JPH0387700A - Treating method for radioactive waste liquid - Google Patents
Treating method for radioactive waste liquidInfo
- Publication number
- JPH0387700A JPH0387700A JP1223286A JP22328689A JPH0387700A JP H0387700 A JPH0387700 A JP H0387700A JP 1223286 A JP1223286 A JP 1223286A JP 22328689 A JP22328689 A JP 22328689A JP H0387700 A JPH0387700 A JP H0387700A
- Authority
- JP
- Japan
- Prior art keywords
- waste liquid
- activated carbon
- valve
- hydrogen peroxide
- pump
- 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
- 239000007788 liquid Substances 0.000 title claims abstract description 35
- 239000002901 radioactive waste Substances 0.000 title claims abstract description 16
- 238000000034 method Methods 0.000 title claims description 9
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 claims abstract description 78
- MHAJPDPJQMAIIY-UHFFFAOYSA-N Hydrogen peroxide Chemical compound OO MHAJPDPJQMAIIY-UHFFFAOYSA-N 0.000 claims abstract description 26
- 238000001179 sorption measurement Methods 0.000 claims description 5
- 230000007423 decrease Effects 0.000 claims description 3
- 239000002699 waste material Substances 0.000 abstract description 19
- 239000000126 substance Substances 0.000 abstract description 12
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract description 4
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 abstract description 3
- 229910052760 oxygen Inorganic materials 0.000 abstract description 3
- 239000001301 oxygen Substances 0.000 abstract description 3
- 230000002285 radioactive effect Effects 0.000 abstract description 2
- 238000005406 washing Methods 0.000 description 4
- 239000002351 wastewater Substances 0.000 description 3
- 239000003599 detergent Substances 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 239000012530 fluid Substances 0.000 description 2
- 239000004615 ingredient Substances 0.000 description 2
- 230000003247 decreasing effect Effects 0.000 description 1
- 230000007613 environmental effect Effects 0.000 description 1
- 238000001914 filtration Methods 0.000 description 1
- 239000002245 particle Substances 0.000 description 1
- 239000000941 radioactive substance Substances 0.000 description 1
- 230000008929 regeneration Effects 0.000 description 1
- 238000011069 regeneration method Methods 0.000 description 1
- 210000004243 sweat Anatomy 0.000 description 1
Abstract
Description
【発明の詳細な説明】
「発明のＦ］的］
（産業上の利用分野）
本発明は、原子力施設より発生する放射性廃液の処理方
法に関し、特に衣服の洗濯水、手洗い、シャワー等の放
射能濃度の極めて低い廃液の処理方法に関する。Detailed Description of the Invention [F] Field of the Invention (Industrial Application Field) The present invention relates to a method for treating radioactive waste fluid generated from nuclear facilities, and in particular to a method for treating radioactive waste fluid such as washing water for clothes, hand washing, showering, etc. This invention relates to a method for treating waste liquid with extremely low concentration.
（従来の技術）
原子力施設、特に原子力発電所では、作業員の使用した
衣服の洗濯水や、手洗い、シャワー等の廃水が発生する
。このような廃水の特徴は、放射能濃度が極めて低く、
洗剤成分や、糸屑、髪の毛、垢等の不溶解成分が含まれ
でいることである。、これらの廃液を処理する場合、現
在はストレーナ−等により糸廐等の大きなごみを除去し
た後、放射能を測定し、規定濃度以下の放射能であるこ
とを確認し”Ｃ環境に放出している。(Prior Art) Nuclear facilities, especially nuclear power plants, generate wastewater such as water used by workers for washing clothes, washing hands, and showering. The characteristics of such wastewater are that the radioactivity concentration is extremely low.
It contains detergent ingredients and insoluble ingredients such as lint, hair, and dirt. When processing these waste liquids, currently, after removing large debris such as threads using a strainer, the radioactivity is measured, and the radioactivity is confirmed to be below the specified concentration before being released into the environment. ing.
しかしながら、この方法では、廃液中の洗剤や垢等の各
穐有機成分がそのまま放出されるので、環境保全上好ま
しくない。However, this method is unfavorable in terms of environmental conservation, since organic components such as detergent and dirt in the waste liquid are released as they are.
（発明が解決しようとする課題）
そこで、廃水中に含まれる溶解性物質と不溶解性物質と
を活性炭により一度に除去”４ることを試みた。ところ
が、活性炭の溶解性物質り吸香する能力には限度があり
、吸着能力が低下したたきには活性炭を交換しなければ
ならない。この使用済みの活性炭には装置ではあるが放
射能が含まれＣいるので、一般廃棄物として廃棄するこ
とができず、また焼却等の処理を行お・）としても活性
炭の粒径が小さいために焼却炉の火格子から落Ｆ！７、
殆ど燃焼するこ、Ｊ：なく灰受に貯蔵されることになる
。。(Problem to be solved by the invention) Therefore, an attempt was made to simultaneously remove soluble and insoluble substances contained in wastewater using activated carbon. There is a limit to the capacity, and the activated carbon must be replaced when the adsorption capacity has decreased.Although this used activated carbon is a device, it contains radioactivity and C, so it should be disposed of as general waste. Even if the activated carbon is not processed by incineration, etc., it falls from the incinerator grate due to the small particle size of the activated carbon.
