JPH08327789A - Equipment for radioactive waste processing system - Google Patents
Equipment for radioactive waste processing systemInfo
- Publication number
- JPH08327789A JPH08327789A JP7134961A JP13496195A JPH08327789A JP H08327789 A JPH08327789 A JP H08327789A JP 7134961 A JP7134961 A JP 7134961A JP 13496195 A JP13496195 A JP 13496195A JP H08327789 A JPH08327789 A JP H08327789A
- Authority
- JP
- Japan
- Prior art keywords
- backwash water
- tank
- separation tank
- condensate
- waste liquid
- 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.)
- Pending
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
-
- 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
- Separation Of Suspended Particles By Flocculating Agents (AREA)
Abstract
Description
【０００１】[0001]
【産業上の利用分野】本発明は原子力発電所の放射性廃
棄物処理系に設置されている復水ろ過装置および復水脱
塩装置の処理液中のクラッドを沈降し易く構成した放射
性廃棄物処理（以下、Ｒ／Ｗと記す）系設備に関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to the treatment of radioactive waste in which the clad in the treatment liquid of the condensate filter and condensate demineralizer installed in the radioactive waste treatment system of a nuclear power plant is easily settled. (Hereinafter, referred to as R / W) system equipment.
【０００２】[0002]
【従来の技術】沸騰水型原子力発電所では図３に示した
ように原子炉圧力容器１内で発生した蒸発をタービン２
へ送って発電機を駆動し、タービン２で仕事を終えた蒸
気を復水器３で凝縮して復水し、復水を浄化して給水と
し原子炉圧力容器１に戻している。2. Description of the Related Art In a boiling water nuclear power plant, as shown in FIG.
The steam that has been sent to the turbine 2 to drive the generator is condensed in the condenser 3 to condense the steam, and the condensed water is purified and supplied to the reactor pressure vessel 1 as water.
【０００３】この際、復水ろ過装置（以下、ＣＦと記
す）４、復水脱塩装置（以下、ＣＤと記す）５、原子炉
冷却材浄化系（以下、ＣＵＷ（Ｆ／Ｄ）と記す）６、燃
料プール浄化系（以下、ＦＰＣ（Ｆ／Ｄ）（図示せず）
と記す）およびＲ／Ｗ系の低電導度廃液系ろ過器（以
下、ＬＣＷ−ＨＦＦと記す）10等の水処理設備から発生
するクラッドおよびイオン交換樹脂を沈降分離槽８に移
送し、静置することによりクラッド等を沈降させたのち
上澄み液（デカント）を低電導度廃液系収集タンク９ま
たは高電導度廃液系収集タンク11に移送している。At this time, a condensate filter (hereinafter referred to as CF) 4, a condensate demineralizer (hereinafter referred to as CD) 5, a reactor coolant purification system (hereinafter referred to as CUW (F / D)) ) 6, fuel pool purification system (hereinafter, FPC (F / D) (not shown))
And R / W type low conductivity waste liquid type filter (hereinafter referred to as LCW-HFF) 10 and other water treatment equipment clad and ion exchange resin are transferred to a settling separation tank 8 and allowed to stand. After the clad or the like is settled by doing so, the supernatant liquid (decant) is transferred to the low-conductivity waste liquid system collection tank 9 or the high-conductivity waste liquid system collection tank 11.
【０００４】図３により従来のＲ／Ｗ系設備を更に詳し
く説明する。図３において、原子炉圧力容器１内で発生
した蒸気はタービン２に送られてタービン２を回転し、
タービン２で仕事をした蒸気はホットウェル（復水器）
３で凝縮されて復水となる。復水はＣＦ４およびＣＤ５
で浄化された後、再び原子炉圧力容器１へと供給され
る。The conventional R / W system equipment will be described in more detail with reference to FIG. In FIG. 3, the steam generated in the reactor pressure vessel 1 is sent to the turbine 2 to rotate the turbine 2,
The steam that worked in the turbine 2 is a hot well (condenser)
It is condensed in 3 and becomes condensed water. Condensate is CF4 and CD5
After being purified in (1), it is supplied to the reactor pressure vessel 1 again.
