JPH0810272B2 - Reactor well water treatment device - Google Patents
Reactor well water treatment deviceInfo
- Publication number
- JPH0810272B2 JPH0810272B2 JP61054311A JP5431186A JPH0810272B2 JP H0810272 B2 JPH0810272 B2 JP H0810272B2 JP 61054311 A JP61054311 A JP 61054311A JP 5431186 A JP5431186 A JP 5431186A JP H0810272 B2 JPH0810272 B2 JP H0810272B2
- Authority
- JP
- Japan
- Prior art keywords
- storage tank
- pool
- valve
- reactor well
- temporary storage
- 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
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
- Y02E30/30—Nuclear fission reactors
Landscapes
- Excavating Of Shafts Or Tunnels (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Description
【発明の詳細な説明】 〔発明の目的〕 (産業上の利用分野) 本発明は、例えば燃料交換若しくは定期検査時、原子
炉ウェルプール及び機器仮置プールのプール水を排水浄
化した後、これを復水貯蔵槽へ貯水するようにした原子
炉ウェル水処理装置に関する。DETAILED DESCRIPTION OF THE INVENTION Object of the Invention (Industrial field of application) The present invention, for example, at the time of refueling or periodic inspection, after purifying the pool water of the reactor well pool and the equipment temporary pool by drainage purification, The present invention relates to a reactor well water treatment device that stores water in a condensate storage tank.
(従来の技術) 一般に、原子力発電所における原子炉は、1年に約1
回の割合で定期検査や燃料交換を行う。このとき、原子
炉ウェルプールや機器仮置プールに水張りをして作業を
行うが、燃料交換後、これらの貯水を排水し、放射能処
理して復水貯蔵槽へ回収するようになっている。(Prior Art) Generally, a nuclear reactor in a nuclear power plant has about 1
Regular inspections and refueling are performed at a rate of once. At this time, the reactor well pool and the temporary equipment pool are filled with water, but after the fuel is exchanged, the stored water is drained, radioactively treated and collected in the condensate storage tank. .
即ち、既に提案されている原子炉ウェル水処理装置
は、第4図に示されるように構成されている。That is, the already proposed reactor well water treatment apparatus is configured as shown in FIG.
第4図において、圧力容器1と実質的に一体をなす原
子炉ウェルプール2及び機器仮置プール3の各底部2a,3
aと復水貯水槽4とは、ウェルドレン管5で接続されて
おり、このウェルドレン管5の管路上には、上流がわか
ら開閉弁6、浄化水系ポンプ7、過脱塩装置8及び仕
切弁9が順に設けられている。又、上記開閉弁6の上流
側のウェルドレン管5と上記復水貯水槽4とは、分岐管
10で繋がれており、この分岐管10には、第1仕切弁11、
タービン復水器ホットウェル12、濾過脱塩装置13及び第
2仕切弁14が設けられている。さらに、上記圧力容器1
の底部と液体廃棄物処理系15とは連結管16で接続されて
おり、この連結管16の管路には、上流側から順にドレン
弁17、開閉弁18、浄化水系ポンプ19、過脱塩装置20及
び仕切弁21が設けられている。In FIG. 4, the bottoms 2a, 3 of the reactor well pool 2 and the temporary equipment pool 3 which are substantially integrated with the pressure vessel 1 are shown.
The a and the condensate water storage tank 4 are connected by a weld drain pipe 5, and an opening / closing valve 6, a purified water system pump 7, a super desalination device 8 and a partition are provided on the pipe line of the weld drain pipe 5. The valve 9 is provided in sequence. Further, the well drain pipe 5 upstream of the on-off valve 6 and the condensate water storage tank 4 are branched pipes.
The first sluice valve 11,
A turbine condenser hot well 12, a filter desalting device 13 and a second sluice valve 14 are provided. Further, the pressure vessel 1
Is connected to the liquid waste treatment system 15 by a connecting pipe 16, and a drain valve 17, an opening / closing valve 18, a purified water system pump 19, and an excessive desalination system are installed in this connecting pipe 16 in order from the upstream side. A device 20 and a sluice valve 21 are provided.