Most of it will not burn and will be stored in the ash receiver. .
本発明はかかる状況に対処してなされたもので、低放射
性濃度の放射性廃液から溶解性物質と不溶解性物質を効
率的に除去することを目的とし、さらにかかる処理に使
用する活性炭を再使用して放射性廃棄物の生成を阻止す
ることを目的とするものである。The present invention was made in response to such a situation, and aims to efficiently remove soluble and insoluble substances from radioactive waste liquid with a low radioactive concentration, and further reuse activated carbon used in such treatment. The purpose is to prevent the generation of radioactive waste.
［発明の構成コ
（課題を解決するための手段）
すなわち、本発明は、放射性廃液を活性炭で処理し、活
性炭の吸着能力が低下したときに活性炭を過酸化水素で
再生して再使用することを特徴とする放射性廃液の処理
方法に関する。[Components of the Invention (Means for Solving the Problem) That is, the present invention is to treat radioactive waste liquid with activated carbon, and when the adsorption capacity of the activated carbon decreases, the activated carbon is regenerated with hydrogen peroxide and reused. The present invention relates to a method for treating radioactive waste liquid, characterized by:
（作用）
放射性廃液を活性炭で処理することによって、廃液中の
不溶解性物質は濾過除去され、溶解性物質は吸着除去さ
れる。これにより、廃液中の化学的酸素要求量（ＣＯＤ
）は低下する。一方活性炭に吸着された物質は過酸化水
素で処理することにより酸化分解され、再びこの活性炭
を使用することができるので、活性炭を取り替える必要
がなく、放射性廃棄物として新たな問題を生ずることが
ない。(Function) By treating the radioactive waste liquid with activated carbon, insoluble substances in the waste liquid are removed by filtration, and soluble substances are removed by adsorption. This increases the chemical oxygen demand (COD) in the waste liquid.
) decreases. On the other hand, substances adsorbed on activated carbon are oxidized and decomposed by treatment with hydrogen peroxide, and this activated carbon can be used again, so there is no need to replace the activated carbon and no new problems arise as radioactive waste. .
（実施例） 本発明の実施例を図面を参照して説明する。(Example) Embodiments of the present invention will be described with reference to the drawings.
第１図は本発明の放射性廃液の処理方法の一実施例に使
用される装置の説明図である。第１図において、１は給
液タンク、２は供給ポンプ、３は活性炭充填容器、４は
活性炭、５は圧力計、６は過酸化水素供給タンク、７は
ポンプ、８は使用済み過酸化水素受はタンクである。FIG. 1 is an explanatory diagram of an apparatus used in an embodiment of the radioactive waste liquid treatment method of the present invention. In Figure 1, 1 is a liquid supply tank, 2 is a supply pump, 3 is an activated carbon filling container, 4 is activated carbon, 5 is a pressure gauge, 6 is a hydrogen peroxide supply tank, 7 is a pump, and 8 is used hydrogen peroxide. Uke is a tank.
第２図は活性炭充填容器３の縦断面図である。FIG. 2 is a longitudinal sectional view of the activated carbon filling container 3.
これは円筒状の容器に活性炭４が充填されて構成されて
おり、該容器には廃液供給口ａと処理液出口すがある。This is constructed by filling a cylindrical container with activated carbon 4, and the container has a waste liquid supply port a and a processing liquid outlet port.
廃液は廃液供給口ａから入り、活性炭充填層を通過して
溶解性物質および不溶解性物質を除去され、浄化されて
処理液出口すから排出される。The waste liquid enters from the waste liquid supply port a, passes through an activated carbon packed bed, removes soluble and insoluble substances, is purified, and is discharged from the treated liquid outlet.
上記装置を使用して、模擬廃液の浄化処理を行った。模
擬廃液は下記第１表に示す組成のものである。A simulated waste liquid was purified using the above apparatus. The simulated waste liquid had the composition shown in Table 1 below.
第
表
まず、模擬廃液を給液タンクｌに供給し、ポンプ２を作
動させて弁Ｖｌを開にし、活性炭充填容器３に模擬廃液
を供給した。充填された活性炭は第２表に示す性状のも
のである。First, the simulated waste liquid was supplied to the liquid supply tank 1, the pump 2 was operated to open the valve V1, and the simulated waste liquid was supplied to the activated carbon filling container 3. The filled activated carbon has properties shown in Table 2.
