Deprecated: The each() function is deprecated. This message will be suppressed on further calls in /home/zhenxiangba/zhenxiangba.com/public_html/phproxy-improved-master/index.php on line 456
JPS6015209B2 - condensate equipment - Google Patents
[go: Go Back, main page]

JPS6015209B2 - condensate equipment - Google Patents

condensate equipment

Info

Publication number
JPS6015209B2
JPS6015209B2 JP53048361A JP4836178A JPS6015209B2 JP S6015209 B2 JPS6015209 B2 JP S6015209B2 JP 53048361 A JP53048361 A JP 53048361A JP 4836178 A JP4836178 A JP 4836178A JP S6015209 B2 JPS6015209 B2 JP S6015209B2
Authority
JP
Japan
Prior art keywords
condensate
pump
water
pipe
condenser
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
Application number
JP53048361A
Other languages
Japanese (ja)
Other versions
JPS54141903A (en
Inventor
理一郎 北川
勝美 日下部
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.)
Toshiba Corp
Original Assignee
Tokyo Shibaura Electric Co 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 Tokyo Shibaura Electric Co Ltd filed Critical Tokyo Shibaura Electric Co Ltd
Priority to JP53048361A priority Critical patent/JPS6015209B2/en
Publication of JPS54141903A publication Critical patent/JPS54141903A/en
Publication of JPS6015209B2 publication Critical patent/JPS6015209B2/en
Expired 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
    • 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
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Treatment Of Water By Ion Exchange (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 本発明は、例えば原子力発電プラントの復水系の機器お
よび配管の保有する水の排水処理装置に係わり、特に建
設時および定期点検時プラント停止時の復水器ホットゥ
ェルおよび復水管内の水を放射性廃棄物処理系で処理す
ることなく、ポンプを設けて既設の復水浄化装置を介し
て、復水貯蔵槽に回収する系統を有する復水装置に関す
るものである。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to, for example, a wastewater treatment device for water contained in condensate system equipment and piping of a nuclear power plant, and particularly to a condenser hotwell and a condenser water treatment device during construction, periodic inspections, and plant shutdowns. This invention relates to a condensate system having a system for collecting water in a water pipe into a condensate storage tank via an existing condensate purification system using a pump, without treating the water in a radioactive waste treatment system.

ここで復水系は、復水器で凝縮した水を低圧復水ポンプ
、復水浄化装置等を介して原子炉へ供給する系統であり
、放射性廃棄物処理系は、原子力発電プラント内の放射
能を帯びた液体等を浄化処理する装置である。
The condensate system is a system that supplies water condensed in a condenser to the reactor via a low-pressure condensate pump, condensate purification device, etc., and the radioactive waste treatment system is a system that supplies water condensed in a condenser to a nuclear reactor through a low-pressure condensate pump, condensate purification equipment, etc. This is a device that purifies liquids, etc. that are tinged with

従釆の原子力発電プラントでは復水系の排水処理に関し
て次のような問題点があった。
At the nuclear power plant in question, there were the following problems with the treatment of condensate wastewater.

即ち、低圧復水ポンプの吸込側はきわめて高真空でしか
も飽和温度に近い温水を取り扱うため、吸込側に十分な
水頭をもたせキャビテーションの発生を防止し円滑な運
転ができるように考慮しなければならない。このような
観点から復水器ホットゥェル内の水位がある位置まで低
下すると安全のため、低圧復水ポンプの運転を停止して
いる。しかしながら低圧復水ポンプ停止後も、復水器ホ
ットゥェルおよび復水管内に復水が残留し、従来は、こ
の復水の排水は、ポンプを仮設しておこなっていた。こ
のため、数百トンもある復水を排水するのに多大な時間
を要し、かつ完全に排水することが困難であった。また
、仮設ポンプ等の準備等が必要であり、時間的にも経済
的にも効率が悪いという不具合があった。ここで、従来
の復水排水処理系統を第1図によって説明する。
In other words, since the suction side of a low-pressure condensate pump is in an extremely high vacuum and handles hot water close to the saturation temperature, consideration must be given to providing a sufficient water head on the suction side to prevent cavitation and ensure smooth operation. . From this point of view, when the water level in the condenser hotwell drops to a certain level, the operation of the low-pressure condensate pump is stopped for safety reasons. However, even after the low-pressure condensate pump is stopped, condensate remains in the condenser hotwell and condensate pipe, and conventionally, this condensate has been drained by temporarily installing a pump. For this reason, it took a long time to drain hundreds of tons of condensate, and it was difficult to drain it completely. In addition, it is necessary to prepare temporary pumps, etc., and there is a problem that it is inefficient in terms of time and economy. Here, a conventional condensate wastewater treatment system will be explained with reference to FIG.

