JPS59128496A - Cleanup system for cement solidification device of radioactive liquid waste - Google Patents
Cleanup system for cement solidification device of radioactive liquid wasteInfo
- Publication number
- JPS59128496A JPS59128496A JP376483A JP376483A JPS59128496A JP S59128496 A JPS59128496 A JP S59128496A JP 376483 A JP376483 A JP 376483A JP 376483 A JP376483 A JP 376483A JP S59128496 A JPS59128496 A JP S59128496A
- Authority
- JP
- Japan
- Prior art keywords
- waste liquid
- cement
- cleaning system
- cleaning
- radioactive waste
- 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
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】
本発明は、放射性廃液のセメント固化処理装置の洗浄シ
ステムの改良に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to an improvement in a cleaning system for a radioactive waste liquid cement solidification treatment apparatus.
原子力設備、とくに発電プラントから排出され、ＰＭ射
性廃液を・濃縮により減容してセメント固化法により固
化処理する場合、セメント混線装置はモルタルの容器へ
の充填が終了したら、水洗いしなければならない。 放
置しておくと、装置に付着したモルタルが凝結して放射
能の表面線量が高くなったり、装置の稼動不良をおこす
おそれがあるからである。When PM radioactive waste liquid discharged from nuclear facilities, especially power plants, is reduced in volume through concentration and solidified using the cement solidification method, the cement mixer must be washed with water after filling the container with mortar. . If left as is, there is a risk that the mortar adhering to the equipment will condense, increasing the surface dose of radioactivity and causing malfunction of the equipment.
従来の放射性廃液セメント固化処理装置とその洗浄シス
テムは、一般に第１図に示すようなものであって、濃縮
廃液タンク１の濃縮された廃液を、セメント混線装置２
でセメントＣｍと混合してセメントペーストとし、ドラ
ム缶３に充填（る。A conventional radioactive waste liquid cement solidification treatment apparatus and its cleaning system are generally as shown in FIG.
It is mixed with cement Cm to form a cement paste and filled into a drum 3.
充填作業が終ったならば、外部からプラント用水Ｗを導
入してセメント混線装置２を洗浄し、洗浄水は第一の洗
浄水タンク４に受けて静置し、上澄み水を第二の洗浄水
タンク６に移送する。 第一の洗浄タンク４のセメント
沈でん物は、ボトムから扱き出し、ドラム缶５に充填す
る。 第二の洗浄水タンク６の水は、不足分を補充して
次の洗浄に使用する。When the filling work is completed, plant water W is introduced from outside to clean the cement mixer 2, the cleaning water is received in the first cleaning water tank 4 and left standing, and the supernatant water is transferred to the second cleaning water. Transfer to tank 6. The cement sediment in the first cleaning tank 4 is taken out from the bottom and filled into a drum 5. The water in the second wash water tank 6 is used to replenish the water for the next wash.
この洗浄システムは、設備として洗浄水を受ける２個の
タンクと、ドラム缶５への充填装置を余分に必要とする
。 ドラム缶５に充填されるセメント沈でん物の固化体
は、組成が均一でなく水分が過大であるから、強度その
他の物性が劣る。This cleaning system requires two additional tanks for receiving cleaning water and a device for filling the drum 5. The solidified cement precipitate filled in the drum 5 has a non-uniform composition and contains too much water, so it has poor strength and other physical properties.
最大の欠点は、プラント用水を導入使用するので、廃棄
物量が増大することにある。The biggest drawback is that the amount of waste increases because plant water is introduced and used.
本発明はこのような問題を解決し、洗浄排水の処理設備
を不要にし、すべてのセメント固化体が良好な物性をも
って得られ、かつ外部から用水を導入しないクローズド
システムとすることによって廃棄物量の増大を避けた洗
浄システムを提供づる。The present invention solves these problems, eliminates the need for treatment equipment for washing wastewater, provides a closed system in which all solidified cement products have good physical properties, and does not introduce water from outside, thereby reducing the amount of waste. We provide a cleaning system that avoids
本発明の放射性廃液セメント固化処理装置の洗浄システ
ムは、放射性廃液をセメントと混練し容器に充填するセ
メント固化処理装置の洗浄システムであって、セメント
混練装置の洗浄に放射性廃液を使用し、洗浄後の廃液も
セメント−固化処理することを特徴とする。The radioactive waste fluid cement solidification processing equipment cleaning system of the present invention is a cleaning system for a cement solidification processing equipment that mixes radioactive waste fluid with cement and fills it into a container, in which the radioactive waste fluid is used to clean the cement kneading equipment, and after cleaning, The waste liquid is also subjected to cement solidification treatment.
