JPH046918B2 - - Google Patents
Info
- Publication number
- JPH046918B2 JPH046918B2 JP57202119A JP20211982A JPH046918B2 JP H046918 B2 JPH046918 B2 JP H046918B2 JP 57202119 A JP57202119 A JP 57202119A JP 20211982 A JP20211982 A JP 20211982A JP H046918 B2 JPH046918 B2 JP H046918B2
- Authority
- JP
- Japan
- Prior art keywords
- condensate
- water
- equipment
- rad
- plant
- 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 - Lifetime
Links
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 42
- 238000000746 purification Methods 0.000 claims description 9
- 238000012546 transfer Methods 0.000 claims description 9
- 238000011084 recovery Methods 0.000 claims description 7
- 238000009835 boiling Methods 0.000 claims description 6
- 238000011144 upstream manufacturing Methods 0.000 claims description 2
- 230000005574 cross-species transmission Effects 0.000 description 5
- 238000000034 method Methods 0.000 description 5
- 239000002699 waste material Substances 0.000 description 4
- 238000010586 diagram Methods 0.000 description 3
- 239000007788 liquid Substances 0.000 description 3
- 230000000694 effects Effects 0.000 description 2
- 235000020681 well water Nutrition 0.000 description 2
- 239000002349 well water Substances 0.000 description 2
- 238000007664 blowing Methods 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 238000005342 ion exchange Methods 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 238000012545 processing Methods 0.000 description 1
- 238000011160 research Methods 0.000 description 1
- 239000010802 sludge 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
Description
【発明の詳細な説明】
〔発明の利用分野〕
本発明は沸騰水型原子力プラントに係り、特に
原子力発電における停止時系統水のラド処理量を
低減するのに好適な沸騰水型原子力プラントに関
する。DETAILED DESCRIPTION OF THE INVENTION [Field of Application of the Invention] The present invention relates to a boiling water nuclear power plant, and more particularly to a boiling water nuclear power plant suitable for reducing the amount of Rad throughput of system water during shutdown in nuclear power generation.
従来の原子力発電所、停止時水抜き方法は、系
統水をすべてラド設備によつて処理しており、ラ
ド設備への負担が大きく問題となつている。従来
系統水、水抜き方法を第１図により説明する。
In the conventional method of draining water during shutdown of nuclear power plants, all system water is treated by RAD equipment, which poses a problem as it places a large burden on the RAD equipment. The conventional system water and water draining method will be explained with reference to FIG.
プラント停止後、系統の水抜きは各系統毎に実
施している。 After the plant is shut down, water is drained from each system.
プラント停止後、復水器真空破壊前、給水加熱
器８の胴側、管側の系統水は、高水位調整弁１３
を開にし、真空度を利用して、ホツトウエル４へ
ブローする。しかしこの方法でのブロー量は少量
で大部分が機器ドレンフアンネルを通して、機器
ドレンサンプヘブローされる。また復水系、給水
系配管内の系統水も機器ドレンサンプ１０へブロ
ーされ、ラド設備で処理される。ホツトウエル内
の水は、復水ポンプ５が運転可能水位まで、コン
デミ６を通し、スピルオーバーライン１４によつ
て復水貯蔵タンク１１へ回収される。しかしその
量はわずかで、大部分は他の系統と同様に機器ド
レンサンプへ回収され、ラド設備で処理される。 After the plant is stopped and before the condenser vacuum is broken, the system water on the shell side and pipe side of the feed water heater 8 is
Open the door and use the degree of vacuum to blow into hot well 4. However, the amount of blowing in this method is small and most of it is blown through the equipment drain funnel and into the equipment drain sump. System water in the condensate system and water supply system piping is also blown to the equipment drain sump 10 and treated by the RAD equipment. The water in the hot well passes through the condenser 6 until the water level at which the condensate pump 5 can operate is recovered to the condensate storage tank 11 by the spillover line 14. However, the amount is small and the majority is collected in the equipment drain sump and treated in the rad facility like other systems.
