり、給水ポ
ンプ設計の標準化を可能としている。同一仕様の給水ポ
ンプを製造すればよいので、それの製造も容易である。
保守点検時に使用する部品も各給水ポンプで共有化でき
る。3系統の各常用系統は、給水ポンプの回転数を可変
に制御する手段、すなわち流体継手を備えているので、
給水ポンプ起動直後の低流量状態から定格流量まで給水
ポンプ一台当りの給水流量をスムーズに変化させること
ができる。
In this embodiment, the capacity of each of the water supply pumps 11 to 14 is 1/3 of the rated flow rate of the entire water supply facility, that is, about 3
It is set equal to 3%. For this reason, it is possible to use water supply pumps with the same specifications in each system, which enables standardization of water supply pump designs. Since it is only necessary to manufacture water supply pumps having the same specifications, it is easy to manufacture them.
Parts used for maintenance and inspection can be shared by each water pump. Since each of the three regular systems is provided with a means for variably controlling the rotation speed of the water supply pump, that is, a fluid coupling,
It is possible to smoothly change the water supply flow rate per water supply pump from the low flow rate state immediately after starting the water supply pump to the rated flow rate.

【0024】従来のタービン駆動の給水ポンプと電動機
駆動の給水ポンプを備えた原子炉給水設備と本実施例と
の物量を比較すると、給水ポンプの基数は等しいが、本
実施例は、1系統当りの容量を給水設備全体の約33%
としているので、給水ポンプを駆動する電動機動力の過
度な増大を抑制でき、従来よりも物量が著しく低減す
る。
Comparing the physical quantity of a conventional reactor water supply facility equipped with a turbine-driven water supply pump and an electric motor-driven water supply pump with that of this embodiment, the number of water supply pumps is the same, but this embodiment is 33% of the total water supply capacity
Therefore, it is possible to suppress an excessive increase in the electric power of the electric motor that drives the water supply pump, and the amount of material is significantly reduced as compared with the conventional case.

【0025】本実施例を1350MWe級の原子炉プラ
ントに適用した場合には、電動機容量が約8000kW
となる。この電動機容量は、単機での製作実績範囲内に
あるので、新たな大型電動機の開発や小型の電動機のタ
ンデム化等が不要であり、電動機の物量の増大が抑制で
きる。また、給水ポンプの総設備容量も従来の150%
から133%に低減できる。なお、全ての給水ポンプ1
1〜14を電動機駆動としたことにより、従来の設備に
比べ電動機2基と流体継手3基の物量が増加するが、タ
ービン駆動給水ポンプに付随するタービン2基や蒸気配
管・弁を削除でき、コンパクトになる。
When this embodiment is applied to a 1350 MWe class reactor plant, the electric motor capacity is about 8000 kW.
Becomes Since the capacity of the electric motor is within the range of actual production of a single electric machine, development of a new large electric motor and tandemization of a small electric motor are unnecessary, and an increase in the physical quantity of the electric motor can be suppressed. Also, the total installed capacity of the water supply pump is 150% of the conventional capacity.
Can be reduced to 133%. In addition, all water supply pumps 1
Since 1 to 14 are driven by an electric motor, the quantity of electric motors and three fluid couplings is increased as compared with conventional equipment, but two turbines and steam pipes / valves attached to a turbine driven feed pump can be deleted, It becomes compact.

【0026】この結果、給水ポンプ11〜14を、主タ
ービン及び主復水器から分離して放射線量が低い領域に
配置でき、配置設計での自由度が向上する。これととも
に、しゃへい設計上の要求が低減するため、運転中機器
への接近性が改善され、原子炉給水設備の保守性が向上
する。
As a result, the water supply pumps 11 to 14 can be separated from the main turbine and the main condenser in a region where the radiation dose is low, and the degree of freedom in layout design is improved. At the same time, the requirements for shielding design are reduced, so that the accessibility to the operating equipment is improved and the maintainability of the reactor water supply facility is improved.

【0027】さらに、電動機15〜18や流体継手19
〜21の機器の部品数は、タービン駆動方式に比べ少な
く、保守点検作業量も低減する。また、通常運転中に稼
動している3系統の給水ポンプ11〜13のうち、何ら
かの原因で給水ポンプ1台がトリップした場合には、待
機状態にある給水ポンプ14の系統が起動する。
Further, the electric motors 15 to 18 and the fluid coupling 19
The number of parts of equipments up to 21 is smaller than that of the turbine drive system, and the amount of maintenance and inspection work is also reduced. Further, if one of the three water supply pumps 11 to 13 operating during normal operation trips for some reason, the water supply pump 14 in the standby state is activated.