定期点検等でプラントが停止し、復水器ホットウェル1
内の水位がある位置迄低下すると、低圧復水ポンプ3は
上で述べたような理由から停止する。
The plant stopped due to periodic inspection, etc., and condenser hotwell 1
When the water level in the tank drops to a certain point, the low pressure condensate pump 3 stops for the reasons mentioned above.

復水器ホットウヱル1および復水管2に残留した復水は
、復水管2に接続されている排水管4より機器ドレンサ
ンプタンク17に回収され、仮設したサンプポンプ18
により配管19を通し‐て放射性廃棄物処理系20へ送
水され再使用可能な水に浄化され配管21を通して復水
貯蔵槽15に送水され貯えられていた。
The condensate remaining in the condenser hot water 1 and the condensate pipe 2 is collected into the equipment drain sump tank 17 through the drain pipe 4 connected to the condensate pipe 2, and then transferred to the temporarily installed sump pump 18.
The water was sent to a radioactive waste treatment system 20 through a pipe 19, purified into reusable water, and sent to a condensate storage tank 15 through a pipe 21 for storage.

このような従来の排水処理方法では放射性廃棄物処理系
の容量が小さいため、放射性廃棄物処理系の都合により
排水時期に制限を受けたり、多くの排水量を流すことが
できない等の制約を受けていた。このため復水器ホット
ウェルの点検、清掃に要する所要時間を長時間要してい
た。そこで本発明の目的は、上記の如き従来技術の不便
さを排除し、プラントの定期点検時の復水器ホットウェ
ルおよび復水管内の排水処理を迅速におこない、復水器
ホットウェルの点検、清掃時間の短縮化を計るために既
設の復水浄化装置を使用して、排水を復水貯蔵槽に送水
する系統を有する復水装置を提供することにある。
In such conventional wastewater treatment methods, the capacity of the radioactive waste treatment system is small, so there are restrictions on the timing of drainage due to the radioactive waste treatment system, and the inability to dispose of a large amount of wastewater. Ta. Therefore, it takes a long time to inspect and clean the condenser hot well. Therefore, an object of the present invention is to eliminate the inconveniences of the prior art as described above, to quickly perform wastewater treatment in the condenser hot well and condensate pipe during periodic plant inspections, and to perform inspection of the condenser hot well, An object of the present invention is to provide a condensate device having a system for sending wastewater to a condensate storage tank using an existing condensate purification device in order to shorten cleaning time.

また、本発明の別の目的は、放射性廃棄物処理系と独立
した系統で排水処理をおこなう事によって排水時期およ
び排水量の制限を受けないようにした復水装置を提供す
ることにある。
Another object of the present invention is to provide a condensate system that is free from restrictions on the timing and amount of drainage by treating wastewater in a system independent of the radioactive waste treatment system.

また、本発明の更に別な目的は、放射性廃棄物処理系へ
送る排水の量を低減することにより、放射性廃棄物処理
系が大形化するのを防ぐようにした復水装置を提供する
ことにある。
Still another object of the present invention is to provide a condensation device that prevents the radioactive waste treatment system from increasing in size by reducing the amount of wastewater sent to the radioactive waste treatment system. It is in.

本発明を適用した一実施例を第2図によって説明する。An embodiment to which the present invention is applied will be described with reference to FIG.

