JPS6232397A - Method of processing radioactive waste liquor - Google Patents
Method of processing radioactive waste liquorInfo
- Publication number
- JPS6232397A JPS6232397A JP17208685A JP17208685A JPS6232397A JP S6232397 A JPS6232397 A JP S6232397A JP 17208685 A JP17208685 A JP 17208685A JP 17208685 A JP17208685 A JP 17208685A JP S6232397 A JPS6232397 A JP S6232397A
- Authority
- JP
- Japan
- Prior art keywords
- waste liquid
- silica
- radioactive waste
- waste liquor
- exchange resin
- 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
- 238000000034 method Methods 0.000 title claims description 15
- 239000002901 radioactive waste Substances 0.000 title 1
- VYPSYNLAJGMNEJ-UHFFFAOYSA-N Silicium dioxide Chemical compound O=[Si]=O VYPSYNLAJGMNEJ-UHFFFAOYSA-N 0.000 claims description 25
- 239000007788 liquid Substances 0.000 claims description 15
- 239000000377 silicon dioxide Substances 0.000 claims description 12
- 239000002699 waste material Substances 0.000 claims description 9
- NWUYHJFMYQTDRP-UHFFFAOYSA-N 1,2-bis(ethenyl)benzene;1-ethenyl-2-ethylbenzene;styrene Chemical compound C=CC1=CC=CC=C1.CCC1=CC=CC=C1C=C.C=CC1=CC=CC=C1C=C NWUYHJFMYQTDRP-UHFFFAOYSA-N 0.000 claims description 8
- 239000003456 ion exchange resin Substances 0.000 claims description 8
- 229920003303 ion-exchange polymer Polymers 0.000 claims description 8
- 238000000108 ultra-filtration Methods 0.000 claims description 8
- 239000003463 adsorbent Substances 0.000 claims description 6
- KGBXLFKZBHKPEV-UHFFFAOYSA-N boric acid Chemical compound OB(O)O KGBXLFKZBHKPEV-UHFFFAOYSA-N 0.000 claims description 5
- 239000004327 boric acid Substances 0.000 claims description 5
- 239000000706 filtrate Substances 0.000 claims description 3
- 239000012535 impurity Substances 0.000 claims description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 12
- 238000007796 conventional method Methods 0.000 description 8
- 239000012528 membrane Substances 0.000 description 7
- 239000002826 coolant Substances 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 239000000047 product Substances 0.000 description 2
- 238000001179 sorption measurement Methods 0.000 description 2
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 1
- 239000002253 acid Substances 0.000 description 1
- 239000007864 aqueous solution Substances 0.000 description 1
- 229910052796 boron Inorganic materials 0.000 description 1
- 229910001410 inorganic ion Inorganic materials 0.000 description 1
- 239000007787 solid Substances 0.000 description 1
Landscapes
- Fertilizers (AREA)
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】
〔産業上の利用分野〕
本発明は、加圧水型原子力発電所−次系廃液の処理方法
に関する。DETAILED DESCRIPTION OF THE INVENTION [Field of Industrial Application] The present invention relates to a method for treating secondary waste liquid from a pressurized water nuclear power plant.
第２図において、１は原子力発電所から排出されるホウ
酸含有廃液のうち冷却材グレードの廃液を貯蔵するタン
クで、このタンク１から該廃液はフィードポンプ２の作
動により先ず循環タンク３に送られる。この循環タンク
３内の上記廃液は循環ポンプ４によリフィルター５を通
り、ここで懸濁物質が除去された後、限外濾過膜モジュ
ール６に供給される。この供給量は限外濾過膜モジュー
ル６から濾過液として排出される液量に等しい量とし、
また上記循環タンク３内の液レベルも常に一定に保たれ
る様に上記フィードポンプ２を作動させる。In Fig. 2, 1 is a tank for storing coolant-grade waste liquid out of the boric acid-containing waste liquid discharged from nuclear power plants. It will be done. The waste liquid in the circulation tank 3 is passed through the refilter 5 by the circulation pump 4, where suspended solids are removed, and then supplied to the ultrafiltration membrane module 6. This supply amount is equal to the amount of liquid discharged as filtrate from the ultrafiltration membrane module 6,
Further, the feed pump 2 is operated so that the liquid level in the circulation tank 3 is always kept constant.
