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JPH0778556B2 - Dewatering method for powdery radioactive waste - Google Patents
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JPH0778556B2 - Dewatering method for powdery radioactive waste - Google Patents

Dewatering method for powdery radioactive waste

Info

Publication number
JPH0778556B2
JPH0778556B2 JP24837091A JP24837091A JPH0778556B2 JP H0778556 B2 JPH0778556 B2 JP H0778556B2 JP 24837091 A JP24837091 A JP 24837091A JP 24837091 A JP24837091 A JP 24837091A JP H0778556 B2 JPH0778556 B2 JP H0778556B2
Authority
JP
Japan
Prior art keywords
tank
radioactive waste
powdery
dehydration
granular
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
Application number
JP24837091A
Other languages
Japanese (ja)
Other versions
JPH0587984A (en
Inventor
進 武藤
英樹 山田
喜三郎 幸村
正充 寺本
正人 松田
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
NGK Insulators Ltd
Toyota Motor Corp
Original Assignee
NGK Insulators Ltd
Toyota Motor Corp
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by NGK Insulators Ltd, Toyota Motor Corp filed Critical NGK Insulators Ltd
Priority to JP24837091A priority Critical patent/JPH0778556B2/en
Publication of JPH0587984A publication Critical patent/JPH0587984A/en
Publication of JPH0778556B2 publication Critical patent/JPH0778556B2/en
Anticipated expiration legal-status Critical
Expired - Fee Related legal-status Critical Current

Links

Landscapes

  • Centrifugal Separators (AREA)
  • Processing Of Solid Wastes (AREA)
  • Treatment Of Sludge (AREA)

Description

【発明の詳細な説明】Detailed Description of the Invention

【0001】[0001]

【産業上の利用分野】本発明は原子力発電所の排水処理
等に使用されたイオン交換樹脂のような粉粒状放射性廃
棄物の脱水方法に関するものである。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a method for dehydrating powdery radioactive waste such as ion exchange resin used for wastewater treatment of nuclear power plants.

【0002】[0002]

【従来の技術】廃イオン交換樹脂のような粉粒状放射性
廃棄物は焼却炉に投入して焼却処分されているが、水中
で使用されているために多量の水分を含有したスラリー
状態にあり、焼却炉の負荷を軽減するために焼却に先立
って脱水する必要がある。このために従来は底面をメッ
シュ状としたスクリューコンベヤを使用し、焼却炉への
搬送の途中で脱水を行う等の工夫がなされているが、自
重による自然脱水であるために十分な脱水を行うことが
できなかった。
2. Description of the Related Art A granular radioactive waste such as waste ion exchange resin is put into an incinerator for incineration, but since it is used in water, it is in a slurry state containing a large amount of water, It is necessary to dehydrate before incineration to reduce the load on the incinerator. For this reason, conventionally, a screw conveyor with a mesh bottom has been used and dehydration is carried out during the transportation to the incinerator, but sufficient dehydration is performed because it is natural dehydration due to its own weight. I couldn't.

【0003】そこで脱水をより十分に行うために、遠心
脱水機を利用する試みもなされているが、遠心脱水機を
使用する場合には過負荷防止や閉塞防止のために内部に
供給されるスラリー濃度や供給量についてのシビアなコ
ントロールが必要である。ところが現実にはこれらの量
は大きく変動するため、遠心脱水機を完全自動化ライン
に組み込むことは困難であった。更に遠心脱水機は脱水
された粉粒状放射性廃棄物の排出にトラブルが生じ易
く、洗浄も容易ではないのでしばしば分解修理の必要が
ある等の問題があった。
Therefore, attempts have been made to utilize a centrifugal dehydrator in order to perform dehydration more sufficiently, but when a centrifugal dehydrator is used, a slurry is supplied to the inside to prevent overload and blockage. Strict control of concentration and supply is required. However, in reality, since these amounts fluctuate greatly, it was difficult to incorporate the centrifugal dehydrator into a fully automated line. Further, the centrifugal dehydrator is liable to cause troubles in discharging the dehydrated powdery and granular radioactive waste and is not easy to wash, so that there is a problem that it is often necessary to disassemble and repair.