【0028】図4は、図1において、給水ポンプ12が
トリップした場合を示している。給水ポンプ12の系統
に設けた流量計(図示せず)からの信号により、給水ポ
ンプ12がトリップしたことが検出された場合、給水制
御系77により、その系統の仕切弁82,86を全閉と
する。これと同時に、給水制御系77により待機状態に
ある電動機18を起動して給水ポンプ14を駆動し、仕
切弁84,88、給水調整弁90を全開にして、設備全
体の約1/3の流量を確保することができる。電動機1
8を駆動して待機系統の給水ポンプ14を起動すること
により、従来と同様に、原子炉のスクラムレベル水位に
至るような大幅な水位変動が抑制できるので、給水ポン
プ1台トリップ時においても、原子炉の運転が継続でき
原子炉設備の稼働率が向上する。
FIG. 4 shows a case where the water supply pump 12 in FIG. 1 trips. When a signal from a flow meter (not shown) provided in the system of the water supply pump 12 detects that the water supply pump 12 has tripped, the water supply control system 77 fully closes the gate valves 82 and 86 of the system. And At the same time, the water supply control system 77 starts the electric motor 18 in the standby state to drive the water supply pump 14, and fully open the sluice valves 84 and 88 and the water supply adjusting valve 90 to obtain a flow rate of about 1/3 of the entire equipment. Can be secured. Electric motor 1
By driving 8 to start the water supply pump 14 of the standby system, it is possible to suppress a large water level fluctuation such as reaching the scrum level water level of the nuclear reactor as in the conventional case, so even when one water supply pump trips, The operation of the nuclear reactor can be continued and the operating rate of the nuclear reactor equipment can be improved.

【0029】従来の原子炉給水設備の待機系は、定格流
量の25%容量の電動機駆動給水ポンプを2系統として
いたが、本実施例では、待機系が1系統であり、待機系
起動時の制御方法が単純化する。
In the conventional standby system of the reactor water supply system, two electric motor driven feed pumps having a capacity of 25% of the rated flow rate were used, but in the present embodiment, the standby system is one system, and the standby system is The control method is simplified.

【0030】このように、本実施例では、約33%×4
系統の電動機駆動の給水ポンプ(3系統の常用系統の給
水ポンプは流体継手制御による可変速運転方式、1系統
の待機系の給水ポンプは定速運転方式)で原子炉給水設
備を構成したことにより、給水ポンプの標準化が可能と
なるとともに、電動機動力の過度な増大を抑制できる。
また、設備の物量を過度に増大させることなく、従来の
タービン駆動給水ポンプに付随したタービンや蒸気配管
・弁を削除できるため、タービン建屋内における給水ポ
ンプ配置の自由度が増大しかつ給水設備の保守性が向上
するとともに、給水設備の合理化を図ることができる。
Thus, in this embodiment, about 33% × 4
By constructing the reactor water supply equipment with a system electric motor driven water supply pump (three system water supply pumps are variable speed operation system by fluid coupling control, one standby system water supply pump is constant speed operation system) In addition to standardizing the water supply pump, it is possible to suppress an excessive increase in motor power.
In addition, the turbine and steam pipes / valves associated with the conventional turbine-driven water feed pump can be deleted without excessively increasing the amount of equipment, which increases the degree of freedom in arranging the water feed pump in the turbine building and increases the The maintainability can be improved and the water supply facility can be rationalized.

【0031】これに加え、給水ポンプの1系統を予備機
としているので、常用機の給水ポンプ1台トリップ時に
おいても、スクラムレベルに達するような原子炉水位の
大幅な低下を抑制でき、原子炉設備の稼働率向上に寄与
する。
In addition to this, since one system of the water supply pump is used as a standby machine, even when one of the water supply pumps of the regular machine is tripped, it is possible to suppress a drastic drop in the reactor water level that would reach the scrum level, and to reduce the reactor water level. Contributes to improving the operating rate of equipment.

【0032】本発明の他の一実施例を、図5より説明す
る。
Another embodiment of the present invention will be described with reference to FIG.