一方、上記復水貯蔵槽4と上記液体廃棄物処理系15と
は、開閉弁22を備えた連管23で接続されており、この液
体廃棄物処理系15で処理されたプール水は、上記復水貯
蔵槽4へ貯蔵されるようになっている。On the other hand, the condensate storage tank 4 and the liquid waste treatment system 15 are connected by a connecting pipe 23 having an opening / closing valve 22, and the pool water treated by the liquid waste treatment system 15 is It is adapted to be stored in the condensate storage tank 4.
他方、上記圧力容器1の上部とその下部との間には、
循環路24が接続されており、この循環路24には、第1開
閉弁25、残留熱除去系ポンプ26及び第2開閉弁27が設け
られている。又、上記第1開閉弁25の上流側の循環路24
と上記開閉弁18の上流側の連結管16との間には、バイパ
ス弁28を備えたバイパス管29が付設されており、上記残
留熱除去系ポンプ26の下流側と上記液体廃棄物処理系15
とは仕切弁30を備えた連結管31で接続されている。On the other hand, between the upper part and the lower part of the pressure vessel 1,
A circulation path 24 is connected, and the circulation path 24 is provided with a first opening / closing valve 25, a residual heat removal system pump 26, and a second opening / closing valve 27. In addition, the circulation path 24 on the upstream side of the first opening / closing valve 25
A bypass pipe 29 having a bypass valve 28 is provided between the connection pipe 16 and the upstream side connection pipe 16 of the on-off valve 18, and the downstream side of the residual heat removal system pump 26 and the liquid waste treatment system. 15
And are connected by a connecting pipe 31 equipped with a gate valve 30.
従って、上述した原子炉ウェル水処理装置は、燃料等
の交換後、原子炉ウェルプール2及び機器仮置プール3
のプール水を排水して復水貯蔵槽4へ回収する場合、
(1).上記両プール2,3のプール水は、上記開閉弁6
と仕切弁9を開弁し、浄化水系ポンプ7を駆動すること
により、ウェルドレン管5から過脱塩装置8を通して
復水貯蔵槽4へ回収する手段。Therefore, in the reactor well water treatment device described above, the reactor well pool 2 and the temporary equipment pool 3 are used after the replacement of the fuel and the like.
When draining the pool water of and collecting it in the condensate storage tank 4,
(1). The pool water of both pools 2 and 3 is the on-off valve 6 above.
And means for recovering from the well drain pipe 5 to the condensate storage tank 4 through the excessive desalination device 8 by opening the sluice valve 9 and driving the purified water system pump 7.
(2).上記両プール2,3のプール水は、上記ウェルド
レン管5から分岐した分岐管10のタービン復水器ホット
ウェル12及び過脱塩装置13を通して上記復水貯蔵槽4
へ回収する手段。(2). The pool water of both pools 2 and 3 passes through the turbine condenser hot well 12 and the super desalination device 13 of the branch pipe 10 branched from the weld drain pipe 5 and the condensate storage tank 4
Means to collect.
(3).上記両プール2,3のプール水は、上記圧力容器
1に接続している連結管16上の浄化系ポンプ19を駆動す
ることにより、過脱塩装置20を経て上記液体廃棄物処
理系15へ供給し、こゝで浄化した後、復水貯蔵槽4へ回
収する手段。(3). The pool water of both pools 2 and 3 is driven to the purification system pump 19 on the connecting pipe 16 connected to the pressure vessel 1 to pass through the over desalination device 20 to the liquid waste treatment system 15. Means for supplying and purifying with this, and then collecting in the condensate storage tank 4.
(4).上記両プール2,3のプール水は、上記圧力容器
1に接続している循環路24の残留熱除去系ポンプ26を駆
動すると共に、仕切弁30を開弁することにより、連結管
31を通して上記液体廃棄物処理系15へ供給し、こゝで、
浄化した後、復水貯蔵槽4へ回収する手段等によって行
われる。(4). The pool water of both pools 2 and 3 drives the residual heat removal system pump 26 of the circulation path 24 connected to the pressure vessel 1 and opens the sluice valve 30 to form a connecting pipe.
