JPS6051680B2 - How to dispose of radioactive waste liquid - Google Patents
How to dispose of radioactive waste liquidInfo
- Publication number
- JPS6051680B2 JPS6051680B2 JP15118081A JP15118081A JPS6051680B2 JP S6051680 B2 JPS6051680 B2 JP S6051680B2 JP 15118081 A JP15118081 A JP 15118081A JP 15118081 A JP15118081 A JP 15118081A JP S6051680 B2 JPS6051680 B2 JP S6051680B2
- Authority
- JP
- Japan
- Prior art keywords
- waste liquid
- oxidizing agent
- radioactive waste
- treatment method
- organic compounds
- 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.)
- Expired
Links
- 239000007788 liquid Substances 0.000 title claims description 33
- 239000002901 radioactive waste Substances 0.000 title claims description 15
- 239000002699 waste material Substances 0.000 claims description 22
- 238000000034 method Methods 0.000 claims description 19
- 150000002894 organic compounds Chemical class 0.000 claims description 18
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Chemical compound O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 15
- 239000007800 oxidant agent Substances 0.000 claims description 12
- 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
- 238000001704 evaporation Methods 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
- CBENFWSGALASAD-UHFFFAOYSA-N Ozone Chemical compound [O-][O+]=O CBENFWSGALASAD-UHFFFAOYSA-N 0.000 claims description 7
- 230000008020 evaporation Effects 0.000 claims description 7
- MHAJPDPJQMAIIY-UHFFFAOYSA-N Hydrogen peroxide Chemical compound OO MHAJPDPJQMAIIY-UHFFFAOYSA-N 0.000 claims description 6
- 230000008023 solidification Effects 0.000 claims description 3
- 238000007711 solidification Methods 0.000 claims description 3
- 238000001035 drying Methods 0.000 claims description 2
- 230000001678 irradiating effect Effects 0.000 claims description 2
- 230000002285 radioactive effect Effects 0.000 claims 1
- OKKJLVBELUTLKV-UHFFFAOYSA-N Methanol Chemical compound OC OKKJLVBELUTLKV-UHFFFAOYSA-N 0.000 description 15
- 238000006864 oxidative decomposition reaction Methods 0.000 description 8
- GETQZCLCWQTVFV-UHFFFAOYSA-N trimethylamine Chemical compound CN(C)C GETQZCLCWQTVFV-UHFFFAOYSA-N 0.000 description 6
- 230000003647 oxidation Effects 0.000 description 5
- 238000007254 oxidation reaction Methods 0.000 description 5
- 239000000126 substance Substances 0.000 description 3
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 2
- 150000001412 amines Chemical class 0.000 description 2
- 238000000354 decomposition reaction Methods 0.000 description 2
- 239000012530 fluid Substances 0.000 description 2
- 239000007789 gas Substances 0.000 description 2
- 239000000941 radioactive substance Substances 0.000 description 2
- 238000001179 sorption measurement Methods 0.000 description 2
- 239000012855 volatile organic compound Substances 0.000 description 2
- ZAMOUSCENKQFHK-UHFFFAOYSA-N Chlorine atom Chemical compound [Cl] ZAMOUSCENKQFHK-UHFFFAOYSA-N 0.000 description 1
- 241000931705 Cicada Species 0.000 description 1
- 238000005273 aeration Methods 0.000 description 1
- 150000001298 alcohols Chemical class 0.000 description 1
- 239000003957 anion exchange resin Substances 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 239000003153 chemical reaction reagent Substances 0.000 description 1
- 239000000460 chlorine Substances 0.000 description 1
- 229910052801 chlorine Inorganic materials 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 238000001514 detection method Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000002474 experimental method Methods 0.000 description 1
- 239000002925 low-level radioactive waste Substances 0.000 description 1
- QSHDDOUJBYECFT-UHFFFAOYSA-N mercury Chemical compound [Hg] QSHDDOUJBYECFT-UHFFFAOYSA-N 0.000 description 1
- 229910052753 mercury Inorganic materials 0.000 description 1
- 239000003595 mist Substances 0.000 description 1
- 230000001590 oxidative effect Effects 0.000 description 1
- 239000010908 plant waste Substances 0.000 description 1
- 239000000843 powder Substances 0.000 description 1
- 238000003672 processing method Methods 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 150000003839 salts Chemical class 0.000 description 1
Landscapes
- Physical Water Treatments (AREA)
Description
【発明の詳細な説明】
−
ー本発明は、放射性廃液から放射性物質および懸濁また
は溶存物質を除去して、再使用するための放射性廃液の
処理方法の改良に関する。DETAILED DESCRIPTION OF THE INVENTION - The present invention relates to an improvement in a method for treating a radioactive waste solution for removing radioactive substances and suspended or dissolved substances from the radioactive waste solution for reuse.
