JPS58161895A - Method and device removing chlorine in radioactive liquid waste - Google Patents
Method and device removing chlorine in radioactive liquid wasteInfo
- Publication number
- JPS58161895A JPS58161895A JP4437482A JP4437482A JPS58161895A JP S58161895 A JPS58161895 A JP S58161895A JP 4437482 A JP4437482 A JP 4437482A JP 4437482 A JP4437482 A JP 4437482A JP S58161895 A JPS58161895 A JP S58161895A
- Authority
- JP
- Japan
- Prior art keywords
- waste liquid
- chlorine
- bismuth
- radioactive
- removing chlorine
- 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
Landscapes
- Removal Of Specific Substances (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】
〔発明の技術分計〕
本発明は、例えば原子力発電プラントにおいて生ずる放
射性廃液中の塩素を除去するための方法および装置に関
する。DETAILED DESCRIPTION OF THE INVENTION [Technical Summary of the Invention] The present invention relates to a method and apparatus for removing chlorine from radioactive waste fluids produced, for example, in nuclear power plants.
原子力発電プラントにおいては、二次冷却水として海水
を使用しており、この海水がリークして原子力発電プラ
ント内に流入した場合、この廃液中には腐食性の塩素が
含有されているため蒸発濃縮器で処理することができず
、従来は塩素を含む廃液中の放射性核種を除去した後放
出するか、あるいはこの廃液をイオン交換樹脂塔に通水
した後廃棄することが行なわれている。In nuclear power plants, seawater is used as secondary cooling water, and if this seawater leaks and flows into the nuclear power plant, this waste liquid contains corrosive chlorine and will be evaporated and concentrated. Conventionally, radioactive nuclides in the chlorine-containing waste liquid are removed and then released, or the waste liquid is passed through an ion exchange resin column and then disposed of.
しかしながら、前者の方法においては、蒸発濃縮処理が
できないため種々の放射性核種を完全に除去することが
できず、また後者の方法においては、廃樹脂発生量が増
大するという難点があった。However, in the former method, various radionuclides cannot be completely removed because evaporative concentration treatment cannot be performed, and in the latter method, the amount of waste resin generated increases.
本発明は、上記の難点を解消するためになされたもので
、その目的とするところは、放射性廃液中の塩素をビス
マス化合物に吸着させることにより、蒸発濃縮処理を可
能にするとともに、蒸発凝縮器や廃液貯蔵時のタンク等
の腐食を防止することができる放射性廃液中の塩素を除
去するための方法および装置を提供することにある。The present invention has been made to solve the above-mentioned difficulties, and its purpose is to enable evaporative concentration treatment by adsorbing chlorine in radioactive waste liquid to a bismuth compound, and to An object of the present invention is to provide a method and apparatus for removing chlorine from radioactive waste liquid, which can prevent corrosion of tanks and the like during waste liquid storage.
本発明は、塩素を含む放射性廃液をほぼ中性に調整した
後、ビスマス酸、ビスマス酸塩あるいはビスマス酸化物
に接触せしめ、次いでこの廃液を中和処理した後濃縮し
て濃縮廃液を分離することを特徴とする放射性廃液中の
塩素除去方法、および塩素を含む放射性廃液を収容して
ほぼ中性に調整する廃液収容槽と、前記廃液中の塩素を
吸着するためのビスマス酸、ビスマス酸塩あるいはビス
マス酸化物を収容した塩素吸着槽と、前記吸着槽通過後
の廃液を中和槽と、中和後の廃液を濃縮して分離するた
めの濃縮器とを備えたことを特徴とする放射性廃液中の
塩素除去装置に関する。The present invention involves adjusting a radioactive waste liquid containing chlorine to almost neutrality, then bringing it into contact with bismuth acid, bismuthate, or bismuth oxide, and then neutralizing the waste liquid and concentrating it to separate a concentrated waste liquid. A method for removing chlorine from a radioactive waste liquid, which is characterized by a waste liquid storage tank for storing a radioactive waste liquid containing chlorine and adjusting it to almost neutrality, and a bismuth acid, bismuthate or A radioactive waste liquid characterized by comprising a chlorine adsorption tank containing bismuth oxide, a neutralization tank for the waste liquid after passing through the adsorption tank, and a concentrator for concentrating and separating the neutralized waste liquid. Regarding the chlorine removal equipment inside.
〔発明の実施例〕 以下本発明の一実施例を図面に基づき説−明する。[Embodiments of the invention] An embodiment of the present invention will be described below based on the drawings.
第１図は本発明に係る放射性廃液中の塩素除去システム
の概略を示したもので、リーク海水やリーク海水を処理
した脱塩器再生廃液あるいは床ドレン廃液等の含塩素廃
液１を収容した廃液収容槽２において、廃液１はほぼｐ
Ｈ＝７に調整された後、適切な流速で充填塔（カラム）
またはグリコートフィルタ３へと通水される。Figure 1 shows an outline of the system for removing chlorine from radioactive waste liquid according to the present invention, in which a waste liquid containing chlorinated waste liquid 1 such as leak seawater, demineralizer recycled waste liquid treated with leak sea water, or floor drain waste liquid is shown. In the storage tank 2, the waste liquid 1 has approximately p
After adjusting to H=7, fill the packed column (column) with an appropriate flow rate.