It is supplied to the above liquid waste treatment system 15 through 31 and
After purification, it is carried out by means of collecting the condensate storage tank 4 or the like.
(発明が解決しようとする問題点) しかしながら、上述した原子炉ウェル水処理装置にお
ける第1の回収処理手段は、液体廃棄物処理系15を通さ
ないので、復水貯蔵槽4の放射能レベルも制限値以下に
抑えることは困難である。又、第2の回収処理手段は、
両プール水を浄化せずに、直接にタービン主復水器ホッ
トウェル12へ排水するため、これも、第1の回収処理手
段と同じように、復水貯蔵槽4の放射能レベルも制限値
以下に抑えることは難しい。(Problems to be Solved by the Invention) However, since the first recovery treatment means in the reactor well water treatment apparatus described above does not pass the liquid waste treatment system 15, the radioactivity level of the condensate storage tank 4 is also increased. It is difficult to keep below the limit value. The second recovery processing means is
Since both pool waters are directly discharged to the turbine main condenser hot well 12 without being purified, the radioactivity level of the condensate storage tank 4 is also a limit value, like the first recovery treatment means. It is difficult to keep below.
さらに、第3及び第4図の回収処理手段は、いずれ
も、両プール水を液体廃棄物処理系15にて浄化するた
め、復水貯蔵槽4の放射能レベルが検出限界値に抑えら
れるけれども、液体廃棄物処理系15の処理容量が小さい
ので、排水時間が長くなる等の難点がある。Furthermore, since the recovery treatment means of FIGS. 3 and 4 both purify both pool water in the liquid waste treatment system 15, the radioactivity level of the condensate storage tank 4 is suppressed to the detection limit value. Since the treatment capacity of the liquid waste treatment system 15 is small, there are drawbacks such as long drainage time.
又一方、原子力発電プラントでは、被曝低減が重視さ
れており、特に、タービン建屋内の放射能レベルを抑え
ることが問題となっている。On the other hand, in a nuclear power plant, reduction of radiation exposure is emphasized, and in particular, suppressing the radioactivity level in the turbine building is a problem.
他方、復水貯蔵槽4の水は、タービン復水器及びター
ビンブランド蒸気系等への補給水の水源であり、この復
水貯蔵槽4の放射能レベルを抑えることは、上記タービ
ン建屋内の放射能レベルを低減することになり、しか
も、この復水貯蔵槽4は、原子炉建屋内への補給水の水
源でもあるので、原子炉建屋内の放射能レベルを低減す
ることが望ましい。On the other hand, the water in the condensate storage tank 4 is a water source of makeup water for the turbine condenser, turbine brand steam system, etc. This will reduce the radioactivity level, and since this condensate storage tank 4 is also a water source of make-up water for the reactor building, it is desirable to reduce the radioactivity level in the reactor building.
そこで、この復水貯蔵槽4の放射能レベルを低減する
ためには、前述したように、両プール水を液体廃棄物処
理系15にて処理した後、復水貯蔵槽4に回収する必要が
ある。Therefore, in order to reduce the radioactivity level of the condensate storage tank 4, as described above, it is necessary to treat both pool waters in the liquid waste treatment system 15 and then collect them in the condensate storage tank 4. is there.
さらに又、原子力発電プラントは、稼動効率(運転効
率)の向上を図るために、定期検査時間の短縮について
も、重要視されるものであり、これに起因して、上記両
プールの排水時間を短縮する必要があり、上記液体廃棄
物処理系にて処理した後、復水貯蔵槽へ回収する手段で
は、排水速度が液体廃棄物処理系15の処理速度に制限さ
れて排水時間が長くかゝり、これを短縮することは困難
である。Furthermore, in the nuclear power plant, it is important to shorten the periodic inspection time in order to improve the operation efficiency (operation efficiency), and as a result, the drainage time of both pools is reduced. It is necessary to shorten the time, and after the liquid waste treatment system is used, the drainage rate is limited to the treatment rate of the liquid waste treatment system 15 and the drainage time is long. However, it is difficult to shorten this.