上記限外濾過膜モジュール６で分離される濁質分を含む
濃縮液は循環タンク３に戻され、再度循環ポンプ４によ
りフィルタ５を介して限外濾過膜モジュール６に送られ
循環処理される。The concentrated liquid containing turbidity separated by the ultrafiltration membrane module 6 is returned to the circulation tank 3, and is again sent to the ultrafiltration membrane module 6 via the filter 5 by the circulation pump 4 for circulation treatment.
一方、限外濾過膜モジュール６から排出される濾過液は
貯蔵タンク７に一旦貯蔵された後、フィードポンプ８に
より直列式もしくは混床式のイオン交換樹脂塔９へ送ら
れ、ここでイオン状の不純物質が除去される。イオン交
換樹脂塔９から排出される液は、略純粋なホウ酸含有液
となっており、処理済液として貯蔵タンク１２に貯蔵さ
れる。On the other hand, the filtrate discharged from the ultrafiltration membrane module 6 is temporarily stored in a storage tank 7, and then sent by a feed pump 8 to an ion-exchange resin tower 9 of a series type or a mixed bed type, where the ionic Impurities are removed. The liquid discharged from the ion exchange resin column 9 is a substantially pure boric acid-containing liquid, and is stored in the storage tank 12 as a treated liquid.
従来法で処理した場合、原水中のシリカ（Ｓ１０２）濃
度が高い場合、生産水（貯蔵タンク（２）中のシリカが
一次系の水質基準値（０，ＩＰ）を満足出来ない場合が
ある。これは従来法（限外沢過膜十イオン交換樹脂塔）
ではシリカの除去が出来ないため、原水中のシリカ濃度
が高い場合には、生産水中のシリカ濃度が一次系の水質
基準を満足出来なくなるためである。When treated by the conventional method, if the concentration of silica (S102) in the raw water is high, the silica in the produced water (storage tank (2)) may not satisfy the primary system water quality standard value (0, IP). This is a conventional method (ultrafiltration membrane 10 ion exchange resin tower)
This is because, since silica cannot be removed using this method, if the silica concentration in the raw water is high, the silica concentration in the produced water will no longer satisfy the water quality standards for the primary system.
本発明は上記問題点を解消することを目的とする。The present invention aims to solve the above problems.
本発明方法の特徴は最近開発された無機イオン交換体（
高濃度ホウ酸水溶液中のシリカの除去が可能）を使用し
、イオン交換樹脂塔の出口水を処理することである。The method of the present invention is characterized by the use of recently developed inorganic ion exchangers (
The method is to treat the outlet water of an ion exchange resin column using a method that allows the removal of silica in a high concentration aqueous solution of boric acid.
そのため従来法に比べて、シリカ除去能がある故、シリ
カ濃度が高い原水でも処理出来る。Therefore, compared to conventional methods, it has a greater ability to remove silica, so even raw water with a high silica concentration can be treated.
本発明の方法で使用した無機吸着剤はポウ酸が高濃度で
共存する状態でもシリカを吸着することが出来る。従っ
て従来法のイオン交換樹脂塔の後に無機吸着塔を追加す
ればシリカを除去出来る。The inorganic adsorbent used in the method of the present invention can adsorb silica even in the presence of a high concentration of poric acid. Therefore, silica can be removed by adding an inorganic adsorption tower after the ion exchange resin tower in the conventional method.
次に本発明方法の一実施例を第１図に示す。 Next, an embodiment of the method of the present invention is shown in FIG.