Alternatively, the water is passed to the Glycoat filter 3.
充填塔またはプリコートフィルタ３にはビスマス酸ＨＢ
ｉＯ，（Ｂｉ、Ｏ，・Ｈｌｏ）またはその塩、あるいは
ビスマス酸化物Ｂｉ、０．− ｎＨ，ｏ （ｆｉ≧Ｏ）
が充填もしくはプリコートされるが、これらは支持体に
コーティングされるようにしても良い。Bismuth acid HB is used in the packed tower or precoat filter 3.
iO, (Bi, O, .Hlo) or its salt, or bismuth oxide Bi, 0. - nH,o (fi≧O)
are filled or precoated, but they may also be coated on the support.
前記廃液収容槽２において廃液のｐＨな調整するのは、
はぼｐＨ＝７においてビスマス酸、ビスマス酸塩および
ビスマス酸化物の塩素吸着量が増大するためで、例えば
第２図に示すようにビスマス酸のｐＨ＝７における塩素
の飽和吸着量は１．０ＩＩＩ ＠ ｑ／ １以上であり
、また第３図に示すようにビスマス酸化物の場合は、同
様に２．９ｙｍ＊ｑ／ｇ である。The pH of the waste liquid in the waste liquid storage tank 2 is adjusted by:
This is because the chlorine adsorption amount of bismuth acid, bismuthate, and bismuth oxide increases at pH = 7. For example, as shown in Figure 2, the saturated chlorine adsorption amount of bismuth acid at pH = 7 is 1.0III. @q/ is 1 or more, and in the case of bismuth oxide as shown in FIG. 3, it is also 2.9ym*q/g.
前記充填塔またはプリコートフィルタ３で処理される廃
液中には最大１ｏｏｏ ｐｐ−程度の塩素（イオン）を
含んでおり、ここで処理された廃液は中和タンク４に送
られるが、この中軸タンクにおける許容塩素濃度は、次
の蒸発濃縮器５で何倍濃縮されるかにより決定される。The waste liquid treated in the packed tower or the pre-coat filter 3 contains chlorine (ions) of up to about 100 pp-, and the waste liquid treated here is sent to the neutralization tank 4. The allowable chlorine concentration is determined by how many times the chlorine is concentrated in the next evaporative concentrator 5.
一例として、再生廃液の場合、Ｎａ１ＳＯ４を含むため
約２５倍に濃縮されるので、蒸発濃縮終点における塩素
濃度が５０００ ｐ ｐ ｍに規制されているとすれば
、中和タンク４内における処理液中の塩素濃度は２００
ｐｐｍ まで許容される。As an example, in the case of regenerated waste liquid, it is concentrated approximately 25 times because it contains Na1SO4, so if the chlorine concentration at the end point of evaporation concentration is regulated to 5000 ppm, the concentration of chlorine in the treated liquid in the neutralization tank 4 The chlorine concentration is 200
Up to ppm is allowed.
また他の例として床ドレンの場合、１００倍濃縮される
ので、やはり蒸発濃縮終点における塩素濃度が同様に５
ｏｏｏ ｐｐｍに規制されているとすれば、中和タンク
４内における２処理液中の塩素濃度は５０ｐｐｍまで許
容される。As another example, in the case of bed drain, the concentration is 100 times, so the chlorine concentration at the end point of evaporation concentration is also 5.
If the chlorine concentration is regulated to ooo ppm, the chlorine concentration in the two treatment solutions in the neutralization tank 4 is allowed up to 50 ppm.
前記蒸発濃縮器５内で濃縮終点に達した缶底液−は廃液
貯蔵タンク６へ排出され、同時に分離された希薄液は脱
塩器７を経て処理水８として回収される。The can bottom liquid that has reached the end point of concentration in the evaporative concentrator 5 is discharged to a waste liquid storage tank 6, and at the same time the separated dilute liquid is recovered as treated water 8 through a desalter 7.
一方、前記充填塔またはプリコートフィルタ３内で飽和
量の塩素を吸着したビスマス酸、ビスマス酸塩あるいは
ビスマス酸化物は廃スラツジとして排出され、沈降分離
、遠心分離、脱水等の分離工程を含む廃スラツジ処理装
置９を経た後、固化装置１０で固化される。On the other hand, the bismuth acid, bismuthate, or bismuth oxide that has adsorbed a saturated amount of chlorine in the packed tower or the precoat filter 3 is discharged as waste sludge, and the waste sludge is processed through separation processes such as sedimentation, centrifugation, and dehydration. After passing through the processing device 9, it is solidified in the solidifying device 10.