本発明は、上述した事情に鑑みてなされたものであっ
て、原子炉ウェルプール及び機器仮置プールの排水時間
を短縮し、併せて、復水貯蔵槽の貯蔵水の放射能レベル
の低減を図ることを目的とする原子炉ウェル水処理装置
を提供するものでいる。The present invention has been made in view of the above circumstances, and shortens the drainage time of the reactor well pool and the equipment temporary storage pool, and at the same time, reduces the radioactivity level of the stored water in the condensate storage tank. It is intended to provide a reactor well water treatment device for the purpose of achieving it.
(問題点を解決するための手段) 本発明は、原子炉ウェルプール及び機器仮置プール内
のプール水を排水して液体廃棄物処理系等で浄化した
後、これを復水貯蔵槽へ回収するようにした原子炉ウェ
ル水処理装置において、上記両プールの全水量を貯蔵す
る仮貯蔵タンクを設け、この仮貯蔵タンクと両プールと
を仕切弁を備えた連結管で接続し、上記仮貯蔵タンクと
上記液体廃棄物処理系とを移送ポンプを備えた連管で接
続し、上記復水貯蔵槽の放射能レベルを低減すると共
に、排水時間を短縮するように構成したものである。(Means for Solving Problems) According to the present invention, pool water in a reactor well pool and a temporary equipment pool is drained and purified by a liquid waste treatment system or the like, and then collected in a condensate storage tank. In the reactor well water treatment device configured to do so, a temporary storage tank for storing the total amount of water in both pools is provided, and the temporary storage tank and both pools are connected by a connecting pipe equipped with a gate valve, and the temporary storage is performed. The tank and the liquid waste treatment system are connected by a connecting pipe equipped with a transfer pump to reduce the radioactivity level of the condensate storage tank and shorten the drainage time.
(作用) 本発明は、原子炉ウェルプール及び機器仮置プールの
プール水の全水量を、一旦仮貯蔵タンクに貯蔵し、しか
る後、これを移送ポンプで液体廃棄物処理系へ供給し
て、こゝで放射能レベルを低減処理し、さらに、これを
復水貯蔵槽へ移送して貯蔵するようにしたものである。(Operation) The present invention temporarily stores the total amount of pool water of the reactor well pool and the equipment temporary storage pool in a temporary storage tank, and thereafter supplies this to a liquid waste treatment system by a transfer pump, This is to reduce the level of radioactivity and transfer it to the condensate storage tank for storage.
(実施例) 以下、本発明を図示の一実施例について説明する。(Example) The present invention will be described below with reference to an illustrated example.
なお、本発明は、上述した具体例と同一構成部材には
同じ符号を付して説明する。Note that, in the present invention, the same components as those in the specific example described above are denoted by the same reference numerals and described.
第1図において、符号1は、圧力容器であって、この
圧力容器1と実質的に一体をなす原子炉ウェルプール2
及び機器仮置プール3の底部と復水貯蔵槽4とは、ウェ
ルドレン管5で接続されており、このウェルドレン管5
の管路には、上流がわから開閉弁6、浄化水系ポンプ
7、過脱塩装置8及び仕切弁9が順に設けられてい
る。又、上記開閉弁6の上流側のウェルドレン管5と上
記復水貯水槽4とは分岐管10で繋がれており、この分岐
管10には、第1仕切弁11、タービン復水器ホットウェル
12、過脱塩装置13及び第2仕切弁14が設けられてい
る。さらに、上記圧力容器1の底部と液体廃棄物処理系
15とは、連結管16で接続されており、この連結管16の管
路には、上流側から順にドレン弁17、開閉弁18、浄化水
系19、過脱塩装置20及び仕切弁21が設けられている。In FIG. 1, reference numeral 1 is a pressure vessel, and a reactor well pool 2 that is substantially integrated with the pressure vessel 1.
The bottom of the equipment temporary storage pool 3 and the condensate storage tank 4 are connected by a weld drain pipe 5.