この様にプラント停止後の系統水は大部分ラド
設備によつて処理され、その量は800MWeクラス
で800m3程あり、ラド設備への負荷となつている。 In this way, most of the system water after the plant is shut down is treated by the RAD equipment, and the amount of water is approximately 800m 3 in the 800MWe class, creating a load on the RAD equipment.
機器ドレンサンプに回収された系統水はラド設
備の機器ドレン系で処理される。その処理過程を
第２図により説明する。 System water collected in the equipment drain sump is treated in the equipment drain system of the RAD facility. The processing process will be explained with reference to FIG.
プラント停止後、水抜きされた系統水は機器ド
レンサンプ１０へ回収され、そこから廃液収集タ
ンクへ移送され、さらに機器ドレン移送ポンプ１
６で昇圧され、機器ドレンフイルター１７、機器
ドレン脱塩器１８で処理される。その後廃液サー
ジタンク１９を経て、復水貯蔵タンク１１へ回収
される。 After the plant is stopped, the drained system water is collected into the equipment drain sump 10, from there transferred to the waste liquid collection tank, and then transferred to the equipment drain transfer pump 1.
6, and is processed by an equipment drain filter 17 and an equipment drain demineralizer 18. Thereafter, it passes through the waste liquid surge tank 19 and is collected into the condensate storage tank 11.
復水貯蔵タンクへ回収された水は、原子炉ウエ
ルの水張り用として利用されるが、約800m3の水
を上記説明のラド設備によて処理するため、ラド
への負荷が大きく、機器ドレンフイルタスラツジ
の増加等の問題がある。 The water collected in the condensate storage tank is used to fill the reactor well, but since approximately 800m3 of water is processed by the RAD equipment explained above, the load on the RAD is large, and equipment drains are required. There are problems such as an increase in filter sludge.
〔発明の目的）
本発明の目的は、プラント停止後、系統水をラ
ド設備を使用せず処理可能な沸騰水型原子力プラ
ントを提供するにある。[Object of the Invention] An object of the present invention is to provide a boiling water nuclear power plant that can process system water without using rad equipment after the plant has been shut down.
原子力発電所停止後、系統水は大部分がラド設
備（機器ドレン系）によつて処理され、復水貯蔵
タンクへ回収されている。
After the nuclear power plant shuts down, most of the system water is treated by the RAD equipment (equipment drain system) and recovered into the condensate storage tank.
沸騰水型原子力発電所では復水浄化装置の出口
に復水貯蔵タンクへ移送できるラインがある。ま
た復水脱塩器は最近の調査，研究により、イオン
交換能力だけではなく、クラツド除去能力も有す
る事が判明した。そこで従来使用していた機器ド
レン系での機器ドレンフイルタ、脱塩器で処理す
る変わりに復水脱塩器を使用し、ここで処理した
処理水は、復水脱塩器出口のスピルオーバーライ
ンにより復水貯蔵タンクへ移送する。 In boiling water nuclear power plants, there is a line at the outlet of the condensate purification system that can be transferred to a condensate storage tank. Furthermore, recent surveys and research have revealed that condensate demineralizers have not only ion exchange ability but also crud removal ability. Therefore, instead of treating the equipment drain filter and demineralizer in the equipment drain system that was conventionally used, a condensate demineralizer was used, and the treated water was passed through the spillover line at the outlet of the condensate demineralizer. Transfer to condensate storage tank.
またホツトウエル内の水は、復水ポンプで移送
できる分は復水脱塩器で処理後、復水貯蔵タンク
へ移送されるが、ホツトウエルの水位が下がると
復水ポンプの空気吸い込みを考慮して、インター
ロツクがかかり、それ以上復水ポンプへ稼動が停
止し、ホツトウエル残留水は機器ドレンサンプへ
回収され、機器ドレン系にて処理されている。 In addition, the amount of water in the hot well that can be transferred by the condensate pump is processed by the condensate demineralizer and then transferred to the condensate storage tank. , an interlock is applied and further operation of the condensate pump is stopped, and the remaining water in the hot well is collected into the equipment drain sump and treated in the equipment drain system.