【０００５】また、原子炉圧力容器１からはＣＵＷ（Ｆ
／Ｄ）６へと接続するラインが設けてあり、原子炉圧力
容器１内の水は一部原子炉冷却材浄化系ろ過脱塩装置に
導かれ浄化された後、再び原子炉格納容器１内へと戻さ
れる。ＣＦ４は逆洗水受タンク７に接続し、逆洗水受タ
ンク７は沈降分離槽８に接続している。ＣＤ５，ＣＵＷ
（Ｆ／Ｄ）６およびＲ／Ｗ系のＬＣＷ−ＨＦＦ10は沈降
分離槽８へと接続されている。From the reactor pressure vessel 1, CUW (F
/ D) 6 is connected to the reactor pressure vessel 1 and the water in the reactor pressure vessel 1 is partially introduced into the reactor coolant purification system filter desalting device to be purified, and then again in the reactor containment vessel 1. Returned to. The CF4 is connected to the backwash water receiving tank 7, and the backwash water receiving tank 7 is connected to the sedimentation separation tank 8. CD5, CUW
The (F / D) 6 and the R / W system LCW-HFF 10 are connected to the sedimentation separation tank 8.
【０００６】ＣＦ４の逆洗水は一旦逆洗水受タンク７に
移送された後、沈降分離槽８へと移送される。他の水処
理設備の逆洗水は直接沈降分離槽８に移送される。ただ
し、プラントによりＣＦ４以外の水処理設備にも逆洗水
受タンクが設置されている場合もある。The backwash water of CF4 is once transferred to the backwash water receiving tank 7 and then to the sedimentation separation tank 8. Backwash water of other water treatment equipment is directly transferred to the sedimentation separation tank 8. However, depending on the plant, the backwash water receiving tank may be installed in water treatment equipment other than CF4.
【０００７】沈降分離槽８では各水処理設備から発生す
るクラッドおよびイオン交換樹脂を逆洗水とともに受け
入れ、静置することによりクラッド等を沈降させ、その
のち上澄み液をＲ／Ｗタンク（低電導度廃液系収集タン
ク９または高電導度廃液収集タンク11）に移送してい
る。In the settling / separation tank 8, the clad and ion-exchange resin generated from each water treatment facility are received together with the backwash water, and the clad and the like are allowed to settle by allowing them to stand, after which the supernatant liquid is stored in an R / W tank (low conductivity). Waste liquid collection tank 9 or high conductivity waste liquid collection tank 11).
【０００８】低電導度廃液系では低電導度廃液系タンク
９からＬＣＷ−ＨＦＦ10に配管が接続されており、低電
導度廃液系収集タンク９内の廃液はＬＣＷ−ＨＦＦ10に
よりろ過処理される。低電導度廃液はその後図示してな
い脱塩装置で脱塩処理された後、復水貯蔵タンクへと送
られプラント内で利用される。In the low-conductivity waste liquid system, a pipe is connected from the low-conductivity waste liquid system tank 9 to the LCW-HFF10, and the waste liquid in the low-conductivity waste liquid collection tank 9 is filtered by the LCW-HFF10. After that, the low-conductivity waste liquid is desalted by a desalting device (not shown) and then sent to a condensate storage tank for use in the plant.
【０００９】高電導度廃液系では高電導度廃液収集タン
ク11から濃縮器12に配管が接続されており、高電導度廃
液系収集タンク11内の廃液は濃縮器12により蒸留処理さ
れる。処理水中のクラッド等の不溶物は濃縮器12により
濃縮され、最終的に固化系13へと送られプラスチック固
化処理される。In the high-conductivity waste liquid system, a pipe is connected from the high-conductivity waste liquid collecting tank 11 to the concentrator 12, and the waste liquid in the high-conductivity waste liquid collecting tank 11 is distilled by the concentrator 12. Insoluble matter such as clad in the treated water is concentrated by the concentrator 12, and finally sent to the solidification system 13 for plastic solidification treatment.
【００１０】[0010]
【発明が解決しようとする課題】しかしながら、従来の
Ｒ／Ｗ系設備においては、浮遊しやすいクラッドは沈降
分離槽８で沈降せずに低電導度廃液系収集タンク９や、
高電導度廃液系収集タンク11へと移送されてしまう。処
理水はその後、脱塩処理等を施され復水貯蔵タンクへと
送られるプラント内で使用されるか、または放水口から
プラント外へと放出される。However, in the conventional R / W system equipment, the clad that tends to float is not settled in the settling separation tank 8 and the low conductivity waste liquid collection tank 9 or
It is transferred to the high conductivity waste liquid system collection tank 11. The treated water is then subjected to desalting treatment or the like and used in a plant that is sent to a condensate storage tank, or is discharged from the plant through a water outlet.