【0033】対象とする原子炉給水設備は、図1に示す
実施例と同様、1系統あたりの容量が設備全体の定格流
量の約33%容量の循環給水ポンプ11〜14の4系統
で構成される。給水ポンプ11〜14は、電動機15〜
18で駆動される。本実施例においては、給水ポンプ1
1,12の流量調整用に流体継手19,20を設けてお
り、流体継手19,20のすくい管の位置を変更するこ
とで給水ポンプ11,12の回転数が制御される。また
給水ポンプ13,14は、増速機24,25を介して電
動機17,18により一定速度で運転される。給水ポン
プ13,14の各吐出側に設けた給水調整弁89,90
の開度を制御することで給水流量を調整する。給水ポン
プ11〜14の前後には、仕切弁81〜88を設けてい
る。4系統のうち、電動機18で駆動される給水ポンプ
14の系統は、待機系統であり通常運転時には待機状態
になっている。
Similar to the embodiment shown in FIG. 1, the target reactor water supply equipment is composed of four systems of circulating water supply pumps 11 to 14 having a capacity per system of about 33% of the rated flow rate of the entire equipment. It The water supply pumps 11 to 14 are electric motors 15 to
Driven by 18. In this embodiment, the water supply pump 1
The fluid couplings 19 and 20 are provided for adjusting the flow rates of the fluid couplings 1 and 12, and the rotational speeds of the water supply pumps 11 and 12 are controlled by changing the positions of the rake pipes of the fluid couplings 19 and 20. Further, the water supply pumps 13 and 14 are operated at a constant speed by the electric motors 17 and 18 via the speed increasers 24 and 25. Water supply adjusting valves 89, 90 provided on the discharge sides of the water supply pumps 13, 14
The feed water flow rate is adjusted by controlling the opening degree of. Gate valves 81 to 88 are provided before and after the water supply pumps 11 to 14, respectively. Of the four systems, the system of the water supply pump 14 driven by the electric motor 18 is a standby system and is in a standby state during normal operation.

【0034】本実施例は、図6に示すように給水流量,
原子炉水位,主蒸気流量の3要素をもとに原子炉水位を
制御する給水制御系を備え、水位制御器の信号から流体
継手のすくい管位置制御回路と給水調整弁制御回路を有
する。この給水制御系は、原子炉の運転モード(起動停
止,通常運転)に応じて、原子炉水位のみの単要素制御
と上記の3要素制御を切り換えることができる。
In this embodiment, as shown in FIG.
It is equipped with a feedwater control system that controls the reactor water level based on the three elements of the reactor water level and the main steam flow rate, and has a rake pipe position control circuit for the fluid coupling and a feedwater control valve control circuit based on the signal from the water level controller. This water supply control system can switch the single element control of only the reactor water level and the above three element control according to the operation mode (start-stop, normal operation) of the reactor.

【0035】次に、本実施例における運転について説明
する。まず、原子炉起動時には、電動機18で駆動され
る給水ポンプ14の系統を使用する。給水ポンプ14を
定速で運転し、給水調整弁90の開度を調整することで
徐々に給水流量を増加させる。この際、何らかの原因で
給水ポンプ14の系統が起動できない場合でも、電動機
17で駆動される給水ポンプ13の系統を起動して、給
水調整弁89の開度を調整することで徐々に給水流量を
増加させることができる。このように、給水調整弁を備
えた系統が2系統あるので、給水ポンプの起動失敗が回
避でき、原子炉の起動時の信頼性が向上する。
Next, the operation in this embodiment will be described. First, at the time of starting the reactor, the system of the feed water pump 14 driven by the electric motor 18 is used. The water supply pump 14 is operated at a constant speed, and the opening of the water supply adjusting valve 90 is adjusted to gradually increase the water supply flow rate. At this time, even if the system of the water supply pump 14 cannot be started for some reason, the system of the water supply pump 13 driven by the electric motor 17 is started, and the opening of the water supply adjusting valve 89 is adjusted to gradually increase the water supply flow rate. Can be increased. As described above, since there are two systems provided with the water supply regulating valve, failure to start the water supply pump can be avoided, and reliability at the time of starting the reactor is improved.

【0036】原子炉出力が、約10%に達した時点で、
電動機17で駆動される給水ポンプ13の系統も運転
し、給水調整弁89の開度を調整し、さらに給水流量を
増加させる。このような原子炉低出力時には、図6に示
した給水制御系においては、原子炉水位のみによる単要
素制御を行い、給水調整弁89,90の開度を制御し、
給水流量を調整する。
At the time when the reactor power reaches about 10%,
The system of the water supply pump 13 driven by the electric motor 17 is also operated, the opening degree of the water supply adjusting valve 89 is adjusted, and the water supply flow rate is further increased. In such a low reactor power output, in the feed water control system shown in FIG. 6, single element control is performed only by the reactor water level to control the opening of the feed water adjusting valves 89 and 90.
Adjust the water supply flow rate.

【0037】原子炉出力が上昇し、電動機15,16で
駆動される給水ポンプ11,12が、流体継手19,2
0によって安定に可変速運転できる出力(例えば30〜
40%)に達した時点で、給水ポンプ11,12の系統
を運転するとともに、給水ポンプ14の系統の停止操作
を開始する。これ以降は、給水ポンプ13の系統の給水
調整弁89を全開とし、給水ポンプ11,12の回転数
を上昇させることにより定格の給水流量まで増加させ、
約33%×3系統の通常運転状態に移行させる。
The feedwater pumps 11, 12 driven by the electric motors 15, 16 are connected to the fluid couplings 19, 2 as the reactor output increases.
Output that enables stable variable speed operation by 0 (for example, 30 to
40%), the system of the water supply pumps 11 and 12 is operated and the stop operation of the system of the water supply pump 14 is started. After that, the water supply regulating valve 89 of the system of the water supply pump 13 is fully opened, and the number of rotations of the water supply pumps 11 and 12 is increased to increase the rated water supply flow rate.
Approximately 33% x 3 systems are transferred to the normal operating state.

