JPS5992400A - Storage facility at shutdown - Google Patents
Storage facility at shutdownInfo
- Publication number
- JPS5992400A JPS5992400A JP57202119A JP20211982A JPS5992400A JP S5992400 A JPS5992400 A JP S5992400A JP 57202119 A JP57202119 A JP 57202119A JP 20211982 A JP20211982 A JP 20211982A JP S5992400 A JPS5992400 A JP S5992400A
- Authority
- JP
- Japan
- Prior art keywords
- condensate
- water
- equipment
- rad
- storage facility
- 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.)
- Granted
Links
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
- Treatment Of Water By Ion Exchange (AREA)
- Supplying Of Containers To The Packaging Station (AREA)
- Indexing, Searching, Synchronizing, And The Amount Of Synchronization Travel Of Record Carriers (AREA)
- Adjustment And Processing Of Grains (AREA)
Abstract
(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
〔発明の利用分野〕
本発明は停止時保管システムに係セ、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
停止時保管設備に関する。DETAILED DESCRIPTION OF THE INVENTION [Field of Application of the Invention] The present invention relates to an outage storage system, and particularly to an outage storage facility suitable for reducing the amount of rad treatment of outage system water 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
べてラド設備によって処理しておシ、ラド設備への負担
が大きく問題となっている。従来系統水、水抜き方法を
第１図によシ説明する。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. A conventional method for draining system water 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、ホットウェル４ヘブローする。しかしこ
の方法でのブロー量は少量で大部分が機器ドＶ／ファノ
ネルを通して、機器ドレンサンプヘプローされる。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。ホットウェル内
の水は、復水ポンプ５が運転可能水位まで、コンデミロ
を通し、スピルオーバー２インｌ、４によって復水貯蔵
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 blown into the hot well 4 by opening the high water level control valve 13 and utilizing the degree of vacuum. However, the amount of blowing in this method is small, and most of it is blown through the equipment V/funnel and into the equipment drain sump. In addition, the system water in the condensate system and water supply system piping is also drained from the equipment drain sump 10.
It is then blown to the ground and processed in a rad facility. The water in the hot well passes through the condemiro until the water level at which the condensate pump 5 can operate is recovered to the condensate storage tank 11 by the spillover 2 in. 4. However, the amount is small and most of it is collected into the equipment drain sump like other systems.
Processed in Rad equipment.
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
って処理され、その量は８００ＭＷｅりラスで８００ｍ
８程アシ、ラド設備への負荷となっている。In this way, most of the system water after the plant is shut down is treated by RAD equipment, and the amount of water is 800mW per 800MW.
8 reeds, putting a strain on the RAD equipment.
機器ドレンザンプに回収された系統水はラド設備の礪７
：ルドレン系で処理される。その処理課程を第２図によ
り説明する。The system water collected in the equipment drain sump is collected in the RAD facility's tank 7.
: Processed by the radren system. The 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ＩＯへ回収され、そこから廃液果状タンクへ移送され
、さらに機器ドレン移送ポンプ１６で昇圧され、機器ド
レンフィルター１７、機器ドレン脱塩器１８で逃埋され
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 IO, transferred from there to the waste liquid tank, further pressurized by the equipment drain transfer pump 16, and then transferred to the equipment drain filter 17 and the equipment drain demineralizer 18. Escaped and buried. 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、原子炉ウェルの水張
シ用として利用されるが、約８００ｍ”の水を上記説明
のラド設備によって処理するため、ラドへの負荷が大き
く、機器ドレンフィルタスラッ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 800 m of water is processed by the RAD equipment described above, the load on the RAD is large, and equipment drains are required. There are problems such as an increase in filter sludge.
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停止時保管システムを提供するにあ
る。An object of the present invention is to provide a storage system during shutdown that can process system water without using rad equipment after the plant is 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）によって処理され、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 RAD equipment (equipment drain system) and recovered into condensate storage tanks.
沸騰水型原子力発電所では復水脱塩器の出力に復水貯蔵
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、研究によシ、イオン交換能力だけではなく、
クラッ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ィルタ、脱塩
器で処理する変わシに復水脱嘱器を使用し、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２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 output of the condensate desalter that can be transferred to a condensate storage tank. In addition, recent surveys and research have shown that condensate demineralizers have not only ion exchange ability, but also
It was found that it also has crud removal ability. Therefore, we used a condensate demineralizer instead of the equipment drain filter and demineralizer used in the conventional equipment drain system. The condensate is transferred to the condensate storage tank by the inlet.
またホットウェル内の水は、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
、ホットウェ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、インターロックがかかシ、それ以上復
水ポンプへ稼動が停止し、ホットウェル残留水は機器ド
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, but if the water level in the hot well decreases, the condensate pump will take in air. Then, the interlock is activated 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、復水ポンプよシ小容鎗の循環用ポンプを設置し
、ホットウェル水はすべて、このポンプによって榎水脱
頃器を通して、復水貯蔵タンクへ回収する。Therefore, a small-capacity circulation pump was installed in addition to the condensate pump, and all the hot well water was collected by this pump through the Enoki water desalinator 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−たんサージタンクへ回収する。回
収された系統水は、復水脱塩器で処理後、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 into the -tan surge tank. The collected system water is treated in a condensate demineralizer and then transferred to a condensate storage tank.
上記方法によってラド設備を使用せず、系統水の抜きと
シが行える。By the above method, system water can be drained and removed without using RAD equipment.
以下本発明の一実施例を第３図によシ説明する。 An embodiment of the present invention will be explained below with reference to FIG.