【００１１】沈降分離槽８のデカント水（上澄み液）を
低電導度廃液系で処理する際に問題となるのは、イオン
交換樹脂およびクラッド等が沈降分離槽８へ移送されて
から、数10時間静置しても沈降せずに浮遊し続けるクラ
ッド等が低電導度廃液系タンク９への移送時に処理水と
一緒に移送されてしまう。A problem when treating the decanted water (supernatant liquid) in the sedimentation separation tank 8 with the low-conductivity waste liquid system is that a few tens of minutes after the ion-exchange resin and the clad are transferred to the sedimentation separation tank 8. A clad or the like that continues to float without settling even when left standing for a long time is transferred together with the treated water when being transferred to the low-conductivity waste liquid system tank 9.
【００１２】そして、低電導度処理系のろ過器への負荷
が上昇すること、およびろ過器の逆洗水が沈降分離槽８
に移送され、再びクラッドが沈降分離槽８に戻ってきて
しまう事象を繰り返す（クラッドリサイクルと云う）こ
とである。また、高電導度廃液系で処理する場合には、
濃縮器12への負荷上昇およびその後のプラスチック固化
時の機器への負荷上昇、固化体の放射能上昇が課題とな
る。Then, the load on the filter of the low-conductivity treatment system is increased, and the backwash water of the filter is settling and separating tank 8
Is repeated and the clad is returned to the settling separation tank 8 again (called clad recycling). When treating with a high conductivity waste liquid system,
An increase in the load on the concentrator 12, an increase in the load on the equipment at the time of solidifying the plastic thereafter, and an increase in the radioactivity of the solidified body become problems.
【００１３】本発明は上記課題を解決するためになされ
たもので、原子力発電所のＲ／Ｗ系に配置している逆洗
水受タンク７および沈降分離槽８内に浮遊し易い小粒径
クラッドを酸化、凝縮させて強制的に沈降させるように
構成したＲ／Ｗ系設備を提供することにある。The present invention has been made to solve the above problems, and has a small particle size that easily floats in the backwash water receiving tank 7 and the settling separation tank 8 arranged in the R / W system of a nuclear power plant. An object of the present invention is to provide R / W system equipment configured to oxidize and condense the clad and forcibly settle it.
【００１４】[0014]
【課題を解決するための手段】本発明は原子炉圧力容器
からの蒸気をタービン復水器で復水とし、その復水を復
水ろ過装置および復水脱塩装置で浄化し原子炉圧力容器
へ供給する系統と前記原子炉圧力容器に接続した原子炉
冷却材浄化系とを有し、前記復水ろ過装置を逆洗水受タ
ンクを経由し沈降分離槽へ接続し、この沈降分離槽に前
記復水脱塩装置および低電導度廃液系ろ過装置を接続
し、前記復水ろ過装置の逆洗水を前記逆洗水受タンクに
移送した後前記沈降分離槽に移送し前記復水脱塩装置の
逆洗水を前記沈降分離槽に移送するように配管接続して
なる放射性廃棄物処理系設備において、前記逆洗水受タ
ンクおよび沈降分離槽に酸化剤または凝集剤注入装置を
接続してなることを特徴とする。According to the present invention, steam from a reactor pressure vessel is condensed into a condensate by a turbine condenser, and the condensate is purified by a condensate filtering device and a condensate demineralizer, and then the reactor pressure vessel. And a reactor coolant purification system connected to the reactor pressure vessel, the condensate filter is connected to a settling separation tank via a backwash water receiving tank, The condensate desalination device and the low-conductivity waste liquid system filtration device are connected to each other, and the backwash water of the condensate filtration device is transferred to the backwash water receiving tank and then to the sedimentation separation tank to transfer the condensate demineralization. In a radioactive waste treatment system facility which is connected by piping so as to transfer the backwash water of the apparatus to the sedimentation separation tank, an oxidizer or coagulant injection device is connected to the backwash water receiving tank and the sedimentation separation tank. It is characterized by
【００１５】[0015]
【作用】本発明は、沈降分離槽内で浮遊し易い小粒径ク
ラッドを酸化、凝縮させ、沈降分離槽内で沈降し易くし
て、低電導度廃液系または高電導度廃液系に小粒子クラ
ッドが移送されることを防止する。The present invention oxidizes and condenses a small particle size clad that easily floats in the sedimentation separation tank, facilitates sedimentation in the sedimentation separation tank, and reduces small particles in the low-conductivity waste liquid system or the high-conductivity waste liquid system. Prevents the clad from being transferred.