【0038】通常運転中は、常用として流体継手を用い
て可変速で給水ポンプを運転する2系統と定速で給水ポ
ンプを運転する1系統(流量は給水調整弁89で制御)
を組み合わせて運転しているので、起動直後の低流量状
態から定格流量まで給水流量をスムーズに変化させるこ
とができる。更に、給水ポンプの駆動方式について多様
化が図れており、給水設備の信頼性が向上する。
During normal operation, two systems are normally used to operate the water supply pump at a variable speed using the fluid coupling, and one system is operated to operate the water supply pump at a constant speed (the flow rate is controlled by the water supply adjusting valve 89).
Since they are operated in combination, the feed water flow rate can be smoothly changed from the low flow rate state immediately after startup to the rated flow rate. Furthermore, the drive system of the water supply pump is diversified, and the reliability of the water supply equipment is improved.

【0039】通常運転中に、原子炉出力の変動が生じ、
原子炉水位が変動した場合には、図6に示す給水制御系
では、原子炉水位,主蒸気流量,給水流量の3要素制御
を行って、水位設定値を満足するように給水流量を制御
する。この際、給水ポンプ11,12の系統に備えられ
た流体継手19,20のすくい管位置制御を、給水ポン
プ13の系統の給水調整弁89の開度制御に優先して実
施する。これにより、給水調整弁89は通常時は全開と
する運転が可能となり、給水調整弁89での動力損失を
低減するとともに、弁の振動などによる故障を防止する
ことができる。
During normal operation, fluctuations in reactor output occur,
When the reactor water level fluctuates, the feedwater control system shown in FIG. 6 controls the reactor water level, the main steam flow rate, and the feedwater flow rate to control the feedwater flow rate so as to satisfy the water level set value. . At this time, the rake pipe position control of the fluid couplings 19 and 20 provided in the system of the water supply pumps 11 and 12 is performed with priority over the opening control of the water supply adjustment valve 89 of the system of the water supply pump 13. As a result, the water supply adjusting valve 89 can be operated to be fully opened in the normal state, so that the power loss in the water supply adjusting valve 89 can be reduced and the failure due to the vibration of the valve can be prevented.

【0040】また、通常運転中に稼動している3系統の
給水ポンプ11〜13のうち、何らかの原因で給水ポン
プ1台がトリップした場合には、図1の実施例と同様、
待機状態にある給水ポンプ14の系統を起動する。待機
系の給水ポンプ14と給水調整弁90により、原子炉の
スクラムレベル水位に至るような大幅な水位低下が抑制
できるので、給水ポンプ1台トリップ時の場合でも、原
子炉の運転が継続でき原子炉設備の稼働率が向上する。
If one of the three system water supply pumps 11 to 13 operating during normal operation trips for some reason, as in the embodiment of FIG.
The system of the water supply pump 14 in the standby state is started. The standby water supply pump 14 and the water supply adjustment valve 90 can prevent a significant decrease in the water level that would reach the scrum level water level of the reactor, so that the operation of the reactor can be continued even when one water supply pump trips. The operating rate of furnace equipment is improved.

【0041】本実施例は、待機系統以外に、常用系統に
流量調整弁で給水流量を制御する系統を1系統設けてい
るので、原子炉の起動時に待機系統の給水ポンプ14が
異常により起動しない場合、その常用系統の給水ポンプ
13を起動して、前述の実施例と同様に、原子炉起動時
の低流量時に制御性の良い流量調整弁89の開度制御に
より、給水流量を安定に制御することができる。原子炉
の通常運転時に、流量調整弁で制御する1系統の給水系
統を用いているので、その分、前述の実施例よりも電気
エネルギーの利用効率は低くなるが、給水ポンプの回転
数を制御する給水系統が2系統使用されるので、電気エ
ネルギーの利用効率は高い。
In the present embodiment, in addition to the standby system, one system for controlling the feed water flow rate by the flow rate adjusting valve is provided in the regular system, so that the water supply pump 14 of the standby system does not start due to an abnormality when the reactor is started. In this case, the feed water pump 13 of the regular system is started, and the feed water flow rate is stably controlled by controlling the opening degree of the flow rate adjusting valve 89 having good controllability at the time of low flow rate at the time of starting the reactor, as in the above-described embodiment. can do. At the time of normal operation of the nuclear reactor, since one water supply system controlled by the flow rate adjusting valve is used, the utilization efficiency of electric energy is lower than that of the above-mentioned embodiment, but the rotation speed of the water supply pump is controlled. Since two water supply systems are used, the utilization efficiency of electric energy is high.