原子力設備がＰＷＲ型発電プラントである場合に、推奨
り°べさ本発明の実施態様は、第２図に示すフローをと
る。 濃縮した廃液はタンク１から前処理槽１１に送り
、そこでカルシウム化合物を加えて、廃液に含まれてい
るホウ酸と反応させて不溶性の塩を析出させ、ついで熟
成により析出物を沈降性のスラリーとし、濃縮装＠１２
において濃縮した上で、混線装置２に送ってセメントペ
ーストとし、ドラム缶３に充填する。 上記のカルシウ
ム化合物の添加による不溶性塩の析出は、ホウ酸塩含有
廃液に適する処理法として、本発明者らがさきに開発し
、すでに提案したところである（特願昭５７−１２０７
９１号）。 なお、ここで濃縮工程に固液分離を行なっ
て分離液を蒸発する方法を採用づれば、蒸発濃縮装置内
に不溶性の塩がもち込まれないので伝熱面へのスケール
付着が軽減され、蒸発濃縮の効率の低下が避けられる。When the nuclear power facility is a PWR type power plant, the recommended embodiment of the present invention follows the flow shown in FIG. Concentrated waste liquid is sent from tank 1 to pretreatment tank 11, where a calcium compound is added and reacted with boric acid contained in the waste liquid to precipitate insoluble salts, and then aged to convert the precipitate into a sedimentary slurry. Concentrator@12
After being concentrated, it is sent to a crosstalk device 2 to be made into cement paste, and the cement paste is filled into a drum 3. The above-mentioned precipitation of insoluble salts by addition of calcium compounds was previously developed and proposed by the present inventors as a treatment method suitable for borate-containing waste liquid (Japanese Patent Application No. 57-1207
No. 91). In addition, if a method is adopted in which solid-liquid separation is performed in the concentration process and the separated liquid is evaporated, insoluble salts will not be brought into the evaporative concentration device, reducing scale adhesion to the heat transfer surface, and the evaporation concentration will be reduced. A decrease in efficiency is avoided.
混線装置２の洗浄は、タンク１からの廃液を、第２図に
おける太線のラインをへて導入して行ない、洗浄後の廃
液はボトムから太線のラインをへて前処理槽１１へ送り
、前記したところと同じカルシウム化合物の添加による
処理をイラない、淵縮装置占１２へ供給して濃縮する。The crosstalk device 2 is cleaned by introducing the waste liquid from the tank 1 through the thick line in FIG. The same treatment as above with the addition of a calcium compound is not required, and the product is fed to the deep condensation device 12 and concentrated.
ホウ酸塩が存在するとセメントの凝結がおくれるので
、前処理槽内でセメントが固結することはなく、さらに
セメントが添加するカルシウム化合物と同様な効果を示
し、不溶性ホウ酸塩の析出に役立つ。The presence of borates slows down the setting of the cement, so the cement does not set in the pretreatment tank, and the cement also has a similar effect to added calcium compounds, helping to precipitate insoluble borates. .
洗浄後の廃液を上記のように処理して得１＝セメント同
化体の物性は、洗浄に用いてない廃液を処理して得たセ
メント同化体のそれと異なるところはなく、圧縮強度で
いえば、２８日養生後で 、２３０Ｋ（］ ／ａｍ
、３力月後には２６０Ｋｇ／Ｃｍ２に達した。The physical properties of the assimilated cement obtained by treating the waste liquid after washing as described above are the same as those of the assimilated cement obtained by treating the waste liquid not used for washing, and in terms of compressive strength, After 28 days curing, 230K(]/am
After 3 months, it reached 260Kg/Cm2.
この洗浄システムでは、洗浄用水を外部から導入しない
ですむだけでなく、洗浄後の廃液が濃縮されるので、廃
棄物容積の増加を避ける効果が大きい。This cleaning system not only eliminates the need to introduce cleaning water from the outside, but also concentrates the waste liquid after cleaning, which is highly effective in preventing an increase in waste volume.
原子ノｊ設備がＢＷＲ型発電プラントである場合にも、
本発明の洗浄システムは適用できる。 その実施態様の
フローは、第３図に示すとおりである。Even if the atomic energy facility is a BWR type power plant,
The cleaning system of the present invention is applicable. The flow of this embodiment is as shown in FIG.
濃縮廃液は、タンク１から直接混練装置２に入り、セメ
ントＣｍと混練され、ドラム缶３に充填される。 続い
て濃縮廃液を混練装置に入れ、攪拌して洗浄する。The concentrated waste liquid enters the kneading device 2 directly from the tank 1, is kneaded with the cement Cm, and is filled into the drum 3. Subsequently, the concentrated waste liquid is put into a kneading device, stirred, and washed.
洗浄に用いた廃液は、計量タンク２１に移し、次の廃液
のセメント固化に際して、それとあわせて混練装置へ供
給して処理する。The waste liquid used for cleaning is transferred to the measuring tank 21, and when the next waste liquid is solidified with cement, it is also supplied to the kneading device for treatment.
洗浄廃液を含む廃液のセメント同化体の物性は洗浄廃液
を含まない廃液からの同化体と同等である。The physical properties of cement assimilates from waste fluids containing cleaning waste fluids are the same as those from waste fluids that do not contain cleaning waste fluids.