そこで、復水ポンプより小容量の循環用ポンプ
を設置し、ホツトウエル水はすべて、このポンプ
によつて復水浄化装置を通して、復水貯蔵タンク
へ回収する。 Therefore, a circulation pump with a smaller capacity than the condensate pump is installed, and all the hot well water is collected by this pump through the condensate purification device and into the condensate storage tank.
その他の系統については、各系統最下部に水抜
きラインを新設し、系統水を一たん復水回収タン
クへ回収する。回収された系統水は、復水浄化装
置で処理後、復水貯蔵タンクへ移送する。 For other systems, a new drainage line will be installed at the bottom of each system, and the system water will be collected once into the condensate recovery tank. The collected system water is treated with a condensate purification device and then transferred to a condensate storage tank.
上記方法によつつてラド設備を使用せず、系統
水の抜きとりが行える。 By using the above method, system water can be drained without using RAD equipment.
以下本発明の一実施例を第３図により説明す
る。
An embodiment of the present invention will be described below with reference to FIG.
プラント停止後、各系統での水抜きラインのバ
ルブ２０を開にし、復水回収タンク移送ライン２
１により、復水回収タンク２２に回収する。この
回収した系統水を復水移送ライン２３を通して復
水浄化装置６の上流側へ移送し、復水浄化装置６
で処理後、スピルオーバーライン２５により、復
水貯蔵タンク１１へ回収する。 After the plant is stopped, open the valve 20 of the water drain line in each system, and open the condensate recovery tank transfer line 2.
1, the condensate is collected in the condensate collection tank 22. This recovered system water is transferred to the upstream side of the condensate purification device 6 through the condensate transfer line 23, and
After treatment, the condensate is collected into the condensate storage tank 11 via the spillover line 25.
一方ホツトウエル水及び復水系での系統水は循
環用ポンプ２４にで昇圧し、復水浄化装置６を通
し、スピルオーバーライン２５により、復水貯蔵
タンクへ回収する。 On the other hand, hot well water and system water in the condensate system are pressurized by the circulation pump 24, passed through the condensate purification device 6, and recovered to the condensate storage tank by the spillover line 25.
本発明によれば、プラント停止後、系統水をラ
ド設備を使用せず、復水浄化装置を用いて処理で
きるので、ラド負荷低減の効果がある。
According to the present invention, after the plant is shut down, the system water can be treated using a condensate purification device without using a rad equipment, which has the effect of reducing rad load.
第１図は原子力発電プラントの概略図、第２図
は原子力発電所ラド設備での概略図、第３図は本
発明の具体的実施例を示す図である。
１……原子炉ウエル、２……原子炉、３……タ
ービン、４……ホツトウエル、５……低圧復水ポ
ンプ、６……復水浄化装置、７……高圧復水ポン
プ、８……給水ヒーター、９……給水ポンプ、１
０……機器ドレンサンプ、１１……復水貯蔵タン
ク、１２……機器ドレンライン、１３……高水位
調整弁、１４……スピルオーバーライン、１５…
…廃棄集収タンク、１６……機器ドレン移送ポン
プ、１７……機器ドレンフイルター、１８……機
器ドレン脱塩器、１９……廃液サージタンク、２
０……復水回収タンク移送ラインバルブ、２１…
…復水回収タンク移送ライン、２２……復水回収
タンク、２３……復水移送ライン、２４……循環
用ポンプ。
FIG. 1 is a schematic diagram of a nuclear power plant, FIG. 2 is a schematic diagram of a nuclear power plant RAD facility, and FIG. 3 is a diagram showing a specific embodiment of the present invention. 1... Reactor well, 2... Nuclear reactor, 3... Turbine, 4... Hot well, 5... Low pressure condensate pump, 6... Condensate purification device, 7... High pressure condensate pump, 8... Water heater, 9...Water pump, 1
0... Equipment drain sump, 11... Condensate storage tank, 12... Equipment drain line, 13... High water level adjustment valve, 14... Spill over line, 15...