【００１６】すなわち、逆洗水受タンクおよび沈降分離
槽に小粒径クラッドを酸化、凝縮する酸化剤（凝集剤）
注入装置を設けることにより、酸化剤等（例えば過酸化
水素水）を注入し小粒径クラッドを酸化、または凝縮さ
せることにより沈降分離槽内で沈降し易い成分として、
低電導度廃液系または高電導度廃液系へのクラッドの持
ち込みを防止する。That is, an oxidizer (coagulant) for oxidizing and condensing the small particle size clad in the backwash water receiving tank and the sedimentation separation tank.
By installing an injection device, an oxidizing agent (for example, hydrogen peroxide solution) is injected to oxidize or condense the small particle size clad, and as a component that easily sediments in the sedimentation separation tank,
Prevents the clad from being brought into a low-conductivity waste liquid system or a high-conductivity waste liquid system.
【００１７】酸化処理により非晶鉄等の小粒径クラッド
をマグネタイト（Ｆｅ3 Ｏ4 ）等の比較的大きな結晶を
つくる形態に変化させることで沈降を促すことができ
る。また可溶性の２価の鉄イオンを酸化し３価の鉄の水
酸化物として沈殿させることもできる。凝縮剤を加えた
場合は、凝集剤により粒子表面の荷電の中和と粒子のフ
ロック化により粒子の凝縮・沈殿が生じる。Sedimentation can be promoted by changing the small particle size clad such as amorphous iron into a form that produces relatively large crystals such as magnetite (Fe 3 O 4 ) by the oxidation treatment. It is also possible to oxidize soluble divalent iron ions and precipitate them as hydroxides of trivalent iron. When a condensing agent is added, the coagulant neutralizes the electric charge on the surface of the particles and causes the particles to flocculate, so that the particles are condensed / precipitated.
【００１８】本発明により、逆洗水受タンクおよび沈降
分離槽内に浮遊し易い小粒径クラッドが移送された場
合、逆洗水受タンクおよび沈降分離槽内でクラッドを酸
化・凝縮することにより、沈降分離槽でクラッドを効率
的に沈殿させることができ、低電導度廃液系または高電
導度廃液系に余分なクラッドを移送せず液体のみを移送
することができる。According to the present invention, when the small particle size clad which is easily floated is transferred into the backwash water receiving tank and the sedimentation separation tank, the cladding is oxidized and condensed in the backwash water receiving tank and the sedimentation separation tank. The clad can be efficiently precipitated in the sedimentation separation tank, and only the liquid can be transferred to the low-conductivity waste liquid system or the high-conductivity waste liquid system without transferring the extra clad.
【００１９】[0019]
【実施例】図１および図２により本発明に係るＲ／Ｗ系
設備の一実施例を説明する。なお、図１中図３と同一部
分には同一符号を付して重複する部分の説明は省略す
る。EXAMPLE An example of the R / W system equipment according to the present invention will be described with reference to FIGS. 1 and 2. In FIG. 1, the same parts as those in FIG. 3 are designated by the same reference numerals, and the description of the overlapping parts will be omitted.
【００２０】本発明の実施例が従来例と異なる点は図１
に示したように逆洗水受タンク７の外周部位に加熱ヒー
タ14を設けるとともに内部にガスバブリング用スパージ
ャ15を設け、さらに酸化剤（凝集剤）注入装置16からの
配管を接続したことにある。また、沈降分離槽８にも同
様にガスバブリング用スパージャ15と酸化剤（凝集剤）
注入装置16からの配管を接続したことにある。The difference between the embodiment of the present invention and the conventional example is shown in FIG.
As shown in FIG. 3, the heater 14 is provided on the outer peripheral portion of the backwash water receiving tank 7, the gas bubbling sparger 15 is provided inside, and the pipe from the oxidant (coagulant) injection device 16 is connected. . Also, in the settling separation tank 8, the gas bubbling sparger 15 and the oxidizing agent (aggregating agent) are similarly added.
This is because the pipe from the injection device 16 was connected.