第2図において1は復水器ホットウヱル、2は復水管、
3は低圧復水ポンプ「 13は復水浄化装置、15は復
水貯蔵槽である。この構成は従来の系統であって、本発
明では従来の系統に破線で示すバイパス系統16を並設
したものである。即ち、プラント通常運転中は弁5は閉
となっており、復水は、復水管21を通り低圧復水ポン
プ8を介して復水浄化装置13へと送水される。一方、
プラントが停止し、復水器ホットウェル1内の水位があ
る位置迄低下し、低圧復水ポンプ3が停止した後、弁5
を関とし復水器ホットウェルーおよび復水管2内の残留
水を調節弁6を介して排水管4を通りトタンク7に送水
して貯える。このタンク7内に貯えられた水は「ポンプ
8によって、弁9、弁10を介し配管11を通り低圧復
水ポンプ3出口後の配管12に送水される。タンク7へ
の排水の流入量は調節弁6によって調節され、ポンプ8
の起動停止はタンク7内の水位を検出することによって
制御される。配管12に送水された水は、復水浄化装置
13を通り浄化された後、既設の配管14を通り復水貯
蔵槽15へ回収される。
In Figure 2, 1 is the condenser hot well, 2 is the condensate pipe,
3 is a low-pressure condensate pump. 13 is a condensate purification device, and 15 is a condensate storage tank. This configuration is a conventional system, and in the present invention, a bypass system 16 shown by a broken line is installed in parallel with the conventional system. That is, during normal plant operation, the valve 5 is closed, and condensate is sent to the condensate purification device 13 through the condensate pipe 21 and the low-pressure condensate pump 8. On the other hand,
After the plant has stopped, the water level in the condenser hot well 1 has dropped to a certain point, and the low pressure condensate pump 3 has stopped, the valve 5
The residual water in the condenser hotwell and condensate pipe 2 is sent to the tank 7 via the control valve 6 through the drain pipe 4 and stored therein. The water stored in the tank 7 is sent to the pipe 12 after the outlet of the low-pressure condensate pump 3 through the pipe 11 via the valves 9 and 10 by the pump 8.The amount of wastewater flowing into the tank 7 is regulated by control valve 6 and pump 8
Activation/stopping of the tank 7 is controlled by detecting the water level in the tank 7. The water sent to the pipe 12 is purified through the condensate purification device 13 and then collected into the condensate storage tank 15 through the existing pipe 14.

回収される水の水資管理は復水浄化装置出口にある既設
の試料採取系を使用しておこなう事ができる。
Water resource management of the recovered water can be done using the existing sampling system at the outlet of the condensate purifier.

本発明における他の実施例としては、第3図に示すよう
に、第2図におけるタンク7およびポンプ8の代りに、
既設の復水回収槽27および復水回収ポンプ28を使用
する事も考えられる。
As another embodiment of the present invention, as shown in FIG. 3, in place of the tank 7 and pump 8 in FIG.
It is also possible to use the existing condensate recovery tank 27 and condensate recovery pump 28.

以上のように、本発明によれば、原子力発電プラントの
定期定検時等の復水器ホットウェルおよび復水管内の排
水を迅速におこなうことができ、復水器ホットウェルの
点検、清掃に要する時間を短縮できる効果がある。また
、従釆、排水処理に使用していた放射性廃棄物処理系を
使用しないため、排水時期および排水量に制約を受けな
いという効果がある。
As described above, according to the present invention, the condenser hot well and condensate pipe can be drained quickly during periodic inspections of nuclear power plants, and the condenser hot well can be inspected and cleaned. This has the effect of shortening the time required. In addition, since the radioactive waste treatment system used for wastewater treatment is not used, there is no restriction on the timing and amount of drainage.

また、放射性廃棄物処理系へ送る排水の量を低減するこ
とにより、放射性廃棄物処理系が大形化するのを防ぐと
いう効果がある。
Furthermore, by reducing the amount of wastewater sent to the radioactive waste treatment system, there is an effect of preventing the radioactive waste treatment system from becoming larger.

このように、原子力発電プラントの復水装置に、簡単な
、かつ経済的な本発明による系統を迫設することによっ
て、上で述べたような大きな効果があると考えられる。
As described above, it is believed that the above-mentioned great effects can be achieved by installing the simple and economical system according to the present invention in the condensation equipment of a nuclear power plant.

図面の簡単な説明第1図は従来の実施例を示す図、第2
図は本発明の一実施例を示す図、第3図は本発明の他の
実施例を示す図である。
BRIEF DESCRIPTION OF THE DRAWINGS Fig. 1 shows a conventional embodiment, Fig. 2 shows a conventional embodiment;
The figure shows one embodiment of the invention, and FIG. 3 shows another embodiment of the invention.

