JPS6159479B2 - - Google Patents
Info
- Publication number
- JPS6159479B2 JPS6159479B2 JP53118411A JP11841178A JPS6159479B2 JP S6159479 B2 JPS6159479 B2 JP S6159479B2 JP 53118411 A JP53118411 A JP 53118411A JP 11841178 A JP11841178 A JP 11841178A JP S6159479 B2 JPS6159479 B2 JP S6159479B2
- Authority
- JP
- Japan
- Prior art keywords
- water supply
- steam
- pump
- reactor
- pumps
- 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
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 45
- 206010073306 Exposure to radiation Diseases 0.000 description 4
- 238000010586 diagram Methods 0.000 description 2
- 238000007689 inspection Methods 0.000 description 2
- 238000012423 maintenance Methods 0.000 description 2
- 230000007423 decrease Effects 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 239000008400 supply water Substances 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
- Structures Of Non-Positive Displacement Pumps (AREA)
- Control Of Non-Positive-Displacement Pumps (AREA)
Description
【発明の詳細な説明】
本発明は、例えばB.W.Rのような原子力発電ブ
ラントにおける給水装置に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a water supply system in a nuclear power plant, such as a BWR.
従来、この種の原子力発電プラントは、第１図
に示されるように、原子炉ａの炉心で熱交換して
発生した高温高圧の蒸気を主蒸気管ｂの主蒸気止
弁ｃを通して高圧タービンｄに移送し、この高圧
タービンｄを駆動し、さらに、この高圧タービン
ｄから流出した蒸気をモイスチヤセパレータｅを
介して低圧タービンｆを駆動し、仕事を了えた蒸
気を復水器ｇで復水し、しかる後、この復水を複
数の復水ポンプｈで給水管１に圧送するようにし
たものである。 Conventionally, in this type of nuclear power plant, as shown in Fig. 1, high-temperature, high-pressure steam generated by heat exchange in the core of a nuclear reactor a is passed through a main steam stop valve c of a main steam pipe b to a high-pressure turbine d. The steam flowing out from the high-pressure turbine d is passed through a moisture separator e to drive a low-pressure turbine f, and the steam that has completed its work is condensed in a condenser g. After that, this condensate is pumped to the water supply pipe 1 by a plurality of condensate pumps h.
又一方、上記給水管ｉ上には、起動及び停止時
に使用される各給水ポンプj1，j2及び各流量制御
弁k1，k2と通常運転時に使用される各給水タービ
ンl1，l2及びこれによつて駆動される各タービン
駆動ポンプm1，m2が並設されている。従つて、
各復水ポンプｈで圧送される給水は、起動又は停
止時には、各給水ポンプj1，j2及び各流量制御弁
k1，k2を通して原子炉ａの炉心に給水される。他
方、通常運転時に達すると、上記復水ポンプｈの
給水は、上記各タービン駆動ポンプm1，m2によ
つて原子炉へ給水するようになつている。 On the other hand, on the water supply pipe i, there are water supply pumps j 1 , j 2 and flow control valves k 1 , k 2 used during startup and stop, and water supply turbines l 1 , l used during normal operation. 2 and turbine-driven pumps m 1 and m 2 driven thereby are arranged in parallel. Therefore,
The water supplied under pressure by each condensate pump h is transferred to each water supply pump j 1 , j 2 and each flow rate control valve when starting or stopping.
Water is supplied to the core of reactor a through k 1 and k 2 . On the other hand, when normal operation is reached, water from the condensate pump h is supplied to the reactor by the turbine-driven pumps m 1 and m 2 .
しかしながら、上記原子力発電プラントの給水
装置は、(1)通常運転時、原子炉の発生蒸気の一部
を利用して各タービン駆動ポンプm1，m2を駆動
する関係上、放射能を含む蒸気の漏洩又は保守点
検時に被爆するおそれがあり、これらの安全性を
確保するための配管工事が複雑になると共に、(2)
発電プラントの起動、及び停止と通電運転時の各
ポンプj1j2、m1，m2の分担のために、４台の巨大
なポンプを必要となり、給水設備が高価になる。
(3)特に、起動及び停止に使用される各給水ポンプ
j1，j2は吐出側に各調整弁k1，k2を附設する関係
上、ポンプ効率を低下し、しかも各調整弁k1，k2
の保守点検時に放射能による被爆を受けるおそれ
がある。 However, the above-mentioned water supply system of a nuclear power plant has the following drawbacks: (1) During normal operation, a portion of the steam generated by the reactor is used to drive each turbine-driven pump m 1 and m 2 ; therefore, steam containing radioactivity is used. There is a risk of radiation leakage or radiation exposure during maintenance inspections, which complicates piping work to ensure safety, and (2)
Four gigantic pumps are required to handle each pump j 1 j 2 , m 1 , m 2 during startup, shutdown, and energized operation of the power plant, making the water supply equipment expensive.
