JPH0574040B2 - - Google Patents
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- JPH0574040B2 JPH0574040B2 JP58059704A JP5970483A JPH0574040B2 JP H0574040 B2 JPH0574040 B2 JP H0574040B2 JP 58059704 A JP58059704 A JP 58059704A JP 5970483 A JP5970483 A JP 5970483A JP H0574040 B2 JPH0574040 B2 JP H0574040B2
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- organic waste
- containing organic
- sulfur
- radioactive
- liquid
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- Treatment Of Water By Oxidation Or Reduction (AREA)
Description
【発明の詳細な説明】
[発明の技術分野]
本発明は、原子力発電施設等の放射性物質取扱
い施設で発生する放射性含イオウ有機廃棄物を酸
化分解してなる分解液の処理方法およびこの分解
液を減容し固化するための放射性含イオウ有機廃
棄物の減容固化方法に関する。[Detailed Description of the Invention] [Technical Field of the Invention] The present invention relates to a method for treating a decomposition liquid obtained by oxidizing and decomposing radioactive sulfur-containing organic waste generated in facilities handling radioactive materials such as nuclear power generation facilities, and a method for treating the decomposition liquid. This invention relates to a method for volume reduction and solidification of radioactive sulfur-containing organic waste.
[発明の技術的背景とその問題点]
原子力発電所等の放射性物質取扱い施設におい
ては、種々の放射性固体廃棄物が発生するが、現
在のところその多くは最終処分方法が未だ確立せ
ず流動的であるため、固体廃棄物の主要な構成成
分である使用済みイオン交換樹脂およびフイルタ
ースラツジなどはそのまま主としてタンク等に貯
蔵保管されており、放射性廃棄物の発生量を減ら
すことは貯蔵管理の上で緊急かつ重要な課題とさ
れている。[Technical background of the invention and its problems] A variety of radioactive solid wastes are generated in facilities that handle radioactive materials such as nuclear power plants, but at present, the final disposal method for most of them has not yet been established and is in a state of flux. Therefore, used ion exchange resins and filter sludge, which are the main components of solid waste, are mainly stored in tanks, etc., and reducing the amount of radioactive waste generated is a priority in storage management. It is considered an urgent and important issue.
このような固体廃棄物の中でも、例えば使用済
み放射性イオン交換樹脂のような放射性有機廃棄
物は大量に発生するため、これを減容化すること
は発生廃棄物量の減少に大きく貢献する。 Among such solid wastes, radioactive organic wastes such as used radioactive ion exchange resins are generated in large quantities, so reducing the volume of this waste greatly contributes to reducing the amount of wastes generated.
ところで放射性有機廃棄物は高分子化合物であ
り、減容化の方法としてこれを化学構造的に分解
することが可能なため、従来から乾式焼却法、湿
式焼却法、熱分解法、化学分解法等の減容方法が
検討されている。 By the way, radioactive organic waste is a polymeric compound, and it is possible to decompose it chemically to reduce its volume. Therefore, conventional methods such as dry incineration, wet incineration, thermal decomposition, chemical decomposition, etc. have been used to reduce the volume. Volume reduction methods are being considered.
このうち乾式焼却法は文字通りそのまま焼却炉
で焼却する方法であつて、多くの方式の検討開発
が行なわれている。しかしながら、放射性有機廃
棄物を焼却炉において焼却する場合には、熱量の
コントロールが必要なため、乾燥等の前処理や廃
棄物の供給方法の工夫が必要であり、操作や設備
が複雑となる難点がある。また、焼却炉自身には
焼却灰の飛散を抑制する機能はないので、焼却炉
からの放射性焼却灰の飛散は非常に大きい
(DF:除染係数はほぼ1)。そして、焼却ガスと
してSOx,NOx等の有害ガスが放射性気体とし
て発生するので、廃ガス処理という後処理が放射
能対策も含めて必要であること、およびこれらの
ガスは腐蝕性が強く、装置材料の選定が難しいこ
と等の問題がある。さらにこの方法においては、
放射性有機廃棄物が高温の環境で処理されるため
に、発生する焼却ガス中へ放射能成分が移行す
る、いわゆる核種の移行という放射能取扱いに特
有な問題がある。 Among these methods, the dry incineration method is a method in which waste is incinerated as is in an incinerator, and many methods are being studied and developed. However, when radioactive organic waste is incinerated in an incinerator, it is necessary to control the amount of heat, so pre-treatment such as drying and waste supply methods must be devised, making operations and equipment complicated. There is. Furthermore, since the incinerator itself does not have a function to suppress the scattering of incinerated ash, the scattering of radioactive incinerated ash from the incinerator is extremely large (DF: decontamination factor is approximately 1). Since harmful gases such as SOx and NOx are generated as radioactive gases as incineration gas, post-processing called waste gas treatment is necessary, including measures against radioactivity, and these gases are highly corrosive and may cause damage to equipment materials. There are problems such as difficulty in selecting Furthermore, in this method,
Because radioactive organic waste is processed in a high-temperature environment, there is a problem unique to the handling of radioactivity, which is so-called nuclide migration, in which radioactive components migrate into the generated incineration gas.
