JPS58205899A - Method of removing chlorine ion in radioactive liquid waste - Google Patents
Method of removing chlorine ion in radioactive liquid wasteInfo
- Publication number
- JPS58205899A JPS58205899A JP8939482A JP8939482A JPS58205899A JP S58205899 A JPS58205899 A JP S58205899A JP 8939482 A JP8939482 A JP 8939482A JP 8939482 A JP8939482 A JP 8939482A JP S58205899 A JPS58205899 A JP S58205899A
- Authority
- JP
- Japan
- Prior art keywords
- waste liquid
- chlorine ions
- crud
- ions
- 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.)
- Granted
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】
［発明の技術分野］
本発明は、例えば原子カー発電プラントにおいて（１，
・ｒる放射性廃液中の塩素イオンを除去するための方法
に関する。DETAILED DESCRIPTION OF THE INVENTION [Technical field of the invention] The present invention is directed to, for example, nuclear car power generation plants (1,
-Relates to a method for removing chlorine ions from radioactive waste liquid.
［発明の技術的背…どぞの問題点］
涼了炉発電プラントにおいては、二次冷却水として海水
を使用しているが、この海水がリークして原イカプラン
ト内に流入した場合、プラントから１１１出される廃液
中には腐蝕ｉ１１の塩素イオンが含有されるようにイ（
るためこのような廃液は蒸発濃縮器で処１！ｌ！ ！ｌ
−ることができないという問題があった。このため従Ｍ
目３Ｌ石索イオンを含む廃液中の放射性核種を除）、し
た後放出Ｊるか、あるいはこの廃液をイオン交換樹脂塔
に通水した後廃東することがｆｊわれている。[Problems with the technical background of the invention] Seawater is used as secondary cooling water in the cooling furnace power plant, but if this seawater leaks and flows into the raw squid plant, the plant I (
Therefore, such waste liquid should be disposed of in an evaporative concentrator1! l! ! l
-There was a problem that it was not possible to do so. For this reason, subordinate M
It is recommended that radioactive nuclides in the waste liquid containing 3L stone ions be removed) and then released, or that this waste liquid be passed through an ion exchange resin tower and then disposed of.
しかしなが番）、前者の方法においては、蒸発濃縮処理
ができ／ｉ〜いＩ、：めＴｉ１ｉ々の放射性核種を完全
に除去することができヂ、また後者の方法においては、
廃樹脂発／１吊が増大づるという難点があった。However, in the former method, it is possible to perform evaporative concentration treatment, and in the latter method, it is possible to completely remove the radioactive nuclides.
There was a problem that the amount of waste resin per 1 hanger increased.
本発明省らは、このにうな！Ｕ点を解消するため放飼性
廃液をほぼ中性に調整し、この廃液中の塩素イオンをビ
スマス化合物に吸着させて除去する方ｄ１について先に
出願したが、この方法では配管内等で生成したクラッド
（Ｆｅ ２０３ ）が廃液中に存在覆るようになると塩
素イオンの吸＠量が非常に低トするという難点があった
。The Ministry of the Invention and others agree to this! In order to eliminate the U point, we have previously applied for method d1, which adjusts the free waste liquid to almost neutrality and removes the chlorine ions in this waste liquid by adsorbing them to a bismuth compound. When the cladding (Fe 203 ) is present in the waste liquid, the amount of chlorine ions absorbed becomes extremely low.
札なみに人］［海水の１／１０ｍ！！度の塩素イオンを
有する液にＦｅ ２０３を添加し、水酸化ビスマスの塩
素イオン吸着量を測定してみると第１図のグラフに示す
ようにＦｅ２ｏ３が１μａ／ｍ℃存在りると塩素イオン
はほとんど吸着されないＪ：うになる。As many people as bills] [1/10m of seawater! ! When Fe 203 was added to a solution containing chlorine ions at a temperature of Hardly adsorbed J: Swells.
［発明の目的］
本発明はこのＪ：うな点に対処してなされたもので、塩
素イオンの吸着を妨害す６クラツドを除去して効率よく
放射性廃液中の塩素イオンを除去する方法を提供するも
のである。[Objective of the Invention] The present invention has been made in response to this problem, and provides a method for efficiently removing chlorine ions from radioactive waste liquid by removing six clades that interfere with the adsorption of chlorine ions. It is something.
［発明の概要］
づなわち水元明方が１は、塩素イオンおよびクラッドを
含む放射性廃液中の塩素イオンをビスマス化合物に吸着
ざＶて除去するにあたり、あらかじめ廃液中のクラッド
を除去した後塩素イオンをどスマス化合物に吸着さ１！
ることを特徴する。[Summary of the Invention] Mizumoto Akikata 1 is a method for removing chlorine ions in a radioactive waste liquid containing chlorine ions and crud by adsorption to a bismuth compound. Ions are adsorbed by dosmas compounds 1!