亀・…・・復水器ホットウェル、3…・・・低圧復水ポ
ンプ、7……タンク、8……ポンプ、13……復水浄化
装置、15……復水貯蔵槽、i6・・・・”バイパス系
統、20・・・…放射性廃棄物処理系。
Turtle... Condenser hot well, 3... Low pressure condensate pump, 7... Tank, 8... Pump, 13... Condensate purification device, 15... Condensate storage tank, i6... ..."Bypass system, 20...Radioactive waste treatment system.

第1図第2図 第3図Figure 1 Figure 2 Figure 3

Claims (1)

【特許請求の範囲】[Claims] 1 復水器ホツトウエルに溜る復水を低圧復水ポンプを
介して復水浄化装置に送る復水装置において、上記低圧
復水ポンプ停止時、復水器ホツトウエルに溜る復水を上
記復水浄化装置に送るバイパス系統を設けたことを特徴
とする復水装置。
1 In a condensing device that sends condensate accumulated in the condenser hot well to the condensate purification device via a low pressure condensate pump, when the low pressure condensate pump is stopped, the condensate accumulated in the condenser hot well is sent to the condensate purification device A condensing device characterized by having a bypass system for sending water to the water.
JP53048361A 1978-04-25 1978-04-25 condensate equipment Expired JPS6015209B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP53048361A JPS6015209B2 (en) 1978-04-25 1978-04-25 condensate equipment

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP53048361A JPS6015209B2 (en) 1978-04-25 1978-04-25 condensate equipment

Publications (2)

Publication Number Publication Date
JPS54141903A JPS54141903A (en) 1979-11-05
JPS6015209B2 true JPS6015209B2 (en) 1985-04-18

Family

ID=12801205

Family Applications (1)

Application Number Title Priority Date Filing Date
JP53048361A Expired JPS6015209B2 (en) 1978-04-25 1978-04-25 condensate equipment

Country Status (1)

Country Link
JP (1) JPS6015209B2 (en)

Families Citing this family (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS57122285A (en) * 1981-01-21 1982-07-30 Hitachi Ltd Condensation system
JPS5815196A (en) * 1981-07-22 1983-01-28 株式会社日立製作所 Steam generating plant
CN102168850B (en) * 2010-12-31 2012-09-26 东莞理文造纸厂有限公司 Papermaking condensate recovery system
CN110986616A (en) * 2019-11-18 2020-04-10 国网河北省电力有限公司电力科学研究院 A device and method for recovering working fluid of a direct air-cooled unit

Also Published As

Publication number Publication date
JPS54141903A (en) 1979-11-05

Similar Documents

Publication Publication Date Title
JPS6015209B2 (en) condensate equipment
US4208298A (en) Process for treating radioactive liquid waste
SU1506252A1 (en) Closed circuit water system
JP2597562B2 (en) Reactor well water purification equipment
JPS62237396A (en) Nuclear-reactor well water drainage system
CN210419328U (en) Concentrated solution discharge system
JPH0344600A (en) Transferring equipment of spent resin
CN221027738U (en) Sealing cover for preventing grid slag leakage of squeezer of sewage treatment plant
JPS6059481B2 (en) Filtration equipment for water supply systems in thermal and nuclear power plants
SU1260463A1 (en) Method of withdrawing waste water
CN222250072U (en) Circulating water drainage warehousing and transportation system
JPH0252297A (en) Purifying facility for nuclear reactor cooling material
CN215137413U (en) Dirt removing filter
JPH01185492A (en) Feed water tubing circulating facility in nuclear power plant
JPH0531202Y2 (en)
JPH0634720Y2 (en) Radioactive waste sump
JPS59206089A (en) Waste liquid treating apparatus
SU1056924A3 (en) Method and device for controlling water conditions in liquid fuel handling systems
JP2004012265A (en) Nuclear power station make-up water facilities
JP2001356189A (en) Radioactive waste liquid treatment equipment
JPS6235033B2 (en)
JP2878707B2 (en) Storage method of feed water heater of nuclear power plant
SU866328A1 (en) Device for removal of condensate
JP2001129547A (en) Supply water desalting apparatus and treatment method of ion exchange resin in supply water desalting apparatus
JPS5930991B2 (en) condenser