また湿式焼却法は、水溶液中または硫酸銅水溶
液中で20〜100気圧、200〜300℃という高温高圧
下で酸素または空気を送り込むことによつて放射
性有機廃棄物を燃焼させる方法であつて、焼却の
条件が厳しいという難点に加え、減容率も前述の
乾式焼却法に比較して数段劣るという難点があ
る。 Wet incineration is a method of burning radioactive organic waste by pumping oxygen or air into an aqueous solution or an aqueous copper sulfate solution at high temperatures and pressures of 20 to 100 atmospheres and 200 to 300 degrees Celsius. In addition to the drawback that the conditions are severe, the volume reduction rate is also several steps inferior to the dry incineration method described above.
さらに熱分解法は、酸素の供給を遮断して加熱
分解させる方法であつて、不活性ガス雰囲気下で
高温で放射性有機廃棄物を熱分解するため、乾式
焼却法に比較して発生する媒塵の量が少ないとい
う利点を有する。しかしながら、この方法では分
解ガスの燃焼工程が余計に必要であるうえに、乾
式焼却法の場合と同様に放射性核種の移行の問題
がある。 Furthermore, the pyrolysis method is a method of thermally decomposing radioactive organic waste by cutting off the supply of oxygen, and because it thermally decomposes radioactive organic waste at high temperatures in an inert gas atmosphere, it generates more dust than the dry incineration method. It has the advantage that the amount of However, this method requires an extra step of burning the cracked gas, and, like the dry incineration method, there is the problem of radionuclide migration.
一方化学分解法は薬剤との化学反応により樹脂
を酸化分解させるもので、次のような方法が知ら
れている。 On the other hand, the chemical decomposition method oxidizes and decomposes the resin through a chemical reaction with a drug, and the following methods are known.
熱濃硫酸(130〜300℃)で放射性有機物を炭
化させた後、硝酸または過酸化水素で酸化分解
する方法。 A method of carbonizing radioactive organic materials with hot concentrated sulfuric acid (130-300℃) and then oxidizing and decomposing them with nitric acid or hydrogen peroxide.
主として鉄イオンまたはクロム酸イオンある
いは重クロム酸イオンの存在する溶液中で有機
廃棄物を過酸化水素水と接触させて酸化分解す
る方法。 A method of oxidative decomposition of organic waste by contacting it with hydrogen peroxide in a solution containing mainly iron ions, chromate ions, or dichromate ions.
しかしながらこれらの方法では、例えば、の
方法では強力酸および酸化剤を高温で取扱うため
に装置材料の選定が非常に厳しいという難点があ
り、の方法ではスルフオン基を有するカチオン
交換樹脂、あるいはこれを含む混合イオン交換樹
脂のような含イオウ有機廃棄物に由来する硫酸イ
オンの中和による硫酸塩が二次廃棄物として発生
するため、廃液の濃度が高く、また固化処理した
場合の減容効果が不十分であるという難点があ
る。 However, these methods have the disadvantage that, for example, the selection of equipment materials is very strict in order to handle strong acids and oxidizing agents at high temperatures. Because sulfate is generated as secondary waste due to the neutralization of sulfate ions derived from sulfur-containing organic waste such as mixed ion exchange resin, the concentration of waste liquid is high and the volume reduction effect of solidification treatment is ineffective. The problem is that it is enough.