原子力発電所の廃棄物処理施設において発生する低レ
ベル放射性廃液は、蒸発濃縮して濃縮廃液は固化処理し
、蒸発した水分は凝縮してイオン交換樹脂で処理し、再
利用している。Low-level radioactive waste fluid generated at nuclear power plant waste treatment facilities is evaporated and concentrated, the concentrated waste fluid is solidified, and the evaporated water is condensed and treated with ion exchange resin for reuse.
ところで、アニオン交換樹脂は一般に熱や放射線に対
してあまり安定ではなく、一部が分解してアミン（たと
えばトリメチルアミン）やアルコール（たとえばメタノ
ール）を生成する。Incidentally, anion exchange resins are generally not very stable against heat or radiation, and a portion of them decomposes to produce amines (eg, trimethylamine) and alcohols (eg, methanol).
これらの有機化合物はもともと低沸点であつて容易に揮
発するし、そのほかの不揮発性の有機化合物も、蒸発濃
縮に際して熱分解されて揮発性成分を生じたりし、水蒸
気とともに凝縮器に送られる。凝縮水中に含有された（
ほとんど溶解している）有機化合物は、一部はイオン交
換樹脂に吸着されるが、一部は吸着されずに処理水中に
混入したまま循環する。吸着されたものは、イオン交換
樹脂の再生時に放出され、その再生廃液は上記の廃液処
理に際して一緒に処理するので、結局は処理水中に移行
する。 このようにして、循環する回収水の中には、次
第に有機化合物が蓄積する傾向があるので、その除去を
はからなければならない。These organic compounds originally have low boiling points and are easily volatilized, and other non-volatile organic compounds are also thermally decomposed during evaporation and concentration to produce volatile components, which are sent to the condenser together with water vapor. Contained in condensed water (
Some of the organic compounds (mostly dissolved) are adsorbed by the ion exchange resin, but some remain unadsorbed and circulate in the treated water. The adsorbed substances are released when the ion exchange resin is regenerated, and since the regenerated waste liquid is treated together with the above-mentioned waste liquid treatment, it is eventually transferred to the treated water. In this way, organic compounds tend to gradually accumulate in the recycled recycled water and must be removed.
水中の有機化合物を除去する方法としては、活性炭な
どを用いる吸着、エアーストリツピング、および紫外線
プラス塩素を用いた酸化分解などがあるが、吸着能率や
二次廃棄物の処理、あるいは装置の腐食といつた問題が
伴うので、いずれも放射性廃液の処理には不向きである
。Methods for removing organic compounds from water include adsorption using activated carbon, air stripping, and oxidative decomposition using ultraviolet rays plus chlorine, but there are problems with adsorption efficiency, secondary waste treatment, and equipment corrosion. Both methods are unsuitable for treating radioactive waste liquids because of the following problems.
今回、本発明者らは、紫外線の照射下に酸化剤とくにオ
ゾンまたは過酸化水素を使用する酸化分解という、上記
のような問題のない廃液中有機化合物の除去を見出し、
これをとりいれた放射性廃液の蝉稈方法を轡飢ｔこ？で
、ここに提案する、恣第てある。This time, the present inventors have discovered a method for removing organic compounds in waste liquid without the above-mentioned problems by oxidative decomposition using an oxidizing agent, particularly ozone or hydrogen peroxide, under irradiation with ultraviolet light.
Are you looking for a cicada culm method for radioactive waste liquid that incorporates this? So, here is an arbitrary suggestion.
本発明の放射性廃液の処理方法は放射性廃液を蒸発濃縮
して発生する水蒸気を凝縮し回収再使用する処理方法に
おいて、蒸発濃縮を行なう廃液に対し、または蒸発濃縮
の後に得た復水に対し、紫外線を照射しつつ酸化剤を作
用させて、廃液または復本中に含有されている有機化合
物を酸化分解することにより、有機化合物を含まない回
収水を得ることを特徴とする。The radioactive waste liquid treatment method of the present invention is a treatment method in which the radioactive waste liquid is evaporated and concentrated, and the generated water vapor is condensed and recovered and reused. The method is characterized in that recovered water containing no organic compounds is obtained by oxidizing and decomposing organic compounds contained in the waste liquid or book duplication by applying an oxidizing agent while irradiating ultraviolet rays.
