JPH11264896A - Processing method for waste liquid and processing device of waste liquid - Google Patents
Processing method for waste liquid and processing device of waste liquidInfo
- Publication number
- JPH11264896A JPH11264896A JP6696598A JP6696598A JPH11264896A JP H11264896 A JPH11264896 A JP H11264896A JP 6696598 A JP6696598 A JP 6696598A JP 6696598 A JP6696598 A JP 6696598A JP H11264896 A JPH11264896 A JP H11264896A
- Authority
- JP
- Japan
- Prior art keywords
- waste liquid
- decomposing
- power plant
- nuclear power
- treatment
- 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
- Physical Water Treatments (AREA)
- Treatment Of Water By Ion Exchange (AREA)
Abstract
Description
【０００１】[0001]
【発明の属する技術分野】本発明は、廃液中の不純物除
去方法及びその装置に係り、特に、沸騰水型原子力発電
所において行われている廃液の処理方法及びその装置に
関するものである。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a method and an apparatus for removing impurities in a waste liquid, and more particularly to a method and an apparatus for treating a waste liquid performed in a boiling water nuclear power plant.
【０００２】[0002]
【従来の技術】沸騰水型原子力発電プラント内で発生し
た廃液は、その種類により分別され、各々蒸発処理、脱
塩処理、ろ過処理などが行われ、復水貯蔵タンク（以下
「ＣＳＴ」という）に回収されている。これらの処理の
内、脱塩処理はほぼ全ての廃液について行われており、
廃液中に含まれるイオン性不純物や放射性物質が除去さ
れ、ＣＳＴに回収されていた。2. Description of the Related Art Wastewater generated in a boiling water nuclear power plant is separated according to its type, subjected to an evaporation treatment, a desalination treatment, a filtration treatment, etc., and then to a condensate storage tank (hereinafter referred to as "CST"). Has been recovered. Of these treatments, desalination treatment is performed on almost all waste liquids,
The ionic impurities and radioactive substances contained in the waste liquid have been removed and collected in the CST.
【０００３】[0003]
【発明が解決しようとする課題】管理が高度化された最
近のプラントでは、発電所内の放射線レベルを低く維持
し、また系統構成材料の健全性を維持する観点から、廃
液の処理後の水質を高純度にすることが要求されてい
る。しかし、従来の処理装置では、高度な要求に対して
満足できず、特に廃液中に極微量存在する放射性物質に
ついての除去性能は低く、長時間の循環通水により処理
しているのが現状であり、ランニングコストの上昇とな
っている。また、この原因となっているのが廃液中に含
まれている有機性物質であるといわれており、これは脱
塩装置に使用されている陰イオン交換樹脂などの表面を
汚染させ、その反応速度を低下させる要因となっている
と共に、廃液中に存在する放射性物質である重金属と錯
体を形成し、イオン交換樹脂による除去をしにくいもの
としている。この有機性物質は、主として陽イオン交換
樹脂や陰イオン交換樹脂に含まれていた、あるいはこれ
らのイオン交換樹脂の分解に基づいて生じた極性基をも
つ低分子化合物が溶出したものであって、それが重金属
と錯体を形成するものであり、この低分子化合物の分子
量が２０００を越すものは、樹脂による除去が困難にな
る。本発明は、上記の諸問題を解決し、廃液中に含まれ
る不純物の除去を容易にすることのできる廃液処理方法
及びその処理装置を提供することを目的とする。In recent plants with advanced management, water quality after treatment of waste liquid is reduced from the viewpoint of maintaining low radiation levels in power plants and maintaining soundness of system constituent materials. High purity is required. However, the conventional processing equipment cannot satisfy the high demands, and especially the removal performance of radioactive substances present in trace amounts in the waste liquid is low. Yes, running costs are rising. It is said that this is caused by organic substances contained in the waste liquid, which contaminates the surface of the anion exchange resin used in the desalination equipment, It is a factor that lowers the speed and forms a complex with the heavy metal that is a radioactive substance present in the waste liquid, making it difficult to remove with an ion exchange resin. This organic substance is mainly a cation exchange resin or an anion exchange resin, or a low molecular weight compound having a polar group eluted based on the decomposition of these ion exchange resins, It forms a complex with a heavy metal, and when the molecular weight of this low molecular compound exceeds 2,000, it becomes difficult to remove it with a resin. SUMMARY OF THE INVENTION An object of the present invention is to provide a waste liquid treatment method and a treatment apparatus capable of solving the above-mentioned problems and facilitating removal of impurities contained in the waste liquid.