【0004】[0004]

【発明が解決しようとする課題】本発明は上記した従来
の問題点を解消し、イオン交換樹脂のような粉粒状放射
性廃棄物を自動的に十分に脱水することができ、しかも
閉塞による排出困難等を生じることのない粉粒状放射性
廃棄物の脱水方法を提供するために完成されたものであ
る。
DISCLOSURE OF THE INVENTION The present invention solves the above-mentioned problems of the prior art, and is capable of automatically dehydrating powdered and radioactive waste such as ion exchange resin, and is difficult to discharge due to blockage. The present invention has been completed to provide a method for dehydrating powdery and granular radioactive waste that does not cause the above.

【0005】[0005]

【課題を解決するための手段】上記の課題を解決するた
めになされた本発明は、水中に分散した粉粒状放射性廃
棄物を脱水用のタンクの内部に供給し、タンク上部から
導入した圧縮空気の圧力によりタンク底面から水分を除
去し、次にタンク内部の回転羽根を回転してスラッジの
表面を平滑化したうえ圧縮空気の圧力により更に脱水
し、その後回転羽根を逆転させて脱水された粉粒状放射
性廃棄物をタンクの底面中央から排出することを特徴と
するものである。
DISCLOSURE OF THE INVENTION The present invention, which has been made to solve the above-mentioned problems, provides compressed air introduced from the upper part of a tank by supplying powdery granular radioactive waste dispersed in water to the inside of a tank for dehydration. To remove water from the bottom of the tank by rotating the rotary blades inside the tank to smooth the surface of the sludge and dehydrate it further with the pressure of compressed air. The feature is that the granular radioactive waste is discharged from the center of the bottom surface of the tank.

【0006】[0006]

【実施例】以下に本発明を図示の実施例により更に詳細
に説明する。図1において、1は水中に分散した廃イオ
ン交換樹脂のような粉粒状放射性廃棄物を貯留している
貯留槽、2は断面円形状の脱水用のタンク、3は脱水さ
れた粉粒状放射性廃棄物の供給機、4は焼却炉である。
貯留槽1の内部には多量の粉粒状放射性廃棄物のスラリ
ーが貯留されており、ポンプ5によって脱水用のタンク
2内へ供給される。
The present invention will be described in more detail below with reference to the embodiments shown in the drawings. In FIG. 1, 1 is a storage tank for storing powdery and granular radioactive waste such as waste ion exchange resin dispersed in water, 2 is a dehydrating tank having a circular cross section, 3 is dehydrated powdery and granular radioactive waste The material feeder 4 is an incinerator.
A large amount of powdery granular radioactive waste slurry is stored in the storage tank 1, and is supplied by the pump 5 into the dehydration tank 2.

【0007】図2に拡大して示したように、脱水用のタ
ンク2の底面にはスクリーン6が張ってある。またタン
ク2の底面中央には、図示を略した機構により昇降でき
る筒7と、筒7の上端を封止できる昇降することのない
キャップ8とが設けられている。更にタンク2の天井の
中央から垂下した軸9の下端には水平アームを介して多
数の回転羽根10が設けられている。これらの回転羽根10
はタンク2の半径線に対して斜めになっており、軸9を
タンク2の上方から見て反時計方向に回転させたときに
タンク2内の粉粒状放射性廃棄物を中央の筒7の方向へ
かき寄せることができる構造となっている。次に本発明
の脱水方法を図3により詳細に説明する。
As shown enlarged in FIG. 2, a screen 6 is stretched on the bottom surface of the dehydrating tank 2. At the center of the bottom surface of the tank 2, there are provided a cylinder 7 that can be moved up and down by a mechanism (not shown), and a cap 8 that can seal the upper end of the cylinder 7 and that does not move up and down. Further, a large number of rotary blades 10 are provided at the lower end of a shaft 9 hanging from the center of the ceiling of the tank 2 via a horizontal arm. These rotary blades 10
Is inclined with respect to the radial line of the tank 2, and when the shaft 9 is rotated counterclockwise as viewed from above the tank 2, the granular radioactive waste in the tank 2 is directed toward the central cylinder 7. It has a structure that can be scraped. Next, the dehydration method of the present invention will be described in detail with reference to FIG.

【0008】まず図3のA,Bに示すように、筒7をキ
ャップ8に密着するまで上昇させた状態で脱水用のタン
ク2の内部に粉粒状放射性廃棄物のスラリーを供給す
る。タンク2の底面はスクリーン6が張ってあるためそ
のままでもスラリー中の水分は自重により徐々に抜けて
行くが、本発明ではタンク2の上部から圧縮空気を供給
することにより強制的に水分を排出させる。
First, as shown in FIGS. 3A and 3B, a slurry of powdery radioactive waste is supplied into the dewatering tank 2 in a state where the cylinder 7 is raised until it comes into close contact with the cap 8. Since the screen 6 is stretched on the bottom surface of the tank 2, the water content in the slurry gradually escapes due to its own weight even if it is left as is. .