【0042】このように、本実施例では、約33%×4
系統の電動機駆動の給水ポンプ(2系統の給水ポンプは
流体継手制御による可変速運転方式、他の2系統の給水
ポンプは定速運転方式)で原子炉給水設備を構成したこ
とにより、給水ポンプの標準化が可能となるとともに、
電動機動力の過度な増大を抑制できる。
Thus, in this embodiment, about 33% × 4
The water supply pump of the system is driven by a motor (two system water supply pumps are variable speed operation system by fluid coupling control, the other two system water supply pumps are constant speed operation system). Standardization is possible,
It is possible to suppress an excessive increase in motor power.

【0043】また、従来の設備に比べ電動機2基と流体
継手2基の物量が増加するが、タービン駆動給水ポンプ
に付随するタービン2基や蒸気配管・弁を削除できる。
このため、タービン建屋内における給水ポンプ配置設計
での自由度や給水設備の保守性が向上するとともに、給
水設備の合理化を図ることができる。
Although the quantity of the electric motors and the two fluid couplings is increased as compared with the conventional equipment, the two turbines and the steam pipes / valves associated with the turbine driven water feed pump can be eliminated.
For this reason, the degree of freedom in designing the arrangement of the water supply pumps in the turbine building and the maintainability of the water supply equipment are improved, and the water supply equipment can be rationalized.

【0044】運転性に関しても、給水調整弁を備えた系
統が2系統あるので、原子炉の起動時における給水ポン
プの起動失敗を回避できる。
Regarding the operability as well, since there are two systems provided with the water supply regulating valve, it is possible to avoid a failure in starting the water supply pump at the time of starting the reactor.

【0045】また、常用系統として流体継手制御により
可変速運転される系統と給水調整弁制御により定速運転
される系統を組み合わせて運転するので、給水ポンプの
駆動方式についても多様化が図れており、給水設備の信
頼性が向上する。
Further, as the normal system, the system which is operated at a variable speed by the fluid coupling control and the system which is operated at a constant speed by the water supply adjusting valve control are operated in combination, so that the drive system of the water supply pump is also diversified. , The reliability of water supply equipment is improved.

【0046】これに加え、図1,図4の実施例と同様給
水ポンプの1系統を予備機としているので、常用機の給
水ポンプ1台トリップ時においても、スクラムレベルに
達するような原子炉水位の大幅な低下を抑制でき、原子
炉設備の稼働率向上に寄与する。
In addition to this, as in the embodiment of FIGS. 1 and 4, one system of the water supply pump is used as a standby machine, so even when one water supply pump of a regular machine trips, the reactor water level that will reach the scrum level. It is possible to suppress a drastic decrease in fuel consumption and contribute to the improvement of the operating rate of reactor equipment.

【0047】本発明の他の一実施例を、図7により説明
する。対象とする原子炉給水設備は、図5に示す実施例
と同様、1系統あたりの容量が定格流量の約33%容量
の循環給水ポンプ11〜14の4系統で構成される。本
実施例においては、給水ポンプ11,12を駆動する電
動機15,16の回転数制御に、電動機15,16に接
続したサイリスタ21,22を用いた構成としている。
サイリスタ21,22は、給水ポンプの回転数を可変に
制御する手段である。これら以外の給水設備の構成は、
図5に示した実施例と同様である。本実施例において
も、図6に示したものと同様の給水制御系を備えてい
る。
Another embodiment of the present invention will be described with reference to FIG. Similar to the embodiment shown in FIG. 5, the target reactor water supply equipment is composed of four systems of circulating water supply pumps 11 to 14 each having a capacity of about 33% of the rated flow rate. In this embodiment, the thyristors 21 and 22 connected to the electric motors 15 and 16 are used to control the rotational speeds of the electric motors 15 and 16 that drive the water supply pumps 11 and 12.
The thyristors 21 and 22 are means for variably controlling the rotation speed of the water supply pump. The structure of the water supply equipment other than these is
This is similar to the embodiment shown in FIG. Also in this embodiment, a water supply control system similar to that shown in FIG. 6 is provided.