An opening / closing valve 6, a purified water system pump 7, a super-desalination device 8 and a sluice valve 9 are provided in this order from the upstream side. The well drain pipe 5 on the upstream side of the on-off valve 6 and the condensate water storage tank 4 are connected by a branch pipe 10. The branch pipe 10 has a first gate valve 11 and a turbine condenser hot water. Well
12, a desalting device 13 and a second sluice valve 14 are provided. Furthermore, the bottom of the pressure vessel 1 and the liquid waste treatment system
15 is connected by a connecting pipe 16, and a drain valve 17, an on-off valve 18, a purified water system 19, a super desalination device 20, and a sluice valve 21 are provided in the pipe line of the connecting pipe 16 in this order from the upstream side. Has been.
一方、上記復水貯蔵槽4と上記液体廃棄物処理系15と
は、開閉弁22を備えた連管23で接続されており、この液
体廃棄物処理系15で放射能処理された冷却材は、上記復
水貯蔵槽4へ上記連管23を通して貯蔵されるようになっ
ている。又、上記圧力容器1の上部とその下部との間に
は、循環路24が接続されており、この循環路24には、第
1開閉弁25、残留熱除去系ポンプ26及び第2開閉弁27が
設けられている。さらに、上記第1開閉弁25の上流側の
循環路24と上記開閉弁18の上流側の連結管16との間に
は、バイパス弁28を備えたバイパス管29が付設されてお
り、上記残留熱除去系ポンプ26の吐出側と上記液体廃棄
物処理系15との間には、仕切弁30を備えた連結管31で接
続されている。On the other hand, the condensate storage tank 4 and the liquid waste treatment system 15 are connected by a connecting pipe 23 equipped with an on-off valve 22, and the coolant that has been radioactively treated by the liquid waste treatment system 15 is The condensate storage tank 4 is stored through the connecting pipe 23. A circulation passage 24 is connected between the upper portion and the lower portion of the pressure vessel 1, and the first opening / closing valve 25, the residual heat removal system pump 26 and the second opening / closing valve are connected to the circulation passage 24. 27 are provided. Further, a bypass pipe 29 having a bypass valve 28 is attached between the circulation path 24 on the upstream side of the first opening / closing valve 25 and the connecting pipe 16 on the upstream side of the opening / closing valve 18, and the residual A connection pipe 31 having a gate valve 30 is connected between the discharge side of the heat removal system pump 26 and the liquid waste treatment system 15.
他方、上記第2開閉弁27の上流側の循環路24と仮貯蔵
タンク32は、仕切弁34を備えた連結管33で接続されてお
り、特に、この仮貯蔵タンク32は、前記原子炉ウェルプ
ール2及び機器仮置プール3内のプール水の全水量を貯
蔵し得るように構成されている。又、上記仮貯蔵タンク
32と前記液体廃棄物処理系15とは連管35で接続されてお
り、この連管35には、移送ポンプ36及び仕切弁37が設け
られている。On the other hand, the circulation path 24 on the upstream side of the second on-off valve 27 and the temporary storage tank 32 are connected by a connecting pipe 33 equipped with a gate valve 34. In particular, this temporary storage tank 32 is the reactor well. It is configured to be able to store the total amount of pool water in the pool 2 and the temporary equipment pool 3. Also, the above temporary storage tank
32 and the liquid waste treatment system 15 are connected by a connecting pipe 35, and the connecting pipe 35 is provided with a transfer pump 36 and a gate valve 37.
従って、本発明は、燃料等の交換後、上記原子炉ウェ
ルプール2及び機器仮置プール3のプール水を排水して
復水貯蔵槽4へ回収する場合、予め、開閉弁22、第2開
閉弁27、仕切弁34,37を開弁すると共に、移送ポンプ36
を駆動することにより、上記両プール2,3のプール水
は、循環路24、連結管33を通して一旦、仮貯蔵タンク32
に貯蔵される。しかして、この仮貯蔵タンク32に貯蔵さ
れたプール水は、連管35を通して液体廃棄物処理系15へ
供給し、こゝで浄化した後、連管23を通して復水貯蔵槽
4へ回収する。Therefore, in the present invention, when the pool water of the reactor well pool 2 and the equipment temporary storage pool 3 is drained and recovered in the condensate storage tank 4 after the replacement of the fuel etc., the opening / closing valve 22 and the second opening / closing valve are provided in advance. The valve 27 and the gate valves 34 and 37 are opened, and the transfer pump 36
By driving the pool water in both pools 2 and 3 through the circulation path 24 and the connecting pipe 33, the temporary storage tank 32
Stored in. Then, the pool water stored in the temporary storage tank 32 is supplied to the liquid waste treatment system 15 through the connecting pipe 35, purified by this, and then collected in the condensate storage tank 4 through the connecting pipe 23.