[発明の目的]
本発明はかかる従来の事情に対処してなされた
もので、実施が容易な緩和な条件の下で、かつ無
機イオンまでも除去して廃液の濃度を低下させ、
かつ固化処理した場合に高い減容率を達成する放
射性含イオウ有機廃棄物分解液の処理方法および
減容固化方法の提供を目的とする。[Objective of the Invention] The present invention has been made in response to such conventional circumstances, and it is possible to reduce the concentration of waste liquid by removing even inorganic ions under easy-to-implement and easy-to-implement conditions.
Another object of the present invention is to provide a method for treating a radioactive sulfur-containing organic waste decomposition solution and a method for volume reduction and solidification that achieve a high volume reduction rate when solidified.
[発明の概要]
すなわち本発明は、放射性含イオウ有機廃棄物
を液中で過酸化水素または酸素含有ガスを酸化剤
として酸化分解して硫酸イオンを含有する分解液
を生成する酸化分解工程と、この分解液を還元剤
又は水素よりイオン化傾向の大きい金属の存在下
に加熱濃縮し、硫酸イオンを二酸化イオウに分解
して除去する硫酸イオン除去工程とを有すること
を特徴とする放射性含イオウ有機廃棄物分解液の
処理方法および放射性含イオウ有機廃棄物を液中
で過酸化水素または酸素含有ガスを酸化剤として
酸化分解して硫酸イオンを含有する分解液を生成
する酸化分解工程と、この分解液を還元剤又は水
素よりイオン化傾向の大きい金属の存在下に加熱
濃縮し、硫酸イオンを二酸化イオウに分解して除
去する硫酸イオン除去工程と、この硫酸イオン除
去工程後の分解液をPH調整し蒸発乾燥処理する乾
燥工程と、この乾燥処理後の乾燥残渣を固化材と
混合して固化させる固化処理工程とを有すること
を特徴とする放射性含イオウ有機廃棄物分解液の
減容固化方法である。[Summary of the Invention] That is, the present invention comprises an oxidative decomposition step in which radioactive sulfur-containing organic waste is oxidized and decomposed in a liquid using hydrogen peroxide or an oxygen-containing gas as an oxidizing agent to generate a decomposed liquid containing sulfate ions; Radioactive sulfur-containing organic waste characterized by comprising a sulfate ion removal step of heating and concentrating this decomposed liquid in the presence of a reducing agent or a metal that has a greater ionization tendency than hydrogen, and decomposing and removing sulfate ions into sulfur dioxide. A method for treating a decomposed liquid, and an oxidative decomposition step in which radioactive sulfur-containing organic waste is oxidized and decomposed in a liquid using hydrogen peroxide or an oxygen-containing gas as an oxidizing agent to produce a decomposed liquid containing sulfate ions, and this decomposed liquid A sulfate ion removal process involves heating and concentrating sulfate in the presence of a reducing agent or a metal that has a greater ionization tendency than hydrogen, decomposing sulfate ions into sulfur dioxide, and then adjusting the pH of the decomposed liquid after this sulfate ion removal process and evaporating it. This is a method for volume reduction and solidification of radioactive sulfur-containing organic waste decomposition liquid, which is characterized by comprising a drying step of drying, and a solidification step of mixing the dried residue after the drying treatment with a solidifying material and solidifying it.
図面は本発明を説明するための工程図である。
本発明の方法においては、例えば図示できるよう
に、まず含イオウ有機廃棄物、例えば含イオウイ
オン交換樹脂1が任意の化学分解法により酸化分
解されて酸化分解液2とされる。 The drawings are process diagrams for explaining the present invention.
In the method of the present invention, for example, as shown in the figure, sulfur-containing organic waste, such as a sulfur-containing ion exchange resin 1, is first oxidized and decomposed by any chemical decomposition method to form an oxidized decomposition liquid 2.
この酸化分解は、前述した金属塩の存在下に過
酸化水素と接触させる方法、あるいは温度200〜
300℃、圧力20〜100気圧の廃棄物を含む水溶液ま
たは廃棄物を含む硫酸銅水溶液において酸素を含
むガスを圧入する方法により行なわれる。 This oxidative decomposition can be carried out by the method of contacting hydrogen peroxide in the presence of the metal salt mentioned above, or by the method of contacting hydrogen peroxide at a temperature of 200 to
This is carried out by pressurizing an oxygen-containing gas into an aqueous solution containing waste or an aqueous copper sulfate solution containing waste at 300°C and a pressure of 20 to 100 atmospheres.