【0009】このような強制脱水を行うと、図3のCの
ようにスクリーン6上に残った粉粒状放射性廃棄物の表
面に次第にひび割れが入り、このひびの部分から圧縮空
気がパスしてしまうために脱水が進行できなくなる。そ
こで本発明では図3のDのように回転羽根10を粉粒状放
射性廃棄物の表面に接するまで下降させ回転することに
より、ひび割れした粉粒状放射性廃棄物の表面を平滑化
したうえ図3のEのようにタンク2の上部から更に圧縮
空気を供給する。この結果、ひび割れからの圧縮空気の
パスを防止することができるので、全表面に均一に空気
圧が作用し、より十分な脱水が行われることとなる。
When such forced dehydration is carried out, cracks gradually form on the surface of the powdery radioactive waste remaining on the screen 6 as shown in FIG. 3C, and compressed air passes through the cracked portions. Therefore, dehydration cannot proceed. Therefore, in the present invention, as shown in FIG. 3D, the rotary vane 10 is lowered and rotated until it comes into contact with the surface of the powdery radioactive waste, thereby smoothing the surface of the cracked powdery radioactive waste and E of FIG. Compressed air is further supplied from the upper part of the tank 2 as described above. As a result, the compressed air can be prevented from passing through the cracks, so that the air pressure is uniformly applied to the entire surface, and more sufficient dehydration is performed.

【0010】その後、図3のFのように回転羽根10を上
昇させ、また中央の筒7をその上端がタンク2の底面と
一致する高さまで下降させる。そして回転羽根10を逆転
させると、十分に脱水された粉粒状放射性廃棄物はその
表面から次第に中央の筒7の方向に掻き寄せられ、筒7
を通じて供給機3へ排出される。実施例では、Cの段階
における粉粒状放射性廃棄物の水分は65〜67%程度であ
ったが、D,Eの段階を経ると粉粒状放射性廃棄物の水
分を55〜60%程度まで低下させることができる。この値
は、遠心脱水機を利用した場合の水分58〜64%よりも更
に低いものである。
After that, the rotary vane 10 is raised as shown by F in FIG. 3, and the central cylinder 7 is lowered to a height such that the upper end thereof coincides with the bottom surface of the tank 2. Then, when the rotary blades 10 are reversed, the sufficiently dehydrated powdery radioactive waste is gradually scraped from its surface toward the central cylinder 7 to form the cylinder 7
Is discharged to the feeder 3 through. In the example, the water content of the granular radioactive waste in the stage C was about 65 to 67%, but the water content of the granular radioactive waste was reduced to about 55 to 60% after the stages D and E. be able to. This value is lower than the water content of 58 to 64% when the centrifugal dehydrator is used.

【0011】なお、図1に示すようにタンク2の上面に
超音波レベルメータのような高さ計11を取り付けてお
き、タンク2内に堆積したスラリーのレベルを検知しつ
つポンプ5によるスラリーの供給量を制御することが好
ましい。このような制御は、スラリーの濃度が変化し易
い実ラインにおいて全自動的にかつ効率的に脱水を行わ
せるために有効なものである。
As shown in FIG. 1, a height meter 11 such as an ultrasonic level meter is attached to the upper surface of the tank 2 to detect the level of the slurry accumulated in the tank 2 and to detect the slurry level by the pump 5. It is preferable to control the supply amount. Such control is effective for fully automatically and efficiently performing dehydration in a real line where the slurry concentration is likely to change.

【0012】[0012]

【発明の効果】以上に説明したように、本発明の粉粒状
放射性廃棄物の脱水方法によれば、イオン交換樹脂のよ
うな粉粒状放射性廃棄物を自動的に十分に脱水すること
ができ、しかも遠心脱水機のような閉塞による排出困難
等を生じることがない。よって本発明は従来の問題点を
解消した廃イオン交換樹脂のような粉粒状放射性廃棄物
の脱水方法として、産業の発展に寄与するところは極め
て大きいものである。
As described above, according to the method for dehydrating powdery and granular radioactive waste of the present invention, powdery and granular radioactive waste such as ion exchange resin can be automatically and sufficiently dehydrated. In addition, there is no problem such as the centrifugal dehydrator that is difficult to discharge due to blockage. Therefore, the present invention has an extremely great contribution to industrial development as a method of dehydrating powdery radioactive waste such as waste ion-exchange resin that solves the conventional problems.