このようにして放射化した上記両プール2,3のプール
水は、一旦、仮貯蔵タンク32へ貯蔵した後、これを液体
廃棄物処理系15へ供給するので、処理容量が小さくて
も、有効適切に上記処理することができると共に、両プ
ール2,3の排水時間を大幅に短縮することができる。The pool water of both pools 2 and 3 thus activated is temporarily stored in the temporary storage tank 32 and then supplied to the liquid waste treatment system 15, so that even if the treatment capacity is small, it is effective. The above-mentioned treatment can be appropriately performed, and the drainage time of both pools 2 and 3 can be shortened significantly.
次に、第2図に示される本発明の他の実施例は、仕切
弁9の上流側のウェルドレン管5と上記仮貯蔵タンク32
とを仕切弁34を備えた連結管33で連結したものであり、
上述した具体例と同一構成をなすものである。Next, another embodiment of the present invention shown in FIG. 2 is that the drain pipe 5 on the upstream side of the gate valve 9 and the temporary storage tank 32 are provided.
And are connected by a connecting pipe 33 equipped with a gate valve 34,
It has the same configuration as the above-described specific example.
又一方、第3図に示される本発明の他の実施例は、仕
切弁21の上流側の連結管16と上記仮貯蔵タンク32とを仕
切弁34を備えた連結管33で連結したものであり、上述し
た各具体例と同一構成をなすものである。On the other hand, in another embodiment of the present invention shown in FIG. 3, the connecting pipe 16 upstream of the gate valve 21 and the temporary storage tank 32 are connected by a connecting pipe 33 having a gate valve 34. And has the same configuration as each of the specific examples described above.
以上述べたように本発明によれば、原子炉ウェルプー
ル2及び機器仮置プール3内のプール水を排水して液体
廃棄物処理系15で浄化した後、これを復水貯蔵槽4へ回
収するようにした原子炉ウェル水処理装置において、上
記両プール2,3の全水量を貯蔵する仮貯蔵タンク32を設
け、この仮貯蔵タンク32と、両プール2,3とを仕切弁34
を備えた連結管33で接続し、上記仮貯蔵タンク32と上記
液体廃棄物処理系15とを移送ポンプ36を備えた連管35で
接続してあるので、排水処理時間を経済的に短縮できる
ばかりでなく、小容量の液体廃棄物処理系15でも有効適
切に放射能レベルの低減を図ることができるし、構成も
簡素であるから、既設の装置にも組込むことができる。As described above, according to the present invention, pool water in the reactor well pool 2 and the temporary equipment pool 3 is drained and purified by the liquid waste treatment system 15, and then collected in the condensate storage tank 4. In the reactor well water treatment device configured as described above, a temporary storage tank 32 for storing the total amount of water in the pools 2 and 3 is provided, and the temporary storage tank 32 and the pool valves 2 and 3 are separated from each other by a partition valve 34.
The temporary storage tank 32 and the liquid waste treatment system 15 are connected by the connecting pipe 35 including the transfer pump 36, so that the wastewater treatment time can be economically shortened. Not only that, even with a small-volume liquid waste treatment system 15, the level of radioactivity can be effectively and appropriately reduced, and since the configuration is simple, it can be incorporated into an existing device.