蒸発濃縮により生じた濃縮廃液は、固化系へ送つて処理
すればよい。酸化剤としては、前述のようにオゾンまた
は過酸化水素を使用するが、とくにアミン等の求電子試
薬としてはオゾンが有用である。これらの酸化剤は、装
置を腐食するおそれがほとんどなく、しかも使用後は無
害な０２やＨ２Ｏに分解し、蓄積することがないから、
二次廃棄物の問題も生じない。本発明において、紫外線
照射下の酸化剤による有機化合物の酸化分解を、蒸発濃
縮に先立つて、っまり蒸発濃縮を行なう廃液を対象にし
て実施する場合は、第１図に示すフローの装置を用いる
ことになる。The concentrated waste liquid produced by evaporation concentration may be sent to a solidification system for treatment. As the oxidizing agent, ozone or hydrogen peroxide is used as described above, and ozone is particularly useful as an electrophilic reagent such as an amine. These oxidants have little risk of corroding equipment, and after use they decompose into harmless 02 and H2O and do not accumulate.
There is no problem of secondary waste. In the present invention, when performing oxidative decomposition of organic compounds using an oxidizing agent under ultraviolet irradiation on waste liquid that is subjected to evaporative concentration prior to evaporative concentration, an apparatus having the flow shown in FIG. 1 is used. It turns out.
すなわち、処理すべき放射性廃液Ｒｗを、ます酸化処理
槽１において、紫外線を照射しつつ酸化剤０ｘを作用さ
せてその中の有機化合物を酸化し、流出液を蒸発濃縮装
置２に送る。That is, the radioactive waste liquid Rw to be treated is irradiated with ultraviolet rays in the oxidation treatment tank 1 and an oxidizing agent 0x is applied thereto to oxidize the organic compounds therein, and the effluent is sent to the evaporation concentration device 2.
酸化剤としてオゾンを空気とともに吹き込んだ場合は、
排ガスを、ミストキヤツチヤー３をへて適宜の排ガス処
理装置４に通して処理したのち放出する。蒸発濃縮装置
２からの濃縮廃液は、濃縮廃液タンク５に受け、固化工
程に送る。揮発成分は、コンデンサ６で凝縮してイオン
交換樹脂塔７で処理し、回収水タンク８に貯えて、循環
再使用する。一方、酸化分解を蒸発濃縮の後に、つまり
蒸発濃縮で得た復水を対象に実施する場合は、第２図に
示すフローの装置を用いることになる。When ozone is blown in with air as an oxidizing agent,
The exhaust gas is passed through the mist catcher 3 and passed through a suitable exhaust gas treatment device 4 to be treated and then released. The concentrated waste liquid from the evaporative concentrator 2 is received in the concentrated waste liquid tank 5 and sent to the solidification process. The volatile components are condensed in a condenser 6, treated in an ion exchange resin tower 7, stored in a recovered water tank 8, and recycled for reuse. On the other hand, when oxidative decomposition is performed after evaporative concentration, that is, when performing oxidative decomposition on condensate obtained by evaporative concentration, an apparatus having the flow shown in FIG. 2 is used.
この場合の工程は、上述したところと一部の順序が変る
だけであるから、再度の説明を要しないであろう。一般
に、前者すなわち第１図の態様は、蒸発濃縮時に発泡性
のある廃液または揮発性の有機物を含む廃液番三対して
実施する一のが適切であり、また後者つまり第２図の態
様は、蒸発濃縮に際してキャリヤーオーバー守る揮発性
有機化合物を含む廃液を処理すべき場合に好都合である
。The steps in this case do not need to be explained again because only a part of the order is changed from that described above. In general, the former mode, that is, the embodiment shown in FIG. 1, is suitable for use with waste liquids that are foamy or contain volatile organic substances during evaporation, and the latter mode, that is, the embodiment shown in FIG. This is advantageous when waste liquids containing volatile organic compounds that carry over during evaporative concentration are to be treated.
−本発明の処理方法は、いうまでもないが、バッチ式、
連続式のいずれでも実施できる。- Needless to say, the processing method of the present invention is a batch method,
It can be carried out either continuously.