【図面の簡単な説明】[Brief description of drawings]

【図1】本発明の実施例を示す一部切欠正面図である。FIG. 1 is a partially cutaway front view showing an embodiment of the present invention.

【図2】タンク部分の断面図である。FIG. 2 is a sectional view of a tank portion.

【図3】本発明の脱水工程を示す断面図である。FIG. 3 is a cross-sectional view showing a dehydration process of the present invention.

【符号の説明】[Explanation of symbols]

2 脱水用のタンク 10 回転羽根 2 Tank for dehydration 10 rotating blades

───────────────────────────────────────────────────── フロントページの続き (72)発明者 幸村 喜三郎 愛知県海部郡弥富町大字鯏浦字西前新田86 番地の12 (72)発明者 寺本 正充 愛知県海部郡美和町大字木田字池の島93番 地 (72)発明者 松田 正人 三重県桑名市大字蛎塚新田866番地 (56)参考文献 特開 昭53−43200(JP,A) 特開 昭55−16282(JP,A) 特開 昭61−251798(JP,A) 特開 昭54−75000(JP,A) ─────────────────────────────────────────────────── ─── Continuation of the front page (72) Inventor Kisaburo Yukimura Ai Prefecture Yabu Town Yabu Town Dairaura, Urauraji 86, Nishimae Nitta 12 (72) Inventor Masamitsu Teramoto Miwa, Kaifu-gun Aichi Prefecture Kida character Ikenoshima No. 93 (72) Masato Matsuda Masato Matsuda, 866 Kanji, Nikkazuka, Kuwana, Mie Prefecture (56) Reference JP-A-53-43200 (JP, A) JP-A-55-16182 (JP, A) JP 61-251798 (JP, A) JP 54-75000 (JP, A)

Claims (1)

【特許請求の範囲】[Claims] 【請求項1】 水中に分散した粉粒状放射性廃棄物を脱
水用のタンクの内部に供給し、タンク上部から導入した
圧縮空気の圧力によりタンク底面から水分を除去し、次
にタンク内部の回転羽根を回転してスラッジの表面を平
滑化したうえ圧縮空気の圧力により更に脱水し、その後
回転羽根を逆転させて脱水された粉粒状放射性廃棄物を
タンクの底面中央から排出することを特徴とする粉粒状
放射性廃棄物の脱水方法。
1. A particulate radioactive waste dispersed in water is supplied to the inside of a tank for dehydration, water is removed from the bottom of the tank by the pressure of compressed air introduced from the top of the tank, and then rotary blades inside the tank. Is rotated to smooth the surface of the sludge and further dehydrated by the pressure of compressed air, and then the rotary vanes are reversed to discharge the dehydrated powdery granular radioactive waste from the center of the bottom surface of the tank. Method for dehydrating granular radioactive waste.
JP24837091A 1991-09-02 1991-09-02 Dewatering method for powdery radioactive waste Expired - Fee Related JPH0778556B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP24837091A JPH0778556B2 (en) 1991-09-02 1991-09-02 Dewatering method for powdery radioactive waste

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP24837091A JPH0778556B2 (en) 1991-09-02 1991-09-02 Dewatering method for powdery radioactive waste

Publications (2)

Publication Number Publication Date
JPH0587984A JPH0587984A (en) 1993-04-09
JPH0778556B2 true JPH0778556B2 (en) 1995-08-23

Family

ID=17177092

Family Applications (1)

Application Number Title Priority Date Filing Date
JP24837091A Expired - Fee Related JPH0778556B2 (en) 1991-09-02 1991-09-02 Dewatering method for powdery radioactive waste

Country Status (1)

Country Link
JP (1) JPH0778556B2 (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP5651885B2 (en) * 2011-03-30 2015-01-14 日本碍子株式会社 Ion exchange resin volume reduction treatment system and ion exchange resin volume reduction treatment method
CN103426493B (en) * 2012-05-14 2017-04-05 中国辐射防护研究院 The drip of radioactive spent resin free water is except device and drip are except method

Also Published As

Publication number Publication date
JPH0587984A (en) 1993-04-09

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