(3) In particular, each water pump used for starting and stopping
Since the adjustment valves k 1 and k 2 are attached to the discharge side of j 1 and j 2 , the pump efficiency decreases, and the adjustment valves k 1 and k 2
There is a risk of exposure to radioactivity during maintenance and inspection.
本発明は、上述した点に鑑み、復水ポンプ及び
原子炉を繋ぐ給水管路上に、可変周波数のサイリ
スタインバータによる各モータで駆動する給水ポ
ンプを並設し、これにより原子炉の高圧蒸気を使
用せずに、しかも被爆を受けることなく、安全に
給水すると共に、給水ポンプの運転効率を向上
し、併せて構成を簡素化して安価にすることを目
的とする原子力発電プラントにおける給水装置を
提供するにある。 In view of the above-mentioned points, the present invention provides a water supply pump driven by each motor using a variable frequency thyristor inverter in parallel on the water supply pipe connecting the condensate pump and the nuclear reactor, thereby using the high pressure steam of the nuclear reactor. To provide a water supply device in a nuclear power plant, which aims to safely supply water without causing radiation exposure and exposure to radiation, improve the operating efficiency of a water supply pump, and simplify the configuration and reduce the cost. It is in.
以下、本発明を図示の一実施例について説明す
る。 Hereinafter, the present invention will be described with reference to an illustrated embodiment.
第２図において、符号１は例えばB.W.Rのよう
な原子炉であつて、この原子炉１の炉心上部には
主蒸気管２の一端が接続しており、この蒸気管２
の一端が接続しており、この蒸気管２の他端には
高圧蒸気タービン３が主蒸気止弁４を介して繋が
れている。又、この高圧蒸気タービン３の蒸気流
出側にはモイスチヤセパレータ５を通して低圧タ
ービン６が設けられており、この低圧タービン６
の一部には復水器７が附設されている。さらにこ
の復水器７の吐出側には複数の復水ポンプ８が並
設されており、この各復水ポンプ８及び上記原子
炉１との間には給水管９が接続されている。さら
に、上記給水管９の管路上には複数の給水ポンプ
１０が並設されており、この各給水ポンプ１０に
は各モータ１１がそれぞれ直結して駆動し得るよ
うになつており、しかも、この各モータ１１には
可変周波数の各サイリスタインバータ１２が図示
されない電源に接続して設けられている。 In FIG. 2, reference numeral 1 denotes a nuclear reactor such as a BWR, and one end of a main steam pipe 2 is connected to the upper part of the core of the reactor 1.
One end of the steam pipe 2 is connected to the other end of the steam pipe 2, and a high pressure steam turbine 3 is connected to the other end of the steam pipe 2 via a main steam stop valve 4. Further, a low pressure turbine 6 is provided on the steam outflow side of the high pressure steam turbine 3 through a moisture separator 5.
A condenser 7 is attached to a part of the condenser. Furthermore, a plurality of condensate pumps 8 are arranged in parallel on the discharge side of the condenser 7, and a water supply pipe 9 is connected between each of the condensate pumps 8 and the nuclear reactor 1. Further, a plurality of water supply pumps 10 are arranged in parallel on the water supply pipe 9, and each motor 11 is directly connected to each of the water supply pumps 10 so that it can be driven. Each motor 11 is provided with a variable frequency thyristor inverter 12 connected to a power source (not shown).
従つて、上記各給水ポンプ１０の流量は可変周
数数の各サイリスタインバータ１２によつて自由
に制御され、給水流量は原子炉１の必要な流量に
基づいて調整されるから、起動又は停止時及び通
常運転時に蒸気を使用することなく、可変給水す
るようになつている。即ち、本発明による給水装
置は、起動又は停止時及び通常運転時において
も、可変周波数のサイリスタインバータ１２によ
る各モータ１１で駆動する給水ポンプ１０のみで
給水流量を制御するようになつている。 Therefore, the flow rate of each of the feed water pumps 10 is freely controlled by each thyristor inverter 12 with a variable number of cycles, and the feed water flow rate is adjusted based on the required flow rate of the reactor 1, so that when starting or stopping Also, the system is designed to provide variable water supply without using steam during normal operation. That is, in the water supply device according to the present invention, the water supply flow rate is controlled only by the water supply pump 10 driven by each motor 11 using the variable frequency thyristor inverter 12, even when starting or stopping and during normal operation.