第1図は、本発明の原子炉ウェル水処理装置を示す線
図、第2図及び第3図は、本発明の他の実施例を示す各
図、第4図は、既に提案されている原子炉ウェル水処理
装置を示す線図である。 1……圧力容器、2……原子炉ウェルプール、3……機
器仮置プール、4……復水貯蔵槽、12……タービン復水
器ホットウェル、13……過脱塩装置、15……液体廃棄
物処理系、19……浄化水系ポンプ、20……過脱塩装
置、32……仮貯蔵タンク、33……連結管、34……仕切
弁、35……連管、36……移送ポンプ、37……仕切弁。FIG. 1 is a diagram showing a reactor well water treatment apparatus of the present invention, FIGS. 2 and 3 are drawings showing other embodiments of the present invention, and FIG. 4 has already been proposed. It is a diagram showing a reactor well water treatment device. 1 ... Pressure vessel, 2 ... Reactor well pool, 3 ... Temporary equipment pool, 4 ... Condensate storage tank, 12 ... Turbine condenser hot well, 13 ... Over desalination equipment, 15 ... … Liquid waste treatment system, 19 …… Purified water system pump, 20 …… Super desalination device, 32 …… Temporary storage tank, 33 …… Connection pipe, 34 …… Silver valve, 35 …… Connection pipe, 36 …… Transfer pump, 37 ... Gate valve.
Claims (3)
のプール水を排水して液体廃棄物処理系で浄化した後、
これを復水貯蔵槽へ回収するようにした原子炉ウェル水
処理装置において、上記両プールの全水量を貯蔵する仮
貯蔵タンクを設け、この仮貯蔵タンクと上記両プールと
を仕切弁を備えた連結管で接続し、上記仮貯蔵タンクと
上記液体廃棄物処理系とを移送ポンプを備えた連管で接
続したことを特徴とする原子炉ウェル水処理装置。1. The pool water in the reactor well pool and the equipment temporary storage pool is drained and purified by a liquid waste treatment system,
In a reactor well water treatment device designed to collect this in a condensate storage tank, a temporary storage tank for storing the total amount of water in both pools was provided, and a partition valve was provided between this temporary storage tank and both pools. A reactor well water treatment apparatus characterized in that the temporary storage tank and the liquid waste treatment system are connected by a connecting pipe, and the connecting pipe is provided with a transfer pump.
を備えたウェルドレン管の上流側と仮貯蔵タンクとを仕
切弁を備えた連結管で接続したことを特徴とする特許請
求の範囲第1項記載の原子炉ウェル水処理装置。2. An upstream side of a well drain pipe having a gate valve connecting both pools and a condensate storage tank and a temporary storage tank are connected by a connecting pipe having a gate valve. 2. The reactor well water treatment device according to claim 1.
弁を備えた連結管の上流側と仮貯蔵タンクとを開閉弁を
有する連通管で接続したことを特徴とする特許請求の範
囲第1項又は第2項記載原子炉ウェル水処理装置。3. The upstream side of a connecting pipe having a sluice valve connecting the pressure vessel and the liquid waste treatment system and the temporary storage tank are connected by a communicating pipe having an on-off valve. Item 1. The reactor well water treatment device according to item 1 or 2.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP61054311A JPH0810272B2 (en) | 1986-03-12 | 1986-03-12 | Reactor well water treatment device |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP61054311A JPH0810272B2 (en) | 1986-03-12 | 1986-03-12 | Reactor well water treatment device |
Publications (2)
Publication Number | Publication Date |
---|---|
JPS62211590A JPS62211590A (en) | 1987-09-17 |
JPH0810272B2 true JPH0810272B2 (en) | 1996-01-31 |
Family
ID=12967030
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP61054311A Expired - Lifetime JPH0810272B2 (en) | 1986-03-12 | 1986-03-12 | Reactor well water treatment device |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPH0810272B2 (en) |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP7062568B2 (en) * | 2018-09-27 | 2022-05-06 | 株式会社東芝 | Water treatment method and water treatment preparation method for nuclear power plants |
Family Cites Families (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS5992400A (en) * | 1982-11-19 | 1984-05-28 | 株式会社日立製作所 | Storage facility at shutdown |
-
1986
- 1986-03-12 JP JP61054311A patent/JPH0810272B2/en not_active Expired - Lifetime
Also Published As
Publication number | Publication date |
---|---|
JPS62211590A (en) | 1987-09-17 |
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