【０００４】[0004]
【課題を解決するための手段】上記目的を達成するため
に、本発明では沸騰水型原子力発電所における脱塩装置
にて廃液を処理する方法において、脱塩装置の前段に有
機性不純物を分解もしくは除去する装置を設置し、その
後に設ける脱塩装置での放射性物質の除去を容易にした
ものである。この処理装置において使用される有機性物
質の分解もしくは除去する装置としては、紫外線照射装
置、オゾン発生装置、過酸化水素水溶液や次亜塩素酸水
溶液などの酸化性物質の注入装置、活性炭フィルタなど
があり、処理する廃液に応じてこれらの装置を一又は複
数用いて、処理するようにするのがよい。In order to achieve the above object, the present invention provides a method of treating waste liquid in a desalination unit in a boiling water nuclear power plant, wherein organic impurities are decomposed before the desalination unit. Alternatively, a device for removal is provided, and removal of radioactive substances in a desalination device provided thereafter is facilitated. Examples of devices for decomposing or removing organic substances used in this processing apparatus include an ultraviolet irradiation device, an ozone generator, an injection device for oxidizing materials such as an aqueous solution of hydrogen peroxide and an aqueous solution of hypochlorous acid, and an activated carbon filter. Yes, it is preferable to use one or more of these devices according to the waste liquid to be treated.
【０００５】[0005]
【発明の実施の形態】本発明では、脱塩装置の前段に有
機性不純物を分解もしくは除去する装置を設置し、そこ
で有機性不純物を分解もしくは除去することにより、イ
オン交換樹脂からなる脱塩装置において廃液中の有機性
不純物の量が少なくし、イオン交換樹脂粒子の表面を覆
うことを少なくし、イオン交換樹脂による放射性物質の
吸着・除去を阻害しないようにしたものである。このた
め、有機性不純物を分解もしくは除去する装置では、有
機性不純物を分解し、低分子化するものが好ましい。活
性炭フィルタのような有機性不純物を吸着により除去す
るものでは、放射性物質を吸着しない性質のものを用い
ることが好ましい。DESCRIPTION OF THE PREFERRED EMBODIMENTS In the present invention, a device for decomposing or removing organic impurities is installed at the preceding stage of a desalting device, and the organic impurities are decomposed or removed therefrom, whereby a desalination device comprising an ion exchange resin is formed. In this method, the amount of organic impurities in the waste liquid is reduced, the surface of the ion exchange resin particles is less covered, and the adsorption and removal of radioactive substances by the ion exchange resin is not hindered. For this reason, it is preferable that a device for decomposing or removing organic impurities decompose organic impurities and reduce the molecular weight. In a device such as an activated carbon filter that removes organic impurities by adsorption, it is preferable to use a material that does not adsorb a radioactive substance.
【０００６】[0006]
【実施例】以下、実施例により本発明を具体的に説明す
る。但し、本発明はこの実施例に限定されるものではな
い。The present invention will be described below in detail with reference to examples. However, the present invention is not limited to this embodiment.
【０００７】図１に示す廃液処理装置１を用い、沸騰水
型原子力発電プラントにおいて発生した廃液を入れた原
水タンク２から廃液３をポンプ４で送り、流量計５を経
て有機性物質の分解もしくは除去装置６を通し、続いて
樹脂カラム７に通水空間速度１０ｍ／ｈで通して処理液
８を得た。この樹脂カラム７は、強酸性ゲル型陽イオン
交換樹脂５０ｍｌと強塩基性陰イオン交換樹脂１００ｍ
ｌの計１５０ｍｌのイオン交換樹脂を混床状態にて内径
が２５ｍｍ（直径）のカラムに充填したものである。こ
の得られた処理液８をサンプリングして測定した。前記
廃液を、前記の有機性物質の分解もしくは除去装置６に
おいて、紫外線照射した場合としない場合とでイオン交
換樹脂による除去特性を比較した結果を図２に示す。図
２から分かるように、紫外線を照射することにより、イ
オン交換樹脂での放射性物質の除去率が約２０％向上し
ていることが分かる。[0007] Using a waste liquid treatment apparatus 1 shown in FIG. 1, a waste liquid 3 is sent from a raw water tank 2 containing a waste liquid generated in a boiling water nuclear power plant by a pump 4. The solution was passed through the removing device 6 and then passed through the resin column 7 at a space velocity of 10 m / h to obtain a treatment liquid 8. The resin column 7 is composed of 50 ml of a strongly acidic gel type cation exchange resin and 100 m of a strongly basic anion exchange resin.
(1) A total of 150 ml of ion exchange resin was packed in a mixed-bed state into a column having an inner diameter of 25 mm (diameter). The processing liquid 8 thus obtained was sampled and measured. FIG. 2 shows the results of comparing the removal characteristics of the waste liquid with the ion exchange resin in the organic substance decomposition or removal apparatus 6 when the waste liquid is irradiated with ultraviolet light and when it is not irradiated. As can be seen from FIG. 2, the irradiation rate of the radioactive substance in the ion exchange resin is improved by about 20% by irradiating the ultraviolet ray.
【０００８】[0008]
【発明の効果】本発明によれば、沸騰水型原子力発電プ
ラントにて発生する廃液の処理において、廃液中の有機
性物質の分解もしくは除去することができ、それに伴い
脱塩装置での放射性物質の除去率が向上し、廃液中の不
純物を容易に除去することが可能となり、水質の向上、
ランニングコストの低減を図ることが可能となる。According to the present invention, in the treatment of waste liquid generated in a boiling water nuclear power plant, organic substances in the waste liquid can be decomposed or removed, and accordingly, radioactive substances in a desalination apparatus can be decomposed. Removal rate is improved, and impurities in the waste liquid can be easily removed.