【0048】本実施例の動作は、図5に示した実施例と
同様であるため、説明は省略する。本発明の他の一実施
例を、図8により説明する。対象とする原子炉給水設備
は、1系統当りの容量が定格流量の約25%容量の給水
ポンプ31〜35の5系統で構成される。給水ポンプ3
1〜33は、流体継手41〜43を介して電動機36〜
38で駆動される。給水ポンプ34,35は、増速機
9,10を介して電動機39,40で駆動される。給水
ポンプ31〜35の前後には、仕切弁91〜100を、
給水ポンプ34,35の吐出側には、給水調整弁10
1,102を設けている。5系統のうち、電動機40で
駆動される給水ポンプ35の系統は、通常運転時には待
機状態とする。
Since the operation of this embodiment is the same as that of the embodiment shown in FIG. 5, its explanation is omitted. Another embodiment of the present invention will be described with reference to FIG. The target reactor water supply facility is composed of five systems of water supply pumps 31 to 35 each having a capacity of about 25% of the rated flow rate. Water pump 3
1 to 33 are electric motors 36 to 36 via fluid couplings 41 to 43.
Driven at 38. The water supply pumps 34, 35 are driven by electric motors 39, 40 via the speed increasing gears 9, 10. Gate valves 91 to 100 are installed in front of and behind the water supply pumps 31 to 35, respectively.
On the discharge side of the water supply pumps 34, 35, the water supply adjustment valve 10
1, 102 are provided. Of the five systems, the system of the water supply pump 35 driven by the electric motor 40 is in a standby state during normal operation.

【0049】本実施例も、図6に示したものとほぼ同様
の給水制御系を備えている。
This embodiment also has a water supply control system almost similar to that shown in FIG.

【0050】本実施例の設備と、タービン駆動給水ポン
プと電動機駆動給水ポンプを組み合わせた従来の原子炉
給水設備を比較すると、給水ポンプの数が4基から5基
に増加するが、給水ポンプの総設備容量は133%から
125%に低減し、かつ駆動する電動機動力は、従来の
待機系統の電動機駆動給水ポンプの場合とほぼ等しくで
きるので、従来用いていたものとほぼ同じ電動機が使用
できる。なお、本実施例の動作は、図5,図7に示した
実施例とほぼ同様である。
Comparing the equipment of this embodiment with a conventional reactor water supply equipment in which a turbine driven water supply pump and an electric motor driven water supply pump are combined, the number of water supply pumps increases from four to five. The total installed capacity is reduced from 133% to 125%, and the driving electric power of the electric motor can be made almost equal to that of the electric motor driven feed pump of the conventional standby system, so that the almost same electric motor as that used conventionally can be used. The operation of this embodiment is almost the same as that of the embodiment shown in FIGS.

【0051】[0051]

【発明の効果】請求項1の発明によれば、各給水ポンプ
の容量をほぼ等しく設定したことにより、各系統におい
て同一仕様の給水ポンプを使用できるようになり、給水
ポンプの標準化が可能になるとともに、保守点検時に使
用する予備の部品も共有化できる。また、大型炉に適用
する場合においても、製作実績範囲内の電動機で対応で
きるため、電動機物量の過度な増大を抑制できる。
According to the invention of claim 1, the water supply pumps having the same specifications can be used in each system by setting the capacities of the water supply pumps to be substantially equal, and the water supply pump can be standardized. At the same time, spare parts used during maintenance can be shared. Further, even when it is applied to a large-scale furnace, an electric motor within the production performance range can be used, so that an excessive increase in the electric motor quantity can be suppressed.

【0052】さらに、従来のタービン駆動給水ポンプと
電動機駆動給水ポンプの組み合わせとは異なり、全ての
給水ポンプを電動機駆動としたことにより、タービン駆
動給水ポンプ用の蒸気が不要となり蒸気配管が削除でき
る。これに伴って、給水ポンプを主タービン及び主復水
器から分離して放射線量が低い領域に配置でき、配置上
の自由度が向上するとともに、しゃへい設計上の要求が
低減するため、運転中機器への接近性が改善され給水設
備の保守性が向上する。
Further, unlike the conventional combination of the turbine driven water feed pump and the electric motor driven water feed pump, since all the water feed pumps are driven by the electric motor, the steam for the turbine driven water feed pump becomes unnecessary and the steam pipe can be deleted. Along with this, the water supply pump can be separated from the main turbine and the main condenser in the area where the radiation dose is low, which improves the degree of freedom in arrangement and reduces the requirements for shielding design. The accessibility to the equipment is improved and the maintainability of the water supply facility is improved.

【0053】電動機やポンプの回転数を調整する機器の
部品数は、タービン駆動方式に比べ少なく、保守点検作
業量も低減する。
Compared with the turbine drive system, the number of parts of the device for adjusting the rotation speed of the electric motor and pump is smaller, and the maintenance and inspection work amount is also reduced.

【0054】また、可変速で運転するポンプを備えた常
用系と、給水流量調整弁を備えた待機系等系統を組み合
わせて運転して、起動直後の低流量状態から定格流量ま
でスムーズに変化させることができる。
Further, a normal system equipped with a pump operating at a variable speed and a standby system equipped with a feed water flow rate adjusting valve are operated in combination to smoothly change from a low flow state immediately after startup to a rated flow rate. be able to.