【００２１】ガスバブリング用スパージャ15は所内用圧
縮空気系（ＳＡ）または計装用圧縮空気系（ＩＡ）から
空気を供給する配管が接続されて空気バブリング装置を
構成している。エアバブリングはＳＡまたはＩＡから空
気をスパージャ15に流し逆洗水受タンク７または沈降分
離槽８内の逆洗水中に気泡を発生させることで、スパー
ジャ15としては多孔分散管または噴霧器が使用される。The gas bubbling sparger 15 is connected to a pipe for supplying air from the in-house compressed air system (SA) or the instrumentation compressed air system (IA) to form an air bubbling device. In air bubbling, air is flown from the SA or IA to the sparger 15 to generate bubbles in the backwash water in the backwash water receiving tank 7 or the settling separation tank 8. A porous dispersion pipe or a sprayer is used as the sparger 15. .
【００２２】酸化剤としては過酸化水素等が使用され、
酸化剤により逆洗水中のクラッドが酸化して形態（結晶
構造等）を変化させるもので、例えば、非晶鉄がＦｅ3
Ｏ4結晶となり、粒子が大きくなり易くなる。また、逆
洗水中の水に溶けるＦｅ（ＯＨ）2 は酸化してＦｅ（Ｏ
Ｈ）3 となって水に溶けない形態となる。一方、凝集剤
には硫酸バン土等が使用され、小さいクラッド粒子をい
くつか結合させて大きくする作用を有する。Hydrogen peroxide or the like is used as the oxidizing agent,
The oxidizer oxidizes the cladding in the backwash water to change the morphology (crystal structure, etc.). For example, amorphous iron is Fe 3
O 4 crystals are formed, and the particles are likely to become large. In addition, Fe (OH) 2 dissolved in water in the backwash water is oxidized to produce Fe (O).
H) 3 and becomes a form insoluble in water. On the other hand, vanadium sulfate or the like is used as the coagulant, and has an action of binding some small clad particles to increase the size.
【００２３】図１において、沈降分離槽８には、ＬＣＷ
ろ過器10で捕獲したクラッドが逆洗水により沈降分離槽
８に移送される。また、ＣＦ５の逆洗水は一旦逆洗水受
タンク７に移送され、その後沈降分離槽８に移送され
る。In FIG. 1, the settling / separating tank 8 has an LCW.
The clad captured by the filter 10 is transferred to the sedimentation separation tank 8 by backwashing water. The backwash water of CF5 is once transferred to the backwash water receiving tank 7 and then to the sedimentation separation tank 8.
【００２４】逆洗水受タンク７には、ＣＦ４からの逆洗
完了により酸化剤（凝集剤）注入装置16で酸化剤または
凝集剤が自動または手動で注入される。同時に、加温ヒ
ータ14により逆洗水受タンク７が加温され、所内用圧縮
空気系（ＳＡ）、または計装用圧縮空気系（ＩＡ）から
空気が注入されて逆洗水受タンク７の逆洗水中へのバブ
リングが行われる。Oxidizing agent or aggregating agent is automatically or manually injected into the backwashing water receiving tank 7 by the oxidant (aggregating agent) injecting device 16 after the backwashing from CF4 is completed. At the same time, the backwash water receiving tank 7 is heated by the heating heater 14, and air is injected from the internal compressed air system (SA) or the instrumentation compressed air system (IA) to reverse the backwash water receiving tank 7. Bubbling into the wash water is performed.
【００２５】以上の工程を経て逆洗水受タンク７内の処
理水は、沈降分離槽８に移送される。沈降分離槽８が一
定のレベル（デカント可能レベル）まで達した後、沈降
分離槽酸化剤（凝集剤）注入装置16により酸化剤を注入
し、同時にＳＡまたはＩＡからバブリング用スパージャ
15により、数時間攪拌し、数時間静置後上澄み液のデカ
ント移送を収集タンク９に行う。Through the above steps, the treated water in the backwash water receiving tank 7 is transferred to the sedimentation separation tank 8. After the settling / separation tank 8 reaches a certain level (decantable level), the settling / separating tank oxidant (coagulant) injection device 16 injects the oxidant, and at the same time, SA or IA bubbling sparger.
At 15, the mixture is stirred for several hours, left standing for several hours, and then the supernatant is decanted and transferred to the collection tank 9.