It is characterized by
本発明に使用するビスマス化合物としては、ビスマス酸
（ＩＩＢｉ Ｏｘ ）またはその塩、あるいは水酸化ビ
スマス（Ｒｉ （Ｏｆｆ＞ ３ ） 、酸化ビスマス
（Ｂｉｚｏ：＋）があげられる。Examples of the bismuth compound used in the present invention include bismuth acid (IIBiOx) or a salt thereof, bismuth hydroxide (Ri(Off>3)), and bismuth oxide (Bizo:+).
本発明においＣ廃液中のクラッドを除去する方法として
は、廃液を遠心分前または沈降分離あるいは濾過して機
械的にり）ラド分を分前り−る方法や、廃液を酸ｉ’１
．１．、ｍ ｌノ（クラッドを溶解させ、鉄イオンにし
て除去するｌ／Ｊ ｒ）ｓがある、。In the present invention, methods for removing crud in the C waste solution include a method in which the waste solution is centrifuged or mechanically removed by sedimentation or filtration;
．． 1. , ml (l/Jr)s that dissolves the cladding and removes it as iron ions.
ちなみに鉄イオンは第２図に示すように液中に１０００
ｔｔｏ ／’ＩＩＩ 、Ｑ Ｎ”ａ ／（ＳＯ４） ３
ｆｉｎ］存在していても水酸化ｌｒビスマス塩素イオ
ン吸着量は低重しない。By the way, as shown in Figure 2, there are 1000 iron ions in the liquid.
tto /'III, Q N”a /(SO4) 3
Even if fin] is present, the adsorption amount of lr bismuth hydroxide chloride ions will not be reduced.
本発明にＪ３いＣは、廃液中のクラッド分を除去した後
、上記ビスマス化合物に廃液中の塩素イオンを吸着さＶ
るわｌであるが、この方法としては廃液をビスマス化合
物の層に通して塩素イオンを吸着さμる方法や廃液中に
ビスマス化合物を投入し攪拌混合後、 定＋１ｙ １７
ｇ／ｋ ｉｆｆして塩素イオンを吸３−
着したビスマス化合物を分離除去する方法があげられる
。In the present invention, after removing the crud content in the waste liquid, the bismuth compound adsorbs chlorine ions in the waste liquid.
However, this method involves passing the waste liquid through a layer of bismuth compound to adsorb chloride ions, or adding a bismuth compound to the waste liquid and stirring and mixing, then adding a constant +1y 17
A method of separating and removing bismuth compounds adsorbing chlorine ions using g/k iff is mentioned.
［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.
実施例１
第３図にＪ３いて、廃液タンク１に収容されたリーク海
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イオン廃液２は遠心分離機、濾過器
等のクラッド除去装Ｍ３によりクラッド分が除去された
後、受はタンク４に受は入れられる。次いでこの液をビ
スマス化合物が充填された塩素吸着剤塔５に通水し塩素
イオンを除去ず鼻。この後廃液を中和槽６に送りｐｌ−
１を調整後蒸発濃縮器７で濃縮減容覆る。蒸発濃縮器７
で濃縮終点に達した液は廃液貯蔵タンクへ排出され、同
時に分離された希薄液は脱塩器を経て処理水と」ノて回
収される。Example 1 At J3 in Fig. 3, chlorine-containing waste liquid 2 such as leak seawater stored in waste liquid tank 1, demineralizer recycled waste liquid after treating leak sea water, or floor drain waste liquid is collected in a centrifuge, filter, etc. After the crud is removed by the crud removal device M3, the receiver is placed in the tank 4. Next, this liquid is passed through a chlorine adsorbent tower 5 filled with a bismuth compound to remove chlorine ions. After this, the waste liquid is sent to the neutralization tank 6 pl-
After adjusting 1, it is concentrated and reduced in volume using an evaporator 7 and covered. Evaporative concentrator 7
The liquid that has reached the end point of concentration is discharged to a waste liquid storage tank, and at the same time, the separated diluted liquid passes through a desalter and is recovered as treated water.
一方、塩素吸着剤塔５内で飽和量の塩素イオンを吸着し
たビスマス化合物は廃スラツジとして排出され、沈降分
−］、遠心分離、１１１２水等の分離工程−４＝
を粁１．：後固化される。On the other hand, the bismuth compound that has adsorbed a saturated amount of chlorine ions in the chlorine adsorbent tower 5 is discharged as waste sludge, and the sedimentation fraction -], centrifugation, 1112 water, etc. separation step -4= is removed from the sludge. : Post-solidified.