これは第２図に示す従来法のイオン交換樹脂塔９の後に
無機吸着剤充填塔１０を追加したものである。なお、第
１図にお（゛て、第２図と同一符号を付した部材は同一
部材を示す。従来法と不発明の方法でボロン含有廃液を
処理した場合の試験結果を表１に示す。In this method, an inorganic adsorbent packed column 10 is added after the ion exchange resin column 9 of the conventional method shown in FIG. In Fig. 1, parts with the same reference numerals as in Fig. 2 indicate the same parts. Table 1 shows the test results when boron-containing waste liquid was treated by the conventional method and the uninvented method. .
充填塔１１に使用される無機吸着剤としては次のものが
ある。Inorganic adsorbents used in the packed tower 11 include the following.
■Ｄｕｒａｔ、ｅｋ社製 商品名「Ｄｕｒａｓｌｌ ３
０Ｊ■Ｄｕｒａｔｅｋ社製 商品名［Ｄｕｒａｓｉｌ
１３０Ｊ〔発明の効果〕
以上のように、本発明方法によれば、従来法に無機吸着
剤による吸着工程を追加することにより、原水中のシリ
カ濃度が上昇しても処理可能となる。処理済水は一次冷
却材水質基準を充分満足出来る故、−次冷却材として使
用出来る。■Product name: “Durasll 3” manufactured by Durat and ek
0J ■ Made by Duratek Product name [Durasil
130J [Effects of the Invention] As described above, according to the method of the present invention, by adding an adsorption step using an inorganic adsorbent to the conventional method, it is possible to treat even if the silica concentration in raw water increases. The treated water satisfies the primary coolant water quality standards, so it can be used as a secondary coolant.
第１図は本発明方法の一実施例を示す工程図、第２図は
従来の原子力発電所ホウ酸含有廃液の処理法を示す工程
図である。
１・・・貯蔵タンク、２−・フィードポンプ、３・・・
循環タンク、４・・・循環ポンプ、５・・・フィルタ、
６・・・限外濾過膜モジュール、７・・・貯蔵タンク、
８・・・フィードポンプ、９・・・イオン交換樹脂塔、
１０・・・熱着吸着剤充填塔、１１・・・蒸発装置、１
２・・・貯蔵タンク
（埋入 坂 間 跪］丁
”・−一ノFIG. 1 is a process diagram showing one embodiment of the method of the present invention, and FIG. 2 is a process diagram showing a conventional method for treating a boric acid-containing waste liquid from a nuclear power plant. 1...Storage tank, 2--Feed pump, 3...
Circulation tank, 4... Circulation pump, 5... Filter,
6... Ultrafiltration membrane module, 7... Storage tank,
8... Feed pump, 9... Ion exchange resin tower,
10... Heat-attached adsorbent packed tower, 11... Evaporator, 1
2...Storage tank (embedded Sakama kneel) Ding”・-ichino
Claims (1)
限外ろ過法で処理し、ろ過液をイオン交換樹脂を通して
不純物を除去したのち、無機吸着剤を通して、シリカを
除去せしめることを特徴とする放射性廃液処理法。In the treatment of boric acid-containing waste liquid from nuclear power plants, the waste liquid is treated by ultrafiltration, and the filtrate is passed through an ion exchange resin to remove impurities, and then passed through an inorganic adsorbent to remove silica. Waste liquid treatment method.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP17208685A JPS6232397A (en) | 1985-08-05 | 1985-08-05 | Method of processing radioactive waste liquor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP17208685A JPS6232397A (en) | 1985-08-05 | 1985-08-05 | Method of processing radioactive waste liquor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS6232397A true JPS6232397A (en) | 1987-02-12 |
Family
ID=15935280
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP17208685A Pending JPS6232397A (en) | 1985-08-05 | 1985-08-05 | Method of processing radioactive waste liquor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6232397A (en) |
-
1985
- 1985-08-05 JP JP17208685A patent/JPS6232397A/en active Pending
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