JPH0810269B2 - Reactor well drainer - Google Patents
Reactor well drainerInfo
- Publication number
- JPH0810269B2 JPH0810269B2 JP61085963A JP8596386A JPH0810269B2 JP H0810269 B2 JPH0810269 B2 JP H0810269B2 JP 61085963 A JP61085963 A JP 61085963A JP 8596386 A JP8596386 A JP 8596386A JP H0810269 B2 JPH0810269 B2 JP H0810269B2
- Authority
- JP
- Japan
- Prior art keywords
- pump
- water
- reactor well
- piping system
- reactor
- 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 - Fee Related
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
- Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Description
【発明の詳細な説明】 〔産業上の利用分野〕 本発明は、原子炉ウエルの水ぬき装置に係り、特に定
検期間短縮に好適な原子力発電所に関する。TECHNICAL FIELD The present invention relates to a water well for a reactor well, and more particularly to a nuclear power plant suitable for shortening a regular inspection period.
従来の装置は、特開昭54−67895号に記載のように原
子炉ウエルの水を燃料プール冷却浄化系（以下FPC系と
略す）のフイルターで浄化後、復水器又は、復水貯蔵タ
ンクへ排水していた。しかしながら、従来の装置では、
排水中の極微量のイオン化した放射性クラツドを除去し
ないままタンクへ排水していた。A conventional device is a condenser or a condensate storage tank after purifying water in a reactor well with a filter of a fuel pool cooling purification system (hereinafter abbreviated as FPC system) as described in JP-A-54-67895. Was draining to. However, with conventional devices,
I was draining to the tank without removing the trace amount of ionized radioactive cladding in the drainage.
上記従来技術は、原子炉ウエルからの排水中の放射能
レベルを原子力発電所の周囲環境及び原子力発電所内作
業員への影響上問題なく安全な値としていたが、排水中
にはイオン化した放射性クラツドが溶けこんでいるた
め、排水が流れこむタービン廻りの機器は、原子力用の
設備として、作業員の受ける放射線量の管理を実施して
いる。現在検討されている原子力発電所の定期点検の合
理化において、原子力発電所のタービン廻りの機器を火
力発電所なみの放射能レベルまで低減しなければなら
ず、実際には原子炉ウエル排水は、放射性廃棄物処理設
備（以下、ラド設備と略す）で時間をかけて処理を行つ
ていた。このため、原子炉ウエル水約2000m3を排水する
のに約３日間を要していた。The above-mentioned conventional technology has set the radioactivity level in the drainage water from the reactor well to a safe value without any problem in terms of the influence on the surrounding environment of the nuclear power plant and the workers in the nuclear power plant. The equipment around the turbine into which the waste water flows is used as nuclear power equipment to manage the radiation dose received by the workers. In the streamlining of regular inspections of nuclear power plants, which is currently being considered, the equipment around the turbines of nuclear power plants must be reduced to the level of radioactivity that is similar to that of thermal power plants. Waste treatment equipment (hereinafter abbreviated as Rad equipment) was being processed over time. Therefore, it took about 3 days to drain about 2000 m 3 of reactor well water.
本発明の目的は、原子炉ウエルの水ぬきを短時間で行
なえ、且つ燃料貯蔵プール水の温度上昇を抑制できる装
置を提供することにある。An object of the present invention is to provide a device capable of draining water from a reactor well in a short time and suppressing an increase in temperature of fuel storage pool water.
上記目的は、サプレッションプール，第１のポンプ及
びサージタンクを直列接続する第１の配管系と、原子炉
ウエル，第２のポンプ及びフィルターを直列接続する第
２の配管系と、該第２の配管系とは別に、スキマサージ
タンク，第３のポンプ，熱交換器及び燃料貯蔵プールを
直列接続する第３の配管系と、前記フィルターの下流側
を前記第１のポンプの上流側に接続する配管とを備える
ことにより達成される。The above object is to provide a first piping system in which a suppression pool, a first pump and a surge tank are connected in series, a second piping system in which a reactor well, a second pump and a filter are connected in series, and the second piping system. Separately from the piping system, a third piping system that connects the skimmer surge tank, the third pump, the heat exchanger, and the fuel storage pool in series, and the downstream side of the filter is connected to the upstream side of the first pump. It is achieved by including piping.
本発明によれば、原子炉ウエルの水をフィルターで浄
化処理し、第２のポンプ及び第１のポンプを用いて第１
の配管系（サプレッションプール水排水系（以下、SPH
系と略す））のサージタンクに排水することにより、原
子炉ウエルからの排水時間を大幅に低減することができ
る。According to the present invention, the water in the reactor well is purified by the filter and the first and second pumps are used to clean the water.