【0055】請求項2の発明によれば、請求項1の発明
による効果に加えて、通常運転状態の範囲内において
は、可変速運転される給水ポンプの回転数制御を、定速
運転される給水ポンプを有する系統の給水調整弁の開度
制御より優先的に実施することにより、給水調整弁は通
常時は全開とする運転が可能となり、給水調整弁による
圧力損失を低減するとともに、弁の振動などによる故障
を防止することができ、設備の信頼性が向上する。
According to the invention of claim 2, in addition to the effect by the invention of claim 1, in the range of the normal operation state, the rotation speed control of the feed pump which is operated at a variable speed is operated at a constant speed. By prioritizing the opening control of the water supply regulating valve in the system with a water supply pump, the water supply regulating valve can be operated in a fully open state during normal operation, reducing the pressure loss due to the water supply regulating valve and reducing the valve It is possible to prevent breakdown due to vibration and improve the reliability of equipment.

【0056】請求項3又は請求項5の発明によれば、請
求項1又は請求項2の発明による効果に加えて、ポンプ
回転数可変手段が、電動機の回転数制御手段、あるいは
電動機から給水ポンプに伝える回転数を制御する手段で
あることにより、原子炉出力上昇時等の運転範囲におい
て、回転数を容易に変速させることができるため、原子
炉給水設備の運転性が安定する。
According to the third or fifth aspect of the invention, in addition to the effect of the first or second aspect of the invention, the pump rotation speed varying means is the rotation speed control means of the electric motor or the water supply pump from the electric motor. Since it is a means for controlling the number of revolutions transmitted to the engine, the number of revolutions can be easily changed in the operating range such as when the reactor output increases, so that the operability of the reactor water supply facility is stabilized.

【0057】請求項7の発明によれば、請求項1,請求
項2,請求項3及び請求項5のいずれか一項の発明によ
る効果に加えて、待機系統のポンプを定速駆動の簡単な
構成とすることができる。
According to the invention of claim 7, in addition to the effect of the invention of any one of claims 1, 2, 3 and 5, the pump of the standby system can be easily driven at a constant speed. It can be configured in various ways.

【図面の簡単な説明】[Brief description of drawings]

【図1】本発明の第1実施例による原子炉給水設備の構
成図である。
FIG. 1 is a configuration diagram of a reactor water supply facility according to a first embodiment of the present invention.

【図2】従来の原子炉給水設備の構成図である。FIG. 2 is a configuration diagram of a conventional reactor water supply facility.

【図3】図1の原子炉給水設備を適用した沸騰水型原子
炉プラントの概略構成図である。
3 is a schematic configuration diagram of a boiling water reactor plant to which the reactor water supply system of FIG. 1 is applied.

【図4】図1の構成におけるポンプトリップ事故時での
原子炉給水設備の状態を示す説明図である。
FIG. 4 is an explanatory diagram showing a state of reactor water supply equipment at the time of a pump trip accident in the configuration of FIG. 1.

【図5】本発明の第2実施例である原子炉給水設備の構
成図である。
FIG. 5 is a configuration diagram of a reactor water supply facility according to a second embodiment of the present invention.

【図6】図5の原子炉給水設備に適用される制御系ブロ
ック線図である。
FIG. 6 is a block diagram of a control system applied to the reactor water supply system of FIG.

【図7】本発明の第3実施例である原子炉給水設備の構
成図である。
FIG. 7 is a configuration diagram of a reactor water supply facility according to a third embodiment of the present invention.

【図8】本発明の第4実施例である原子炉給水設備の構
成図である。
FIG. 8 is a configuration diagram of a reactor water supply facility according to a fourth embodiment of the present invention.

【符号の説明】[Explanation of symbols]

1〜4,11〜14,31〜35…給水ポンプ、5,6
…蒸気タービン、7,8,15〜18,36〜40…電
動機、9,10,23〜25,44、45…増速機、1
9〜22、41〜43…流体継手、26,27…サイリ
スタ、51…原子炉、52…高圧タービン、53…湿分
分離加熱器、54…低圧タービン、55…復水器、56
…復水ポンプ、57…低圧給水加熱器、58…高圧給水
加熱器、59…給水配管、60…主蒸気配管、61〜6
8,81〜88,91〜100…仕切弁、69,70,
89,90,101,102…給水調整弁、71〜7
4,76…流量計、75…水位計、77…給水制御系。
1-4, 11-14, 31-35 ... Water supply pump, 5, 6
... Steam turbine, 7, 8, 15-18, 36-40 ... Electric motor, 9, 10, 23-25, 44, 45 ... Speed increaser, 1
9-22, 41-43 ... Fluid coupling, 26, 27 ... Thyristor, 51 ... Reactor, 52 ... High pressure turbine, 53 ... Moisture separation heater, 54 ... Low pressure turbine, 55 ... Condenser, 56
... Condensate pump, 57 ... Low-pressure feed water heater, 58 ... High-pressure feed water heater, 59 ... Water supply pipe, 60 ... Main steam pipe, 61 to 6
8, 81-88, 91-100 ... Gate valve, 69, 70,
89, 90, 101, 102 ... Water supply adjusting valve, 71 to 7
4, 76 ... Flowmeter, 75 ... Water level gauge, 77 ... Water supply control system.