...Waste collection tank, 16...Equipment drain transfer pump, 17...Equipment drain filter, 18...Equipment drain demineralizer, 19...Waste liquid surge tank, 2
0...Condensate recovery tank transfer line valve, 21...
...Condensate recovery tank transfer line, 22...Condensate recovery tank, 23...Condensate transfer line, 24...Circulation pump.
Claims (1)
び給水加熱器を朱たる構成要素とする沸騰水型原
子力プラントにおいて、プラントの給・復水系統
に、プラント停止時に該系統水を回収するための
回収ライン、回収した系統水を一時貯蔵するため
の復水回収タンク及び前記回収タンク中の水を前
記復水浄化装置上流側に移送するための移送ライ
ンとを設けたことを特徴とする沸騰水型原子力プ
ラント。1. In a boiling water nuclear power plant whose main components are a reactor, turbine, condenser, condensate purification device, and feedwater heater, system water is recovered from the plant's feed/condensate system when the plant is shut down. A condensate recovery tank for temporarily storing the recovered system water, and a transfer line for transferring the water in the recovery tank to the upstream side of the condensate purification device. Boiling water nuclear power plant.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP57202119A JPS5992400A (en) | 1982-11-19 | 1982-11-19 | Storage facility at shutdown |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP57202119A JPS5992400A (en) | 1982-11-19 | 1982-11-19 | Storage facility at shutdown |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5992400A JPS5992400A (en) | 1984-05-28 |
| JPH046918B2 true JPH046918B2 (en) | 1992-02-07 |
Family
ID=16452273
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP57202119A Granted JPS5992400A (en) | 1982-11-19 | 1982-11-19 | Storage facility at shutdown |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5992400A (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0810272B2 (en) * | 1986-03-12 | 1996-01-31 | 株式会社東芝 | Reactor well water treatment device |
-
1982
- 1982-11-19 JP JP57202119A patent/JPS5992400A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5992400A (en) | 1984-05-28 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| JPH046918B2 (en) | ||
| CN103400626A (en) | Method for processing waste liquid containing Ag-110m of nuclear power plant | |
| JPH0979504A (en) | Cleaning method for exhaust heat recovery boiler | |
| JP3020573B2 (en) | Spent fuel pool cooling system | |
| JPS6059481B2 (en) | Filtration equipment for water supply systems in thermal and nuclear power plants | |
| JP2892827B2 (en) | Nuclear power plant desalination equipment | |
| JP2000140839A (en) | Desalting device of condensate | |
| CN215294874U (en) | Steam recycling device of boiler periodic blowdown flash tank | |
| JPH0810272B2 (en) | Reactor well water treatment device | |
| JPS59112293A (en) | Leaked sea water decontaminating device | |
| JP2597562B2 (en) | Reactor well water purification equipment | |
| JPS621239B2 (en) | ||
| JPS6257960B2 (en) | ||
| JP2003090895A (en) | Method and device for demineralizing condensate | |
| JPH01185492A (en) | Feed water tubing circulating facility in nuclear power plant | |
| JPH0344600A (en) | Transferring equipment of spent resin | |
| JPS6235033B2 (en) | ||
| JPH10174890A (en) | Treatment of ammonia type condensate desalting device and water passage tower using to this | |
| JP2878707B2 (en) | Storage method of feed water heater of nuclear power plant | |
| JPS5892997A (en) | Condensed water clean-up device | |
| JPS6144204A (en) | Clean-up method of steam power plant | |
| JPS604439B2 (en) | How to operate a nuclear reactor plant | |
| JPS5882193A (en) | Device for cleaning residual heat removal pipeline | |
| JPS5794349A (en) | Method and device for decreasing waste liquid at regeneration of ion exchange resin | |
| JPS59112292A (en) | Condensed water cleanup device |