Piping system (suppression pool water drainage system (hereinafter SPH
The drainage time from the reactor well can be greatly reduced by draining to the surge tank (abbreviated as system)).
また、第３の配管系（FPC系）が第２の配管系とは別
に、スキマサージタンク，第３のポンプ，熱交換器及び
燃料貯蔵プールを直列接続することにより、原子炉ウエ
ルの水ぬき時においても、燃料貯蔵プールに戻す水を熱
交換器で冷却できるので、燃料貯蔵プール水の温度上昇
を抑制することができる。In addition, the third piping system (FPC system) is connected to the second piping system separately from the second piping system, and by connecting the clearance surge tank, the third pump, the heat exchanger, and the fuel storage pool in series, it is possible to drain water from the reactor well. Even at times, the water returned to the fuel storage pool can be cooled by the heat exchanger, so that the temperature rise of the fuel storage pool water can be suppressed.
以下、本発明の一実施例を第１図により説明する。 Hereinafter, an embodiment of the present invention will be described with reference to FIG.
第１図において、原子炉ウエル１の水は、FPC系ポン
プ２によりFPC系フイルター３で浄化処理された後、サ
プレツシヨンプール13のSPH系配管４を通り、ブースタ
ーポンプ５で昇圧後、SPH系のサージタンク６へ排水さ
れる。サージタンク６に貯蔵された炉水は、移送ポンプ
７によりラド設備８へ送られて浄化処理後、復水貯蔵タ
ンク９へ回収される。この際、炉水は、FPC系フイルタ
ー３により不純物を除去され初期の放射性クラツド量の
約1/10〜1/100となつた後、サージタンク６へ排出され
るため発電所の周囲環境への影響はまつたくない。又、
排水速度は、ポンプ２の排水量によつて決定され、通常
の原子力発電所では、原子炉ウエル水約2000m3の排水を
約12時間で実施できる。サージタンク６に貯つた炉水
は、ラド設備８で徐々に処理され、約３日間で復水貯蔵
タンク９に回収される。ラド設備８出口では、排水中の
イオン化された放射性クラツドが除去されているため、
復水貯蔵タンク９の水質は向上する。In FIG. 1, the water in the reactor well 1 is purified by the FPC system filter 2 by the FPC system filter 3, passes through the SPH system piping 4 of the supplement pool 13, and is boosted by the booster pump 5, and then SPH. It is drained to the surge tank 6 of the system. The reactor water stored in the surge tank 6 is sent to the rad equipment 8 by the transfer pump 7, is purified, and is collected in the condensate storage tank 9. At this time, the reactor water is cleaned of impurities by the FPC-based filter 3 and becomes about 1/10 to 1/100 of the initial amount of radioactive cladding, and then discharged to the surge tank 6, so that the environment water around the power plant is discharged. I don't want to be affected. or,
The drainage speed is determined by the amount of drainage of the pump 2. In a normal nuclear power plant, drainage of about 2000 m 3 of reactor well water can be performed in about 12 hours. The reactor water stored in the surge tank 6 is gradually treated in the rad equipment 8 and collected in the condensate storage tank 9 in about 3 days. At the exit of the Rad facility 8, since the ionized radioactive cladding in the wastewater has been removed,
The water quality of the condensate storage tank 9 is improved.
通常、発電所では、サプレツシヨンプール13のメンテ
ナンス用としてサージタンク６をサイトに１基以上設置
しており、本発明の実施のために新しくタンクを設置す
る必要はない。又、サージタンク６は、サプレツシヨン
プール水約3000m3を貯蔵できる容量を有しており、原子
炉ウエル水2000m3の排出先として問題ない。Usually, in a power plant, one or more surge tanks 6 are installed at a site for maintenance of the supplement pool 13, and it is not necessary to install a new tank for implementing the present invention. Further, the surge tank 6 has a capacity capable of storing about 3000 m 3 of supplement pool water, and there is no problem as a discharge destination of 2000 m 3 of reactor well water.
又、燃料貯蔵プール11の水は、スキマサージタンク12
から、FPC系ポンプ２で排出された後、フイルター３を
バイパスし直接、熱交換器10で冷却されて燃料貯蔵プー
ル11に戻される。従って、原子炉ウエル１の水ぬき時
に、燃料貯蔵プール11の水温が上昇することを抑制でき
る。Also, the water in the fuel storage pool 11 is
After being discharged from the FPC system pump 2, it bypasses the filter 3 and is directly cooled by the heat exchanger 10 and returned to the fuel storage pool 11. Therefore, the water temperature of the fuel storage pool 11 can be prevented from rising when the reactor well 1 is drained.