酸化処理の条件、すなわち槽内滞留時間、紫外線の強さ
、酸化剤の供給量などは、処理する廃液中に含まれる有
機化合物の種類や濃度によつても異なるが、当業者は、
後記する実例を参考に、必要ならば多少の実験を追加す
ることにより、適切な条件を容易に見出せるであろう。
本発明の処理方法により、放射性廃液から、放射性物質
や塩類はもちろん、有機化合物も含まない回収水が得ら
れ、好適に再使用に供することができ今。The conditions for oxidation treatment, such as the residence time in the tank, the intensity of ultraviolet rays, and the amount of oxidizing agent supplied, vary depending on the type and concentration of organic compounds contained in the waste liquid to be treated, but those skilled in the art can
Appropriate conditions can be easily found by referring to the examples described later and performing some additional experiments if necessary.
By the treatment method of the present invention, recovered water containing not only radioactive substances and salts but also organic compounds can be obtained from radioactive waste liquid, and can be suitably reused.
このようにして、本発明によれば、原子力発電所の廃棄
物処理施設における放射性廃液の処理に関し、クローズ
ドシステムが実現する。In this way, according to the invention, a closed system is realized for the treatment of radioactive waste liquid in the waste treatment facility of a nuclear power plant.
実施例
第１図に示す構成の装置を用いて、イオン交換樹脂の乾
燥工程において発生する復水を、５ｅ／時の割合で処理
した。Example Using an apparatus having the configuration shown in FIG. 1, condensate generated during the drying process of an ion exchange resin was treated at a rate of 5e/hour.
この廃液は、有機化合物としてトリメチルアミン３００
ｐｐｍおよびメタノール１５０ｐｐｍを含有している。
酸化処理槽は容積１０ｅで、底部に散気管を有しており
、これを通して、オゾンを含む空気をオゾン量にして０
．５ｙ／分の速度で供給しつつ、出力１００Ｗの水銀ラ
ンプからの紫外線を照射した。This waste liquid contains trimethylamine 300% as an organic compound.
ppm and methanol 150 ppm.
The oxidation treatment tank has a volume of 10e and has an aeration pipe at the bottom, through which air containing ozone is converted into ozone and 0.
．． Ultraviolet light was irradiated from a mercury lamp with an output of 100 W while supplying at a rate of 5 y/min.
槽からの流出液中のトリメチルアミンおよびメタノール
の分解率は、ともに約９９％であつた。これを蒸発濃縮
して得た復水中の有機化合物は、検出限界以内であつた
。以下、これを常法に従つてイオン交換樹脂で処理した
処理水は、再利用上全く問題のないものであつた。実際
的な操業条件または装置の能力の限界を知るために、メ
タノール１７０ｐｐｍを含有する廃液を処理の対象とし
、酸化処理槽内の液滞留時間を短縮して行つたところ、
第３図に示すメタノール分解率を得た。The decomposition rates of trimethylamine and methanol in the effluent from the tank were both about 99%. The organic compounds in the condensate obtained by evaporation and concentration were within the detection limit. Hereinafter, the treated water was treated with an ion exchange resin according to a conventional method, and there was no problem in terms of reuse. In order to find out the practical operating conditions or the limits of the equipment's capacity, we treated a waste liquid containing 170 ppm of methanol and shortened the residence time of the liquid in the oxidation treatment tank.
The methanol decomposition rate shown in FIG. 3 was obtained.
このグラフから、使用した装置においては、６紛以上８
紛程度の液滞留時間を与えれば、ほぼ完全に酸化分解を
行なえることがわかつた。From this graph, it can be seen that with the equipment used, 6 to 8
It was found that almost complete oxidative decomposition can be achieved by giving the liquid a residence time equivalent to that of powder.
第１図および第２図は、ともに本発明の放射性廃液の処
理方法を説明するためのフローチャートであつて、第１
図は、有機化合物の酸化分解を蒸発濃縮操作にかける前
の廃液に対して行なう態様を、また第２図は、有機化合
物の酸化分解を蒸発濃縮操作によつて得た復水に対して
行なう態様を、それぞれ示す。
第３図は、本発明の実施例の効果を示すグラフである。
１・・・・・・酸化処理槽、２・・・・・・蒸発濃縮装
置、６・・・・・コンデンサ、７・・・・・・イオン交
換樹脂塔。1 and 2 are flowcharts for explaining the radioactive waste liquid treatment method of the present invention.