【００２６】逆洗水タンク７において、酸化剤（凝集
剤）注入と加温またはバブリングがなされることで小粒
径クラッド（浮遊し易いクラッド）は、酸化、凝縮反応
を起こし沈降し易くなる。In the backwash water tank 7, injection of an oxidant (coagulant) and heating or bubbling facilitates the small particle size clad (the clad that easily floats) to undergo an oxidation and condensation reaction to easily settle.
【００２７】さらに、沈降分離槽８内においても、所内
用圧縮空気バブリングと酸化剤注入により、逆洗水受タ
ンク内で、酸化、凝縮しなかった小粒径クラッド等を沈
降させる。Further, also in the settling / separating tank 8, small-sized clad particles which have not been oxidized or condensed are settled in the backwash water receiving tank by bubbling internal compressed air and injecting an oxidant.
【００２８】図２は本発明の他の実施例における沈降分
離槽８の概略図を示したものである。すなわち、図２に
示したように、沈降分離装置８内に大型磁石18を設置す
る。これによりクラッド（鉄：Ｆｅ）を下部に引き寄せ
クラッドの浮遊を迎えることもできる。FIG. 2 is a schematic view of a settling separation tank 8 according to another embodiment of the present invention. That is, as shown in FIG. 2, the large magnet 18 is installed in the sedimentation separation device 8. As a result, the clad (iron: Fe) can be drawn to the lower part and the clad can float.
【００２９】[0029]
【発明の効果】本発明によれば、沈降分離槽内で浮遊し
ている小粒径クラッド等を酸化、凝縮することが可能と
なり、沈降分離槽からのデカント水による低電導度廃液
系収集タンクまたは高電導度廃液収集タンクへのクラッ
ド持ち込みを防止することができる。According to the present invention, it becomes possible to oxidize and condense small particle size clads and the like floating in the sedimentation separation tank, and a low conductivity waste liquid system collection tank by decant water from the sedimentation separation tank. Alternatively, it is possible to prevent the clad from being brought into the high-conductivity waste liquid collection tank.
【００３０】この結果、低電導度廃液系収集タンクの廃
液処理時に低電導度ろ過器に対する負荷が軽減できるた
め、ろ過器の逆洗操作の回数を抑えられると共に、沈降
分離槽のデカント移送後の低電導度廃液系収集タンクの
放射能の上昇を抑えることができるため、被ばく低減に
もなる。As a result, since the load on the low-conductivity filter can be reduced during the waste liquid treatment of the low-conductivity waste liquid system collection tank, the number of backwashing operations of the filter can be suppressed and the decanting of the sedimentation separation tank can be performed. Since the increase in radioactivity of the low conductivity waste liquid collection tank can be suppressed, the exposure can be reduced.
【００３１】また、高電導度廃液系収集タンクにおいて
も、高濃度クラッドが濃縮器により濃縮され、その後濃
縮廃液系を介してプラスチック固化を行う際に生じる各
種問題（廃液性状により機器の過負荷トリップまたは固
化時の高放射線による被ばく等）が解消される。Also in the high-conductivity waste liquid system collection tank, various problems that occur when the high-concentration clad is concentrated by the concentrator and then the plastic is solidified through the concentrated waste liquid system (device overload trip due to waste liquid property) Or, exposure to high radiation during solidification) is eliminated.
【図１】本発明に係る放射性廃棄物処理設備用逆洗水受
タンクまたは沈降分離槽の一実施例が設置された状態を
示す系統図。FIG. 1 is a system diagram showing a state in which an embodiment of a backwash water receiving tank or sedimentation separation tank for radioactive waste treatment equipment according to the present invention is installed.
【図２】図１における強制沈降分離槽内に磁石を設けた
例を概略的に示す縦断面図。2 is a longitudinal sectional view schematically showing an example in which a magnet is provided in the forced sedimentation separation tank in FIG.
【図３】従来の放射性廃棄物処理設備を示す系統図。FIG. 3 is a system diagram showing a conventional radioactive waste treatment facility.