本実施例によれば、原子炉ウエルの水ぬきを従来の約
1/5の時間で行えるため、プラント定検期間の短縮の効
果が有る。According to the present embodiment, the water removal of the reactor well is
Since it can be done in 1/5 of the time, it has the effect of shortening the plant regular inspection period.
本発明によれば、原子炉ウエルの水ぬきを短時間で行
なえるとともに、燃料貯蔵プール水の温度上昇を抑制す
ることができる。According to the present invention, it is possible to drain water from a reactor well in a short time and suppress an increase in temperature of fuel storage pool water.
第１図は本発明の一実施例のシステム構成図である。 １……原子炉ウエル、２……FPC系ポンプ、３……FPC系
フイルタ、４……SPH系配管、５……ブースターポン
プ、６……サージタンク、７……移送ポンプ、８……ラ
ド設備、９……復水貯蔵タンク、10……熱交換器、11…
…燃料貯蔵プール、12……スキマサージタンク、13……
サプレツシヨンプール、14……残留熱除去系ポンプ。FIG. 1 is a system configuration diagram of an embodiment of the present invention. 1 ... Reactor well, 2 ... FPC system pump, 3 ... FPC system filter, 4 ... SPH system piping, 5 ... Booster pump, 6 ... Surge tank, 7 ... Transfer pump, 8 ... Rad Equipment, 9 ... Condensate storage tank, 10 ... Heat exchanger, 11 ...
… Fuel storage pool, 12 …… skimmer surge tank, 13 ……
Supplement pool, 14 ... Residual heat removal system pump.
フロントページの続き (51)Int.Cl.6 識別記号 庁内整理番号 ＦＩ 技術表示箇所 Ｇ２１Ｃ 19/28 Continuation of front page (51) Int.Cl. 6 Identification number Office reference number FI technical display location G21C 19/28
Claims (2)
サージタンクを直列接続する第１の配管系と、 原子炉ウエル，第２のポンプ及びフィルターを直列接続
する第２の配管系と、 該第２の配管系とは別に、スキマサージタンク，第３の
ポンプ，熱交換器及び燃料貯蔵プールを直列接続する第
３の配管系と、 前記フィルターの下流側を前記第１のポンプの上流側に
接続する配管とを備えたことを特徴とする原子炉ウエル
の水ぬき装置。1. A first piping system for connecting a suppression pool, a first pump and a surge tank in series; a second piping system for connecting a reactor well, a second pump and a filter in series; and a second piping system. Separately from the piping system of No. 3, a third piping system that connects a skimmer surge tank, a third pump, a heat exchanger, and a fuel storage pool in series, and a downstream side of the filter is connected to an upstream side of the first pump. A water well draining device for a reactor well.
のポンプと前記第３のポンプの上流側同士及び下流側同
士をそれぞれ接続する第１の接続管及び第２の接続管を
備え、該第１及び第２の接続管はそれぞれ開閉弁を有す
ることを特徴とする原子炉ウエルの水ぬき装置。2. The method according to claim 1, wherein
A first connecting pipe and a second connecting pipe for connecting the upstream side and the downstream side of the pump and the third pump, respectively, and each of the first and second connecting pipes has an on-off valve. Water draining device for reactor wells.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61085963A JPH0810269B2 (en) | 1986-04-16 | 1986-04-16 | Reactor well drainer |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61085963A JPH0810269B2 (en) | 1986-04-16 | 1986-04-16 | Reactor well drainer |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS62242892A JPS62242892A (en) | 1987-10-23 |
| JPH0810269B2 true JPH0810269B2 (en) | 1996-01-31 |
Family
ID=13873391
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP61085963A Expired - Fee Related JPH0810269B2 (en) | 1986-04-16 | 1986-04-16 | Reactor well drainer |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0810269B2 (en) |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS62237396A (en) * | 1986-04-08 | 1987-10-17 | 株式会社東芝 | Nuclear-reactor well water drainage system |
-
1986
- 1986-04-16 JP JP61085963A patent/JPH0810269B2/en not_active Expired - Fee Related
Also Published As
| Publication number | Publication date |
|---|---|
| JPS62242892A (en) | 1987-10-23 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| LAPS | Cancellation because of no payment of annual fees |