第 ２ 表
活性炭充填容器３の出口に設置した化学的酸素要求量計
（ＣＯＤ計）で処理水のＣＯＤを測定し、ＣＯＤが規定
以上に達した時点でポンプ２を停止し、弁Ｖｔを閉じた
。つぎに、ポンプ７を駆動し、弁ｖ３を開き、過酸化水
素（濃度３０％）を所定量活性炭充填容器３に供給する
。このまま１０〜３０時間放置した後、弁■３を閉じ、
弁ｖ２を開いて過酸化水素を使用済み過酸化水素受はタ
ンク８に排出した。以上で活性炭の再生が終了した。弁
ｖ２およびｖ３を閉じた後、再び弁ｖ１を開き、ポンプ
２を作動して再び廃液を活性炭充填容器３に供給し、同
じ動作を繰り返した。Table 2 Measure the COD of the treated water with a chemical oxygen demand meter (COD meter) installed at the outlet of the activated carbon filling container 3, and when the COD reaches the specified value, stop the pump 2 and close the valve Vt. Ta. Next, the pump 7 is driven, the valve v3 is opened, and a predetermined amount of hydrogen peroxide (concentration 30%) is supplied to the activated carbon filling container 3. After leaving it as it is for 10 to 30 hours, close valve 3.
The hydrogen peroxide was discharged into the tank 8 by opening the valve v2. This completes the regeneration of activated carbon. After closing the valves v2 and v3, the valve v1 was opened again, the pump 2 was operated, the waste liquid was again supplied to the activated carbon filling container 3, and the same operation was repeated.
上記操作による処理液のＣＯＤ濃度を測定した結果を第
３表に示す。Table 3 shows the results of measuring the COD concentration of the treatment solution obtained by the above operation.
第 ３ 表
この表から明らかなように、処理損５０ｍ３ （処理時
間２５０時間）で活性炭充填容器３の出目でＱ）ＣＯＤ
値は４０ｐｐｍに達し５、こＣ）時点で過酸化水素によ
り活性炭の再生を行ったと、゛８ろ、処理液のＣＯＤ濃
度は３ ｐｐｎ＋になり、活性炭の吸着能がほぼ完全に
回復したことを示しくいる。Table 3 As is clear from this table, Q) COD is determined by the roll of activated carbon filling container 3 at a processing loss of 50 m3 (processing time 250 hours).
The COD concentration reached 40 ppm5, and when the activated carbon was regenerated with hydrogen peroxide at point C), the COD concentration in the treated solution became 3 ppn+, indicating that the adsorption capacity of the activated carbon had almost completely recovered. I'll show you.
したがって、活性炭を交換４−ることな（再び廃液処理
を行うＪ８とができる。また、活性炭θ）再生を充填容
器内で行うために？１！；性１ｘの抜きＬ＋ＪＩ１．、
、’等０）手間が省番Ｊた。Therefore, it is possible to perform waste liquid treatment again without replacing the activated carbon.Also, in order to regenerate the activated carbon θ in the filling container? 1! ; Gender 1x removal L+JI1. ,
,' etc. 0) It took a lot of effort.
１発明の効果１
本発明によれば、原子力施設で発生する々服Ｑ）洗濯水
、手洗い、ジャワ・−一等０）放射能溌度の極ぬて低い
廃液中の溶解性物質および不溶解性物質を容易に除去す
ることかでき、（、かも放射性廃棄物を発生さぜないと
いう効果がある。1. Effects of the invention 1. According to the present invention, it is possible to reduce the amount of soluble and insoluble substances in the waste liquid generated at nuclear facilities. It is possible to easily remove radioactive substances (and also has the effect of not generating radioactive waste).
第１図は本発明の放射性廃液の処理り法θ）−・実施例
に使用される装置の説明図、第２図（，４，第１図にお
ける活性炭充填容器Ｏ）断１１１ｉ′］ｌ’：ｌ ”’
ｒある。
１・・・給液タンク
２・・・供給ポンプ
３・・・活性炭充填容器
福・・・活性炭
！５・・・汗力計
０・・・過酸化水素供給クシ・り
７・・・ポンプFig. 1 is an explanatory diagram of the apparatus used in the radioactive waste liquid treatment method θ)--Example of the present invention, Fig. 2 (, 4, activated carbon filled container O in Fig. 1) :l ”'
There is r. 1... Liquid supply tank 2... Supply pump 3... Activated carbon filling container Fuku... Activated carbon! 5... Sweat meter 0... Hydrogen peroxide supply comb 7... Pump
Claims (1)
が低下したときに活性炭を過酸化水素で再生して再使用
することを特徴とする放射性廃液の処理方法。(1) A method for treating radioactive waste liquid, which comprises treating the radioactive waste liquid with activated carbon, and when the adsorption capacity of the activated carbon decreases, the activated carbon is regenerated with hydrogen peroxide and reused.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1223286A JPH0387700A (en) | 1989-08-31 | 1989-08-31 | Treating method for radioactive waste liquid |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1223286A JPH0387700A (en) | 1989-08-31 | 1989-08-31 | Treating method for radioactive waste liquid |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH0387700A true JPH0387700A (en) | 1991-04-12 |
Family
ID=16795754
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1223286A Pending JPH0387700A (en) | 1989-08-31 | 1989-08-31 | Treating method for radioactive waste liquid |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0387700A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US11735329B2 (en) | 2019-10-15 | 2023-08-22 | Korea Atomic Energy Research Institute | Radioactive chemical waste treatment apparatus |
-
1989
- 1989-08-31 JP JP1223286A patent/JPH0387700A/en active Pending
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US11735329B2 (en) | 2019-10-15 | 2023-08-22 | Korea Atomic Energy Research Institute | Radioactive chemical waste treatment apparatus |
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