従つて今、原子炉１の炉心で熱交換して生じた
高圧蒸気は主蒸気管２の主蒸気止弁４を通して高
圧タービン３に移送され、こゝで高圧タービン３
を駆動し、さらに、この高圧タービン３から流出
した蒸気は、モイスチヤセパレータ５を介して低
圧タービン６を駆動し、仕事を了えた蒸気は復水
器７で復水し、しかる後、各復水ポンプ８が上記
復水を給水管９に圧送する。しかして、この給水
管９の管路上に設けられた各給水ポンプ１０は、
前述したように、起動又は停止及び通常運転時に
おいても、可変周波数のサイリスタインバータ１
２による各モータ１１で駆動されるため、原子炉
１に必要な給水流量を制御して給水するようにな
つている。 Therefore, high-pressure steam generated by heat exchange in the core of the nuclear reactor 1 is transferred to the high-pressure turbine 3 through the main steam stop valve 4 of the main steam pipe 2.
Further, the steam flowing out from the high-pressure turbine 3 drives the low-pressure turbine 6 via the moisture separator 5, and the steam that has finished its work is condensed in the condenser 7. A water pump 8 pumps the condensate into a water supply pipe 9. Therefore, each water supply pump 10 provided on the pipe of this water supply pipe 9,
As mentioned above, the variable frequency thyristor inverter 1
Since the reactor 1 is driven by each motor 11 of the reactor 1, the flow rate of water required for the reactor 1 is controlled and water is supplied.
以上述べたように本発明によれば、復水ポンプ
８及び原子炉１を繋ぐ給水管９に可変周波数のサ
イリスタインバータ１２による各モータ１１で駆
動する各給水ポンプ１０を並設してあるので、従
来、この種の給水装置のように、原子炉の蒸気の
一部を一切使用しないから、タービン駆動の給水
ポンプや給水流量調整弁が不要になり、しかも蒸
気漏洩による放射線被爆をうけるおそれもなくな
り、装置全体を簡素化できるばかりでなく、ポン
プの運転効率を向上できる等の優れた効果を有す
るものである。 As described above, according to the present invention, each water supply pump 10 driven by each motor 11 by a variable frequency thyristor inverter 12 is arranged in parallel in the water supply pipe 9 that connects the condensate pump 8 and the nuclear reactor 1. Conventionally, this type of water supply system does not use any part of the reactor steam, so there is no need for a turbine-driven water supply pump or water supply flow rate adjustment valve, and there is no risk of radiation exposure due to steam leakage. This has excellent effects such as not only simplifying the entire device but also improving the operating efficiency of the pump.
第１図は従来の原子力発電プラントの給水装置
を示す線図、第２図は本発明による原子力発電プ
ラントの給水装置を示す線図である。
１……原子炉、２……主蒸気管、３……高圧タ
ービン、５……モイスチヤセパレータ、６……低
圧タービン、７……復水器、８……復水ポンプ、
９……給水管、１０……給水ポンプ、１１……モ
ータ、１２……サイリスタインバータ。
FIG. 1 is a diagram showing a conventional water supply system for a nuclear power plant, and FIG. 2 is a diagram showing a water supply system for a nuclear power plant according to the present invention. 1... Nuclear reactor, 2... Main steam pipe, 3... High pressure turbine, 5... Moisture separator, 6... Low pressure turbine, 7... Condenser, 8... Condensate pump,
9... Water supply pipe, 10... Water supply pump, 11... Motor, 12... Thyristor inverter.
Claims (1)
給水管に並設されしかも可変周波数のサイリスタ
インバータによる各モータで駆動する各給水ポン
プとよりなる原子力発電プラントの給水装置。1. A water supply system for a nuclear power plant consisting of a water supply pipe that connects a condensate pump and a nuclear reactor, and water supply pumps that are installed in parallel with this water supply pipe and are driven by respective motors using variable frequency thyristor inverters.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP11841178A JPS5544947A (en) | 1978-09-26 | 1978-09-26 | Feedwater device for atomic power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP11841178A JPS5544947A (en) | 1978-09-26 | 1978-09-26 | Feedwater device for atomic power plant |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5544947A JPS5544947A (en) | 1980-03-29 |
| JPS6159479B2 true JPS6159479B2 (en) | 1986-12-16 |
Family
ID=14735973
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP11841178A Granted JPS5544947A (en) | 1978-09-26 | 1978-09-26 | Feedwater device for atomic power plant |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5544947A (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5886644U (en) * | 1981-12-08 | 1983-06-11 | 株式会社東芝 | image forming device |
| US4497569A (en) * | 1982-09-21 | 1985-02-05 | Xerox Corporation | Copy processing system for a reproduction machine |
-
1978
- 1978-09-26 JP JP11841178A patent/JPS5544947A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5544947A (en) | 1980-03-29 |
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