The figure shows how oxidative decomposition of organic compounds is performed on waste liquid before being subjected to evaporative concentration operation, and Figure 2 shows how oxidative decomposition of organic compounds is performed on condensate obtained through evaporative concentration operation. Each aspect is shown below. FIG. 3 is a graph showing the effects of the embodiment of the present invention.
1... Oxidation treatment tank, 2... Evaporation concentration device, 6... Condenser, 7... Ion exchange resin tower.
Claims (1)
回収再使用する処理方法において、蒸発濃縮を行なう廃
液に対し、または蒸発濃縮の後に得た復水に対し、紫外
線を照射しつつ酸化剤を作用させて、廃液または復水中
に含有されている機化合物の酸化分解を行なつて回収水
を得ることを特徴とする放射性廃液の処理方法。 ２ 酸化剤としてオゾンまたは過酸化水素を使用する特
許請求の範囲第１項の処理方法。 ３ 廃液または復水中に含有されている有機化合物を、
まず酸化剤を作用させてその一部を酸化分解し、ついで
紫外線を照射しつつ酸化剤を作用させて残りを分解する
二段法による特許請求の範囲第１項の処理方法。 ４ 有機化合物を含む放射性廃液が、放射性イオン交換
樹脂の乾燥により発生する蒸気を凝縮して得た放射性廃
液である特許請求の範囲第１項の処理方法。 ５ 蒸発濃縮工程で発生した濃縮廃液を固化系へ送つて
処理する工程を含む特許請求の範囲第１項の処理方法。[Scope of Claims] 1 In a treatment method in which water vapor generated by evaporating and concentrating radioactive waste liquid is condensed and recovered and reused, ultraviolet rays are applied to the waste liquid undergoing evaporative concentration or to the condensate obtained after evaporative concentration. 1. A method for treating radioactive waste liquid, which comprises irradiating and applying an oxidizing agent to oxidatively decompose organic compounds contained in the waste liquid or condensate to obtain recovered water. 2. The treatment method according to claim 1, which uses ozone or hydrogen peroxide as an oxidizing agent. 3. Organic compounds contained in waste liquid or condensate are
The treatment method according to claim 1, which is a two-step method, in which a part of the oxidizing agent is first applied to oxidize and decompose it, and then the remaining part is decomposed by applying an oxidizing agent while being irradiated with ultraviolet rays. 4. The treatment method according to claim 1, wherein the radioactive waste liquid containing an organic compound is a radioactive waste liquid obtained by condensing vapor generated by drying a radioactive ion exchange resin. 5. The treatment method according to claim 1, which includes a step of sending the concentrated waste liquid generated in the evaporation concentration step to a solidification system for treatment.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP15118081A JPS6051680B2 (en) | 1981-09-24 | 1981-09-24 | How to dispose of radioactive waste liquid |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP15118081A JPS6051680B2 (en) | 1981-09-24 | 1981-09-24 | How to dispose of radioactive waste liquid |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5852599A JPS5852599A (en) | 1983-03-28 |
| JPS6051680B2 true JPS6051680B2 (en) | 1985-11-15 |
Family
ID=15513039
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP15118081A Expired JPS6051680B2 (en) | 1981-09-24 | 1981-09-24 | How to dispose of radioactive waste liquid |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6051680B2 (en) |
Families Citing this family (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS59226898A (en) * | 1983-06-08 | 1984-12-20 | 日揮株式会社 | Method of treating radioactive organic waste |
| US4624792A (en) * | 1983-12-12 | 1986-11-25 | Jgc Corporation | Method for treating radioactive organic wastes |
| JPS61104299A (en) * | 1984-10-26 | 1986-05-22 | 日揮株式会社 | Method of disposing radioactive decontaminated waste liquor |
| JPS63158497A (en) * | 1986-08-20 | 1988-07-01 | 富士電機株式会社 | Decomposing processing method of radioactive ion exchange resin |
| FR2825294B1 (en) * | 2001-05-29 | 2004-05-21 | Commissariat Energie Atomique | METHOD AND DEVICE FOR SELECTIVELY ELIMINATING FUNCTIONALIZED ORGANIC COMPOUNDS FROM A LIQUID MEDIUM |
-
1981
- 1981-09-24 JP JP15118081A patent/JPS6051680B2/en not_active Expired
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5852599A (en) | 1983-03-28 |
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