実施例２
第１図において、ｐ１１調整槽８に収容された廃液に硫
酸を添加してｐｌ（１〜５好ましくはｐＨ２・−４に調
整する。調整役ビスマス化合物を添加し攪拌混合後一定
時間（２４〜２５時間）放置して塩素イオンを吸着した
吸名剤と塩素イオンを除去した廃液とを分離装置９にに
り固液分離し、この後廃液を中相槽６に送り１）１１を
調整後蒸発濃縮器７で濃縮減容４る。この後の工程は実
施例１と同様に（１イＴわれる。Example 2 In FIG. 1, sulfuric acid is added to the waste liquid stored in the p11 adjustment tank 8 to adjust it to pl (1 to 5, preferably pH 2.-4). A bismuth compound as a regulator is added, and after stirring and mixing, it is heated for a certain period of time. (24 to 25 hours) The absorbing agent that has adsorbed chlorine ions and the waste liquid from which chlorine ions have been removed are separated into solid and liquid in the separator 9, and then the waste liquid is sent to the medium phase tank 6 1) 11 After adjusting, the evaporator 7 is used to concentrate and reduce the volume. The subsequent steps are carried out in the same manner as in Example 1 (1).
なおｐ Ｉ−ｌ″ＪＡ整槽８、中和槽６および中和槽６
までの配管は耐酸性４４ ｍ’ｌぐ構成されるのが好ま
しい。In addition, p I-l''JA tank 8, neutralization tank 6, and neutralization tank 6
It is preferable that the piping up to 44 m'l is acid-resistant.
第５図はｎ ＩＩ調整１１５に収容された廃液のｐ ｌ
−１と塩素イオン吸名吊との関係を示すグラフである。FIG. 5 shows the p l of the waste liquid stored in the n
It is a graph showing the relationship between -1 and chloride ion absorption.
なお図中実線は水酸化ビスマス、点線はビスマス酸によ
る吸着量を示１゜グラフからも明らかなように廃液を酸
性に調整り゛ることににリフラッドが溶解し塩素イオン
吸着量が増大している。In addition, the solid line in the figure shows the amount of adsorption by bismuth hydroxide, and the dotted line shows the amount of adsorption by bismuth acid.1 As is clear from the graph, by adjusting the waste liquid to acidity, reflood dissolves and the amount of chlorine ion adsorption increases. There is.
［発明の効宋１
以Ｉ：述べたように本発明方法においては、塩素イオン
の吸名を妨害するクラッドを除去した後、塩素イオンを
ビスマス化合物に吸着さけているので効率よく塩素イオ
ンが除去できる。従って蒸発濃縮処理が可能どなり、種
々の放射性核種を完全に除去りることができるとともに
、蒸発濃縮器ヤ）廃液タンク等の腐食を防止することが
でき、まｊこ処１！ＩＩ後のり１水を再刊用づることが
できる等の利点をＮ ？Ｊる。[Effects of the Invention Song 1 Part I: As mentioned above, in the method of the present invention, after removing the cladding that obstructs the absorption of chlorine ions, the chlorine ions are adsorbed onto the bismuth compound, so chlorine ions are efficiently removed. can. Therefore, evaporative concentration processing becomes possible, and various radionuclides can be completely removed, and corrosion of the evaporative concentrator, waste liquid tank, etc. can be prevented, and this is the best part! Is there an advantage such as being able to reprint the second edition of II? Jru.
第１図はクラッドが存右した場合のＪ［ｉｍイイオ吸る
吊の変化を示ずグラフ、第２図は鉄イオンが存イ１した
場合の塩素イオン吸着量の変化を示リグラフ、第３、第
１図は本発明方法の一実施例を丞Ｊブ［１ツク図、第５
図は廃液の０１−１と塩素イオン吸着量の関係を示４グ
ラフである。
１・・・・・・・・・・・・廃液タンク２・・・・・・
・・・・・・含塩素イオン廃液３・・・・・・・・・・
・・クラッド除去装置５・・・・・・・・・・・・塩素
吸着側塔６・・・・・・・・・・・・中和槽
７・・・・・・・・・・・・蒸発濶縮器８・・・・・・
・・・・・・ｐ ｉｆ調整槽代理人弁即−１−須 山
佐 −
＝７−
第り図
第２図
１”１ｅ２（ＳＯ４）３量（ｇｌ／ｍ（！’）８−
第３図
第４図Figure 1 is a graph showing the change in the adsorption capacity of J[im] when cladding is present, Figure 2 is a graph showing the change in the adsorption amount of chloride ions when iron ions are present, and Figure 3 , FIG. 1 shows an embodiment of the method of the present invention.
The figure is four graphs showing the relationship between waste liquid 01-1 and the amount of chlorine ion adsorption. 1...... Waste liquid tank 2...
・・・・・・Chlorine-containing ion waste liquid 3・・・・・・・・・
... Crud removal device 5 ... Chlorine adsorption side tower 6 ...... Neutralization tank 7 ......・Evaporator condenser 8...