１…原子炉圧力容器、２…タービン、３…ホットウェル
（復水器）、４…復水ろ過装置、５…復水脱塩装置、６
…原子炉冷却材浄化系ろ過脱塩装置（ＣＵＷ（Ｆ／
Ｄ））、７…逆洗水受タンク、８…沈降分離槽、９…低
電導度廃液系収集タンク、10…低電導度廃液系ろ過器、
11…高電導度廃液系収集タンク、12…濃縮器、13…固化
系、14…加温ヒータ、15…バブリング用スパージャ、16
…酸化剤（凝集剤）注入装置、17…攪拌機、18…磁石。1 ... Reactor pressure vessel, 2 ... Turbine, 3 ... Hot well (condenser), 4 ... Condensate filter, 5 ... Condensate desalination unit, 6
... Reactor coolant purification system filter desalination unit (CUW (F /
D)), 7 ... Backwash water receiving tank, 8 ... Sedimentation separation tank, 9 ... Low-conductivity waste liquid-based collection tank, 10 ... Low-conductivity waste liquid-based filter,
11 ... High-conductivity waste liquid collection tank, 12 ... Concentrator, 13 ... Solidification system, 14 ... Heater, 15 ... Bubbling sparger, 16
… Oxidizing agent (coagulant) injection device, 17… Stirrer, 18… Magnet.
───────────────────────────────────────────────────── フロントページの続き (72)発明者 長沢 克己 神奈川県川崎市幸区堀川町66番２ 東芝エ ンジニアリング株式会社内 ─────────────────────────────────────────────────── ─── Continuation of the front page (72) Inventor Katsumi Nagasawa 66-2 Horikawa-cho, Saiwai-ku, Kawasaki-shi, Kanagawa Toshiba Engineering Co., Ltd.
Claims (5)
水器で復水とし、その復水を復水ろ過装置および復水脱
塩装置で浄化し原子炉圧力容器へ給水する系統と前記原
子炉圧力容器に接続した原子炉冷却材浄化系とを有し、
前記復水ろ過装置を逆洗水受タンクを経由し沈降分離槽
へ接続し、この沈降分離槽に前記復水脱塩装置および低
電導度廃液系ろ過装置を接続し、前記復水ろ過装置の逆
洗水を前記逆洗水受タンクに移送した後前記沈降分離槽
に移送し前記復水脱塩装置の逆洗水を前記沈降分離槽に
移送するように配管接続してなる放射性廃棄物処理系設
備において、前記逆洗水受タンクおよび沈降分離槽に酸
化剤または凝集剤注入装置を接続してなることを特徴と
する放射性廃棄物処理系設備。1. A system for converting steam from a reactor pressure vessel into condensate by a turbine condenser, purifying the condensate with a condensate filter and a condensate demineralizer, and supplying the water to the reactor pressure vessel, and the atom. Having a reactor coolant purification system connected to the reactor pressure vessel,
The condensate filter is connected to a settling separation tank via a backwash water receiving tank, and the condensate demineralizer and the low-conductivity waste liquid system filter are connected to this settling separation tank, Radioactive waste treatment in which pipes are connected so that the backwash water is transferred to the backwash water receiving tank and then to the sedimentation separation tank, and the backwash water of the condensate demineralizer is transferred to the sedimentation separation tank In the system equipment, a radioactive waste treatment system equipment characterized in that an oxidant or coagulant injection device is connected to the backwash water receiving tank and the sedimentation separation tank.
に、空気バブリング装置を設けてなることを特徴とする
請求項１記載の放射性廃棄物処理系設備。2. The radioactive waste treatment system facility according to claim 1, wherein the backwash water receiving tank and the sedimentation separation tank are provided with an air bubbling device.
に、加熱ヒータを設けてなることを特徴とする請求項１
記載の放射性廃棄物処理系設備。3. A heater is provided in the backwash water receiving tank and the sedimentation separation tank.
The listed radioactive waste treatment system equipment.
に、磁石を設けてなることを特徴とする請求項１記載の
放射性廃棄物処理系設備。4. The radioactive waste treatment system facility according to claim 1, wherein the backwash water receiving tank and the sedimentation tank are provided with magnets.