以ト述べたように本発明の放射性廃液中の塩素除去方法
および装置によれば、廃液中の塩素をビスマス化合物（
酸、塩、酸化物）に吸着させることにより、蒸発濃縮処
理が可能となり、従って種々の放射性核種を完全に除去
することができるとともに蒸発濃縮器や廃液タンク等の
腐食を防止することができ、また処理後の廃水を再利用
することができる等の利点を有する。As described above, according to the method and apparatus for removing chlorine from radioactive waste liquid of the present invention, chlorine in waste liquid is removed by bismuth compound (
By adsorbing it to (acids, salts, oxides), it becomes possible to carry out evaporative concentration treatment, thereby making it possible to completely remove various radionuclides and prevent corrosion of evaporative concentrators, waste liquid tanks, etc. It also has the advantage of being able to reuse wastewater after treatment.
第１図は本発明の一実施例を概略的に示す構成図、第２
図および第３図は、それぞれビスマス酸およびビスマス
酸化物のｐＨと塩素（イオン）吸着量の関係を示す図で
ある。
１ ・・・・・・含塩素廃液
２ ・・・・・・廃液収容槽
３ ・・・・・・ 充填塔またはプリコートフィルタ４
・・・・・・ 中和タンク
５ ・・・・・・蒸発濃縮器
９ ・・・・・・廃スラツジ処理装置
１０ ・・・・・・固化装置
代理人弁理士 須 山 佐 −
第１図
第４図
Ｈ’ ｉ＊＋ｔ ｏＨ−＞重加ｔ（ｍｅｓＡ）５７３−
第３図FIG. 1 is a configuration diagram schematically showing an embodiment of the present invention, and FIG.
3 and 3 are diagrams showing the relationship between pH and chlorine (ion) adsorption amount of bismuth acid and bismuth oxide, respectively. 1... Chlorine-containing waste liquid 2... Waste liquid storage tank 3... Packed tower or precoat filter 4
..... Neutralization tank 5 ..... Evaporation concentrator 9 ..... Waste sludge treatment equipment 10 ..... Solidification equipment Patent attorney Satoshi Suyama - Figure 1 Fig. 4 H' i*+t oH->weighted t(mesA)573- Fig. 3
Claims (1)
スマス酸、ビスマス酸塩あるいはビスマス酸化物に接触
せしめ、次いでこの廃液を中和処理した後濃縮して濃縮
廃液を分離することを特徴とする放射性廃液中の塩素除
去方法。 ２、塩素を含む放射性廃液を収容してほぼ中性に調整す
る廃液収容槽と、前記廃液中の塩素を吸着するためのビ
スマス酸、ビスマス酸塩あるいはビスマス酸化物を収容
した塩素吸着槽と、前記吸着槽通過後の廃液を中和する
ための中和槽と、中和後の廃液を濃縮して分離するため
の濃縮器とを備えたことを特徴とする放射性廃液中の塩
素除去装置。[Scope of Claims] 1. After adjusting the radioactive waste liquid containing chlorine to almost neutrality, it is brought into contact with bismuth acid, bismuthate, or bismuth oxide, and then this waste liquid is neutralized and concentrated to obtain a concentrated waste liquid. A method for removing chlorine from radioactive waste liquid, characterized by separating. 2. A waste liquid storage tank for storing radioactive waste liquid containing chlorine and adjusting it to almost neutrality, and a chlorine adsorption tank containing bismuth acid, bismuth acid salt, or bismuth oxide for adsorbing chlorine in the waste liquid; An apparatus for removing chlorine from radioactive waste liquid, comprising: a neutralization tank for neutralizing the waste liquid after passing through the adsorption tank; and a concentrator for concentrating and separating the neutralized waste liquid.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP4437482A JPS58161895A (en) | 1982-03-19 | 1982-03-19 | Method and device removing chlorine in radioactive liquid waste |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP4437482A JPS58161895A (en) | 1982-03-19 | 1982-03-19 | Method and device removing chlorine in radioactive liquid waste |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS58161895A true JPS58161895A (en) | 1983-09-26 |
Family
ID=12689723
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP4437482A Pending JPS58161895A (en) | 1982-03-19 | 1982-03-19 | Method and device removing chlorine in radioactive liquid waste |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS58161895A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5667754A (en) * | 1995-09-25 | 1997-09-16 | Hach Company | Device for chloride ion removal prior to chemical oxygen demand analysis |
| US5683914A (en) * | 1995-09-25 | 1997-11-04 | Hach Company | Method for chloride ion removal prior to chemical oxygen demand analysis |
-
1982
- 1982-03-19 JP JP4437482A patent/JPS58161895A/en active Pending
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5667754A (en) * | 1995-09-25 | 1997-09-16 | Hach Company | Device for chloride ion removal prior to chemical oxygen demand analysis |
| US5683914A (en) * | 1995-09-25 | 1997-11-04 | Hach Company | Method for chloride ion removal prior to chemical oxygen demand analysis |
| US5932174A (en) * | 1995-09-25 | 1999-08-03 | Hach Company | Device for chloride ion removal prior to chemical oxygen demand analysis |
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