・・・・・・pif adjustment tank agent valve soku-1-Suyama
- =7- Fig. 2 Fig. 1"1e2 (SO4) 3 amount (gl/m (!') 8- Fig. 3 Fig. 4
Claims (3)
塩素イオンをビスマス化合物に吸着させて除去するにあ
たり、あらかじめ廃液中のクラッドを除去した後塩素イ
オンをビスマス化合物に吸着させることを特徴とづる放
射性廃液中の塩素イオン除去方法。(1) A radioactive waste liquid characterized by removing the chlorine ions in the radioactive waste liquid containing chlorine ions and crud by adsorbing them to a bismuth compound, by first removing the crud in the waste liquid and then adsorbing the chlorine ions to the bismuth compound. How to remove chlorine ions inside.
溶解させることにより行なわれる特許請求の範囲第１項
記載の放射性廃液中の塩素イオン除去方法。(2) The method for removing chlorine ions from a radioactive waste liquid according to claim 1, wherein the removal of the crud is carried out by turning the waste liquid into acid gel to dissolve the crud.
許請求の範囲第１項記載の放射性廃液中の塩素イオン除
去方法。(3) The method for removing chlorine ions from radioactive waste liquid according to claim 1, wherein the removal of crud is carried out by mechanical separation.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP8939482A JPS58205899A (en) | 1982-05-26 | 1982-05-26 | Method of removing chlorine ion in radioactive liquid waste |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP8939482A JPS58205899A (en) | 1982-05-26 | 1982-05-26 | Method of removing chlorine ion in radioactive liquid waste |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS58205899A true JPS58205899A (en) | 1983-11-30 |
| JPH0522878B2 JPH0522878B2 (en) | 1993-03-30 |
Family
ID=13969428
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP8939482A Granted JPS58205899A (en) | 1982-05-26 | 1982-05-26 | Method of removing chlorine ion in radioactive liquid waste |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS58205899A (en) |
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS61195400A (en) * | 1985-02-25 | 1986-08-29 | 東京電力株式会社 | Method of treating waste liquor containing radioactive nuclide |
| JPS6457197A (en) * | 1987-08-28 | 1989-03-03 | Kyowa Chem Ind Co Ltd | Purifier agent for nuclear reactor coolant and purification |
| WO1997012240A1 (en) * | 1995-09-25 | 1997-04-03 | Hach Company | Method for chloride ion removal prior to chemical oxygen demand analysis |
| WO1997011780A1 (en) * | 1995-09-25 | 1997-04-03 | Hach Company | Device for chloride ion removal prior to chemical oxygen demand analysis |
| ES2172411A1 (en) * | 2000-07-14 | 2002-09-16 | Faus Jose Andres Sanchis | Production of e.g. chlorine salts from industrial cleaning water consists of treatment with highly saline solution for use in decalcification processing |
| CN107892375A (en) * | 2017-10-19 | 2018-04-10 | 上海交通大学 | The minimizing technology of chloride Chlorine in Solution ion |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS53128590A (en) * | 1977-04-15 | 1978-11-09 | Unitika Ltd | Water treating process |
| JPS559136A (en) * | 1978-07-07 | 1980-01-23 | Hitachi Ltd | Method of filtering radioactive liquid waste |
-
1982
- 1982-05-26 JP JP8939482A patent/JPS58205899A/en active Granted
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS53128590A (en) * | 1977-04-15 | 1978-11-09 | Unitika Ltd | Water treating process |
| JPS559136A (en) * | 1978-07-07 | 1980-01-23 | Hitachi Ltd | Method of filtering radioactive liquid waste |
Cited By (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS61195400A (en) * | 1985-02-25 | 1986-08-29 | 東京電力株式会社 | Method of treating waste liquor containing radioactive nuclide |
| JPS6457197A (en) * | 1987-08-28 | 1989-03-03 | Kyowa Chem Ind Co Ltd | Purifier agent for nuclear reactor coolant and purification |
| WO1997012240A1 (en) * | 1995-09-25 | 1997-04-03 | Hach Company | Method for chloride ion removal prior to chemical oxygen demand analysis |
| WO1997011780A1 (en) * | 1995-09-25 | 1997-04-03 | Hach Company | Device for chloride ion removal prior to chemical oxygen demand analysis |
| 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 |
| ES2172411A1 (en) * | 2000-07-14 | 2002-09-16 | Faus Jose Andres Sanchis | Production of e.g. chlorine salts from industrial cleaning water consists of treatment with highly saline solution for use in decalcification processing |
| CN107892375A (en) * | 2017-10-19 | 2018-04-10 | 上海交通大学 | The minimizing technology of chloride Chlorine in Solution ion |
| CN107892375B (en) * | 2017-10-19 | 2021-08-06 | 上海交通大学 | Method for removing chloride ions in chlorine-containing solution |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0522878B2 (en) | 1993-03-30 |
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