Claims (7)

【特許請求の範囲】[Claims] 【請求項1】給水ポンプ及び給水流量調整弁を含む1系
統の待機系統、及び給水ポンプを含む少なくとも3系統
の常用系統を原子炉給水経路に並列に装備した原子炉給
水設備であって、前記各給水ポンプは電動機で駆動され
る給水ポンプであって互いにほぼ等しい容量を有する給
水ポンプであり、前記常用系統のうち少なくとも2系統
は、前記給水ポンプの回転数を制御するポンプ回転数可
変手段を備えていることを特徴とした原子炉給水設備。
1. A reactor water supply facility comprising one standby system including a water supply pump and a water supply flow rate adjusting valve, and at least three service systems including a water supply pump installed in parallel in a reactor water supply path, comprising: Each of the water supply pumps is a water supply pump driven by an electric motor and has a substantially equal capacity to each other. At least two systems of the regular system include pump rotation speed varying means for controlling the rotation speed of the water supply pump. Reactor water supply facility characterized by being equipped.
【請求項2】通常運転状態の範囲において、前記常用系
統の前記給水ポンプの回転数の調整を、待機系統の給水
流量調整弁の開度制御より優先的に実施する給水制御手
段を有する請求項1の原子炉給水設備。
2. A water supply control means for performing the adjustment of the rotation speed of the water supply pump of the normal system preferentially to the opening control of the water supply flow rate adjusting valve of the standby system in the range of the normal operation state. 1 reactor water supply equipment.
【請求項3】前記ポンプ回転数可変手段が、前記電動機
の回転数を制御する手段である請求項1又は請求項2の
原子炉給水設備。
3. The reactor water supply facility according to claim 1, wherein the pump rotation speed varying means is means for controlling the rotation speed of the electric motor.
【請求項4】前記回転数制御手段がサイリスタである請
求項3の原子炉給水設備。
4. The reactor water supply facility according to claim 3, wherein the rotation speed control means is a thyristor.
【請求項5】前記ポンプ回転数可変手段が、前記電動機
と前記給水ポンプとの間に設けられかつ前記電動機から
前記給水ポンプに伝える回転数を制御する手段である請
求項1又は請求項2の原子炉給水設備。
5. The pump rotational speed varying means is a means that is provided between the electric motor and the water feed pump and that controls the rotational speed transmitted from the electric motor to the water feed pump. Reactor water supply facility.
【請求項6】前記回転数制御手段が流体継手である請求
項5の原子炉給水設備。
6. The reactor water supply facility according to claim 5, wherein the rotation speed control means is a fluid coupling.
【請求項7】前記待機系統の給水ポンプは前記電動機に
より回転数を一定にして駆動される給水ポンプである請
求項1,請求項2,請求項3又は請求項5の原子炉給水
設備。
7. The reactor water supply equipment according to claim 1, wherein the water supply pump of the standby system is a water supply pump driven by the electric motor at a constant rotation speed.
JP7210425A 1994-08-19 1995-08-18 Reactor water supply facility Pending JPH08110392A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP7210425A JPH08110392A (en) 1994-08-19 1995-08-18 Reactor water supply facility

Applications Claiming Priority (3)

Application Number Priority Date Filing Date Title
JP6-195132 1994-08-19
JP19513294 1994-08-19
JP7210425A JPH08110392A (en) 1994-08-19 1995-08-18 Reactor water supply facility

Publications (1)

Publication Number Publication Date
JPH08110392A true JPH08110392A (en) 1996-04-30

Family

ID=26508942

Family Applications (1)

Application Number Title Priority Date Filing Date
JP7210425A Pending JPH08110392A (en) 1994-08-19 1995-08-18 Reactor water supply facility

Country Status (1)

Country Link
JP (1) JPH08110392A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2008051805A (en) * 2006-07-28 2008-03-06 Toshiba Corp Water supply control device, nuclear power plant, and water supply control method
US8467491B2 (en) 2006-07-28 2013-06-18 Kabushiki Kaisha Toshiba Feedwater controller, nuclear power plant and method for controlling feedwater

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2008051805A (en) * 2006-07-28 2008-03-06 Toshiba Corp Water supply control device, nuclear power plant, and water supply control method
US8467491B2 (en) 2006-07-28 2013-06-18 Kabushiki Kaisha Toshiba Feedwater controller, nuclear power plant and method for controlling feedwater

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