第１図は従来の洗浄システムのフローチャートである。
第２図および第３図は本発明の洗浄システムのフローチ
ャートであって、第２図はＰＷＲ型発電プラントからの
放射性廃液のセメント固化装置に適する洗浄システム、
第３図はＢＷＲ型発電プラントからの放射性廃液のセメ
ント固化装置に適する洗浄システムをそれぞれ示す。
１・・・・・・濃縮廃液タンク
２・・・・・・混練装置
３・・・・・・ドラム缶
１１・・・・・・前処理槽 １２・・・・・・濃縮装
置２１・・・・・・計量タンク
Ｗ・・・・・・プラント用水 Ｃｍ・・・・・・セメ
ント特許出願人 日 揮 性 式 会 社代理人 弁
理士 須 賀 総 夫FIG. 1 is a flowchart of a conventional cleaning system. 2 and 3 are flowcharts of the cleaning system of the present invention, in which FIG. 2 shows a cleaning system suitable for a cement solidification device for radioactive waste liquid from a PWR power plant;
FIG. 3 each shows a cleaning system suitable for a cement solidification device for radioactive waste liquid from a BWR type power plant. 1... Concentrated waste liquid tank 2... Kneading device 3... Drum can 11... Pretreatment tank 12... Concentrating device 21... ...Measuring tank W...Plant water Cm...Cement patent applicant Date Volatile formula Company representative Patent attorney Souo Suga
Claims (1)
セメント固化処理装置の洗浄システムであって、セメン
ト混練装置の洗浄に放射性廃液を使用し、洗浄後の廃液
もセメント固化処理することを特徴とする洗浄システム
。 （２） 放射性廃液がＰＷＲ型発電プラン１〜から排出
されるホウ酸塩を含有するものであり、セメン１〜混線
に先立って廃液にカルシウム化合物を添加して不溶性塩
を析出させ、熟成してさらに濃縮する工程を含むセメン
ト固化処理装置の洗浄システムであって、洗浄後の廃液
を上記不溶性塩を析出熟成させる工程または濃縮工程に
戻して廃液とともに濃縮する特許請求の範囲第１項の洗
浄システム。 【３） 濃縮工程として固液分離および（または）蒸発
濃縮を行なう特許請求の範囲第２項の洗浄システム。 （４） 放射性廃液がＢＷＲ型発電プラントから排出さ
れる芒硝を主成分とするものである特許請求の範囲第１
項の洗浄システム。[Scope of Claims] (1) A cleaning system for a cement solidification processing equipment that mixes radioactive waste liquid with cement and fills it into a container, in which the radioactive waste liquid is used to clean the cement mixing equipment, and the waste liquid after cleaning is also solidified into cement. A cleaning system characterized by processing. (2) The radioactive waste liquid contains borate discharged from PWR power generation plan 1~, and prior to cement 1~ crosstalk, calcium compounds are added to the waste liquid to precipitate insoluble salts, and the waste liquid is aged. A cleaning system for a cement solidification processing device, which further includes a step of concentrating, the cleaning system according to claim 1, wherein the waste liquid after washing is returned to the step of precipitating and maturing the insoluble salts or the concentration step and concentrated together with the waste liquid. . [3] The cleaning system according to claim 2, which performs solid-liquid separation and/or evaporative concentration as the concentration step. (4) Claim 1 in which the radioactive waste liquid is mainly composed of mirabilite discharged from a BWR power generation plant.
section cleaning system.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP376483A JPS59128496A (en) | 1983-01-13 | 1983-01-13 | Cleanup system for cement solidification device of radioactive liquid waste |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP376483A JPS59128496A (en) | 1983-01-13 | 1983-01-13 | Cleanup system for cement solidification device of radioactive liquid waste |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS59128496A true JPS59128496A (en) | 1984-07-24 |
Family
ID=11566231
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP376483A Pending JPS59128496A (en) | 1983-01-13 | 1983-01-13 | Cleanup system for cement solidification device of radioactive liquid waste |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS59128496A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4904416A (en) * | 1987-05-21 | 1990-02-27 | Kyushu Electric Power Co., Ltd. | Cement solidification treatment of spent ion exchange resins |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS52116000A (en) * | 1976-03-25 | 1977-09-28 | Toray Eng Co Ltd | Purifying method for stirrer which mixes radioactive waste and cement |
| JPS53400A (en) * | 1976-06-24 | 1978-01-05 | Toray Eng Co Ltd | Washing method for mixing stirrer of radioactive waste and cement |
-
1983
- 1983-01-13 JP JP376483A patent/JPS59128496A/en active Pending
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS52116000A (en) * | 1976-03-25 | 1977-09-28 | Toray Eng Co Ltd | Purifying method for stirrer which mixes radioactive waste and cement |
| JPS53400A (en) * | 1976-06-24 | 1978-01-05 | Toray Eng Co Ltd | Washing method for mixing stirrer of radioactive waste and cement |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4904416A (en) * | 1987-05-21 | 1990-02-27 | Kyushu Electric Power Co., Ltd. | Cement solidification treatment of spent ion exchange resins |
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