気系または計装用圧縮空気系とガスバブリング用スパー
ジャからなることを特徴とする請求項２記載の放射性廃
棄物処理系設備。5. The radioactive waste treatment system facility according to claim 2, wherein the air bubbling device comprises a compressed air system for a facility or a compressed air system for instrumentation and a sparger for gas bubbling.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP7134961A JPH08327789A (en) | 1995-06-01 | 1995-06-01 | Equipment for radioactive waste processing system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP7134961A JPH08327789A (en) | 1995-06-01 | 1995-06-01 | Equipment for radioactive waste processing system |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH08327789A true JPH08327789A (en) | 1996-12-13 |
Family
ID=15140637
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP7134961A Pending JPH08327789A (en) | 1995-06-01 | 1995-06-01 | Equipment for radioactive waste processing system |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH08327789A (en) |
Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2000121785A (en) * | 1998-10-16 | 2000-04-28 | Hitachi Ltd | Reactor power plant and its operation method |
| JP2001324593A (en) * | 2000-05-18 | 2001-11-22 | Japan Organo Co Ltd | Radioactive waste treatment system for boiling water type nuclear power plant |
| JP2007199023A (en) * | 2006-01-30 | 2007-08-09 | Toshiba Corp | Ion-exchange resin processing method, ion-exchange resin pulverizing system, decontamination apparatus, nuclear power station, decontamination apparatus modifying method and nuclear power station modifying method |
| JP2011512531A (en) * | 2008-02-18 | 2011-04-21 | コミッサリア ア ロンネルジー アトミック エ オ ゾンネルジー ザルテルナティーフ | The process of decontaminating radioactive liquid effluent to one or more radioactive chemical elements by solid-liquid extraction using a recycling loop |
| JP2012032155A (en) * | 2010-07-28 | 2012-02-16 | Hitachi-Ge Nuclear Energy Ltd | Radioactive waste treatment method and apparatus therefor |
| JP2012037270A (en) * | 2010-08-04 | 2012-02-23 | Hitachi-Ge Nuclear Energy Ltd | Radioactive waste liquid processor |
| JP2018179834A (en) * | 2017-04-17 | 2018-11-15 | 日立Ｇｅニュークリア・エナジー株式会社 | System and method for removing radioactive particles in fluid |
| CN109300565A (en) * | 2018-10-20 | 2019-02-01 | 中广核研究院有限公司 | Radioactive substance removes system and method in a kind of coolant |
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-
1995
- 1995-06-01 JP JP7134961A patent/JPH08327789A/en active Pending
Cited By (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2000121785A (en) * | 1998-10-16 | 2000-04-28 | Hitachi Ltd | Reactor power plant and its operation method |
| JP2001324593A (en) * | 2000-05-18 | 2001-11-22 | Japan Organo Co Ltd | Radioactive waste treatment system for boiling water type nuclear power plant |
| JP2007199023A (en) * | 2006-01-30 | 2007-08-09 | Toshiba Corp | Ion-exchange resin processing method, ion-exchange resin pulverizing system, decontamination apparatus, nuclear power station, decontamination apparatus modifying method and nuclear power station modifying method |
| JP4679377B2 (en) * | 2006-01-30 | 2011-04-27 | 株式会社東芝 | Ion exchange resin treatment method, ion exchange resin atomization system, decontamination equipment, nuclear power plant, decontamination equipment modification method, and nuclear power plant modification method |
| JP2011512531A (en) * | 2008-02-18 | 2011-04-21 | コミッサリア ア ロンネルジー アトミック エ オ ゾンネルジー ザルテルナティーフ | The process of decontaminating radioactive liquid effluent to one or more radioactive chemical elements by solid-liquid extraction using a recycling loop |
| JP2012032155A (en) * | 2010-07-28 | 2012-02-16 | Hitachi-Ge Nuclear Energy Ltd | Radioactive waste treatment method and apparatus therefor |
| JP2012037270A (en) * | 2010-08-04 | 2012-02-23 | Hitachi-Ge Nuclear Energy Ltd | Radioactive waste liquid processor |
| JP2018179834A (en) * | 2017-04-17 | 2018-11-15 | 日立Ｇｅニュークリア・エナジー株式会社 | System and method for removing radioactive particles in fluid |
| CN109300565A (en) * | 2018-10-20 | 2019-02-01 | 中广核研究院有限公司 | Radioactive substance removes system and method in a kind of coolant |
| CN109300565B (en) * | 2018-10-20 | 2024-01-19 | 中广核研究院有限公司 | System and method for removing radioactive substances in coolant |
| CN109849238A (en) * | 2019-03-28 | 2019-06-07 | 江苏核电有限公司 | A kind of radioactive spent resin grinding system with redundant apparatus |
| CN109849238B (en) * | 2019-03-28 | 2024-05-10 | 江苏核电有限公司 | Radioactive waste resin grinding system with redundant device |
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