The running cost can be reduced.
【図１】本発明の廃液処理装置の概略説明図を示す。FIG. 1 is a schematic explanatory view of a waste liquid treatment apparatus of the present invention.
【図２】本発明の実施例において、有機性物質の分解も
しくは除去の手段に紫外線照射を行った場合と行わなか
った場合との放射能の除去率を表した棒グラフをを示
す。FIG. 2 is a bar graph showing a radioactivity removal rate when ultraviolet irradiation is performed as a means for decomposing or removing an organic substance in an embodiment of the present invention.
１ 廃液処理装置 ２ 原液タンク ３ 廃液 ４ ポンプ ５ 流量計 ６ 有機性物質の分解もしくは除去装置 ７ 樹脂カラム ８ 処理液 DESCRIPTION OF SYMBOLS 1 Waste liquid processing apparatus 2 Undiluted liquid tank 3 Waste liquid 4 Pump 5 Flowmeter 6 Organic substance decomposition or removal apparatus 7 Resin column 8 Processing liquid
Claims (3)
液の処理において、廃液中に含まれる有機性物質を分解
もしくは除去し、その後の脱塩装置にてイオン性の不純
物や放射性物質を除去するすることを特徴とする廃液処
理方法。In the treatment of a waste liquid in a boiling water nuclear power plant, an organic substance contained in the waste liquid is decomposed or removed, and then a ionic impurity or a radioactive substance is removed by a desalination apparatus. Waste water treatment method characterized by the above-mentioned.
液処理装置において、廃液を有機性物質の分解もしくは
除去装置に通し、廃液中に含まれる有機性物質を分解も
しくは除去し、その後の脱塩装置に通してイオン性の不
純物や放射性物質を除去するすることを特徴とする廃液
処理装置。2. A waste liquid treatment apparatus in a boiling water nuclear power plant, wherein the waste liquid is passed through a device for decomposing or removing organic substances to decompose or remove organic substances contained in the waste liquid, and then to a desalination apparatus. A waste liquid treatment apparatus characterized in that ionic impurities and radioactive substances are removed through the waste liquid treatment apparatus.
は、紫外線照射装置、オゾン発生装置、過酸化水素水溶
液や次亜塩素酸水溶液などの酸化性物質の注入処理装
置、活性炭フィルタの少なくとも１つとする請求項２記
載の廃液処理装置。3. The apparatus for decomposing or removing an organic substance includes at least one of an ultraviolet irradiation apparatus, an ozone generation apparatus, an injection processing apparatus for an oxidizing substance such as an aqueous solution of hydrogen peroxide and an aqueous solution of hypochlorous acid, and an activated carbon filter. The waste liquid treatment apparatus according to claim 2, wherein
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP6696598A JPH11264896A (en) | 1998-03-17 | 1998-03-17 | Processing method for waste liquid and processing device of waste liquid |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP6696598A JPH11264896A (en) | 1998-03-17 | 1998-03-17 | Processing method for waste liquid and processing device of waste liquid |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH11264896A true JPH11264896A (en) | 1999-09-28 |
Family
ID=13331257
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP6696598A Pending JPH11264896A (en) | 1998-03-17 | 1998-03-17 | Processing method for waste liquid and processing device of waste liquid |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH11264896A (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2008232773A (en) * | 2007-03-20 | 2008-10-02 | Japan Organo Co Ltd | Treater for water containing radioactive material in nuclear power plant |
| JP2012247329A (en) * | 2011-05-30 | 2012-12-13 | Hitachi-Ge Nuclear Energy Ltd | Processing method of radioactive waste |
| CN103474122A (en) * | 2013-09-04 | 2013-12-25 | 清华大学 | Method of removing tetrahydrofurfuryl alcohol from waste water in production of high temperature reactor fuel elements |
| US8871674B2 (en) | 2011-10-31 | 2014-10-28 | Seibu Newspaper Company | Radioactive-substance-absorbent, radioactive-substance-absorbent production device, and bag unit |
-
1998
- 1998-03-17 JP JP6696598A patent/JPH11264896A/en active Pending
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2008232773A (en) * | 2007-03-20 | 2008-10-02 | Japan Organo Co Ltd | Treater for water containing radioactive material in nuclear power plant |
| JP2012247329A (en) * | 2011-05-30 | 2012-12-13 | Hitachi-Ge Nuclear Energy Ltd | Processing method of radioactive waste |
| US8871674B2 (en) | 2011-10-31 | 2014-10-28 | Seibu Newspaper Company | Radioactive-substance-absorbent, radioactive-substance-absorbent production device, and bag unit |
| CN103474122A (en) * | 2013-09-04 | 2013-12-25 | 清华大学 | Method of removing tetrahydrofurfuryl alcohol from waste water in production of high temperature reactor fuel elements |
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Effective date: 20041028 Free format text: JAPANESE INTERMEDIATE CODE: A971007 |
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