プラント停止後、各系統での水抜きラインの７（ルプ２
０を開にし、復水回収タンク移送ライン２１によシ、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を通して復水脱塩器６の上流側へ移送
し、復水脱塩器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 shut down, drain line 7 (Loop 2) in each system
0 is opened, and the condensate is collected through the condensate recovery tank transfer line 21 and into the condensate recovery tank 22. This recovered system water is transferred to the upstream side of the condensate demineralizer 6 through the condensate transfer line 23, and after being treated in the condensate demineralizer 6, the spillover line 25
The condensate is collected into the condensate storage tank 11.
一方ホッ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、復水脱塩器６を通し、スピルオーバ
ライン２５によシ、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 demineralizer 6, passed through the spillover line 25, and collected into the condensate storage tank.
本発明によれば、プラント停止後、系統水をラド設びＵ
を１吏用せず、復水脱塩器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 stopped, the system water is supplied to the U.
Since it can be treated using a condensate demineralizer without using a single liter, it has the effect of reducing the 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。
■・・・原子炉ウェル、２・・・原子炉、３・・・ター
ビン、４・・・ホットウェル、５・・・低圧復水ポンプ
、６・・・復水脱塩器、７・・・高圧復水ポンプ、８・
・・給水ヒーター、９・・・給水ポンプ、１０・・・機
器ドレンサング、１１・・・復水貯蔵タンク、１２・・
・機器ドレン２イ／、１３・・・高水位調整弁、１４・
・・スピルオーバーライン、１５・・・廃棄果状タンク
、１６・・・機器ドレン移送ポンプ、１７・・・機器ド
レンフィルター、１Ｂ・・・機器ドレン脱塩器、１９・
・・廃液サージタンク、２０・・・復水回収タンク移送
ラインパルプ、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。
剃区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. ■...Reactor well, 2...Reactor, 3...Turbine, 4...Hot well, 5...Low pressure condensate pump, 6...Condensate demineralizer, 7...・High pressure condensate pump, 8・
... Water supply heater, 9 ... Water supply pump, 10 ... Equipment drain sink, 11 ... Condensate storage tank, 12 ...
・Equipment drain 2/, 13... High water level adjustment valve, 14.
... Spill over line, 15... Waste fruit tank, 16... Equipment drain transfer pump, 17... Equipment drain filter, 1B... Equipment drain demineralizer, 19.
...Waste liquid surge tank, 20...Condensate recovery tank transfer line Pulp, 21...Condensate recovery tank transfer line,
22... Condensate recovery tank, 23... Condensate transfer line, 24... Circulation pump. shaving area
Claims (1)
れるサージタンクを有する事を特徴とする停止時保管設
備。 ２、特許請求の範囲第１項においてホットウェル内滞留
水を上記サージタンクへ移送する循環用ポンプを有する
事を特徴とする停止時保管設備。 ３、特許請求の範囲第１項において上記サージタンク水
を復水脱塩器を通して浄化させ、復水貯蔵タンクへ移送
させるラインを有する事を特徴とする停止時保管設備。[Claims] 1. A storage facility during shutdown, characterized by having a surge tank that receives and receives system water during water removal after plant shutdown. 2. The storage facility during outage as set forth in claim 1, characterized by having a circulation pump for transferring the water accumulated in the hot well to the surge tank. 3. The storage facility during outage as set forth in claim 1, characterized by having a line for purifying the surge tank water through a condensate demineralizer and transferring it to a condensate storage tank.
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 true JPS5992400A (en) | 1984-05-28 |
| JPH046918B2 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) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS62211590A (en) * | 1986-03-12 | 1987-09-17 | 株式会社東芝 | Nuclear-reactor well water treatment device |
-
1982
- 1982-11-19 JP JP57202119A patent/JPS5992400A/en active Granted
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS62211590A (en) * | 1986-03-12 | 1987-09-17 | 株式会社東芝 | Nuclear-reactor well water treatment device |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH046918B2 (en) | 1992-02-07 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| JPS5992400A (en) | Storage facility at shutdown | |
| CN103400626A (en) | Method for processing waste liquid containing Ag-110m of nuclear power plant | |
| JPS6179905A (en) | Drain recovery system | |
| JP3020573B2 (en) | Spent fuel pool cooling system | |
| JPS62211590A (en) | Nuclear-reactor well water treatment device | |
| JP2597562B2 (en) | Reactor well water purification equipment | |
| JPS6015209B2 (en) | condensate equipment | |
| JPH0135267Y2 (en) | ||
| JPH0344600A (en) | Transferring equipment of spent resin | |
| JPS6144204A (en) | Clean-up method of steam power plant | |
| JPS5773808A (en) | Steam drain discharging device | |
| JPH01185492A (en) | Feed water tubing circulating facility in nuclear power plant | |
| JPS5860297A (en) | Main steam drain processing device for bwr type reactor plant | |
| JPS624679B2 (en) | ||
| JPH0238897A (en) | Cooling system of fuel pool | |
| JP2003090895A (en) | Method and device for demineralizing condensate | |
| JPS59112293A (en) | Leaked sea water decontaminating device | |
| JPS60196592A (en) | Condensate feedwater recirculating system | |
| JPH0428964B2 (en) | ||
| JPS58219497A (en) | Method of removing corrosion product of reactor | |
| JPS59111097A (en) | Water supply device of atomic power plant | |
| JPS5882193A (en) | Device for cleaning residual heat removal pipeline | |
| JPS63214695A (en) | Control-rod drive hydraulic system feed water supply system | |
| JPS63241392A (en) | Drain water-filling device for nuclear-reactor pressure vessel | |
| JPS621239B2 (en) |