上記金属塩としては、硫酸第一鉄、硫酸第二
鉄、硝酸第一鉄、硝酸第二鉄および硫酸銅から選
ばれた1種または2種以上のものが使用される。
これらの金属塩の濃度は、反応液中金属分として
500〜10000ppm存在する程度が適してる。過酸化
水素水の濃度は、反応系の水溶液中にH2O2換算
で1〜40%程度が好適している。反応は常温でも
進行するが反応を進行させるために加温すること
が望ましい。反応温度は、50℃以上、特に90〜
100℃の範囲が適している。 As the metal salt, one or more selected from ferrous sulfate, ferric sulfate, ferrous nitrate, ferric nitrate, and copper sulfate are used.
The concentration of these metal salts is determined as the metal content in the reaction solution.
A level of 500 to 10,000 ppm is suitable. The concentration of the hydrogen peroxide solution in the aqueous solution of the reaction system is preferably about 1 to 40% in terms of H 2 O 2 . Although the reaction proceeds at room temperature, it is desirable to heat the reaction to proceed. The reaction temperature is 50℃ or higher, especially 90~
A range of 100℃ is suitable.
本発明の対象となる含イオウ有機廃棄物の代表
例としては、原子力発電所で放射性廃液処理に一
般に使用されているカチオンあるいはカチオン、
アニオンの混合イオン交換樹脂、例えばスチレン
とジビニルベンゼンスルホン酸を共重合させた、
合成樹脂内部にスルフオン基あるいはアミノ基を
もつ粉末状あるいは粒状のものがある。 Typical examples of sulfur-containing organic wastes that are the subject of the present invention include cations or cations commonly used in the treatment of radioactive waste liquid at nuclear power plants;
Anionic mixed ion exchange resin, such as copolymerized styrene and divinylbenzenesulfonic acid,
There are powdered or granular synthetic resins that have sulfonic or amino groups inside them.
上記酸化分解反応においては、イオン交換樹脂
中の炭素成分および水素成分が酸化されて主とし
て炭酸ガスおよび水蒸気が発生し、酸化分解液と
して透明な液状生成物が得られる。この酸化分解
反応は乾式焼却法と比較して低温で行なわれるた
め、発生する炭酸ガスおよび水蒸気への放射能の
移行は極めて小さく、従来の廃ガス処理技術によ
り処理することが可能である。なおこの酸化分解
液2中には、例えばスルフオン基等を有する含イ
オウイオン交換樹脂を酸化分解した場合に生ずる
硫酸イオン、金属塩による金属イオンおよび硫酸
イオン等が含まれている。 In the above oxidative decomposition reaction, carbon components and hydrogen components in the ion exchange resin are oxidized to mainly generate carbon dioxide gas and water vapor, and a transparent liquid product is obtained as an oxidative decomposition liquid. Since this oxidative decomposition reaction is carried out at a lower temperature than in the dry incineration method, the transfer of radioactivity to the generated carbon dioxide gas and water vapor is extremely small, and it can be treated using conventional waste gas treatment techniques. Note that this oxidative decomposition liquid 2 contains, for example, sulfate ions generated when a sulfur-containing ion exchange resin having a sulfon group or the like is oxidized and decomposed, metal ions due to metal salts, sulfate ions, and the like.
この酸化分解液2は、次いで還元分解される
が、この還元に先立つて存在する金属イオンを電
解精錬法により除去することが望ましい。この電
解精錬法においては、例えばPtを陽極、Cuまた
はFeを陰極とする電解精錬槽が用いられ、酸化
分解液2中に存在する金属イオンは次の式で示さ
れる反応により陰性上に析出する。 This oxidized decomposition liquid 2 is then reductively decomposed, but it is desirable to remove existing metal ions by electrolytic refining prior to this reduction. In this electrolytic refining method, for example, an electrolytic refining tank with Pt as an anode and Cu or Fe as a cathode is used, and the metal ions present in the oxidized decomposition solution 2 are precipitated on the anode by the reaction shown by the following formula. .
Fe2++2e-−−→Fe
Fe3++3e-−−→Fe
Cu2++2e-−−→Cu
このような反応により、酸化分解液中の金属イ
オンはほぼ100%陰に析出させて回収することが
できる。 Fe 2+ +2e - −−→Fe Fe 3+ +3e - −−→Fe Cu 2+ +2e - −−→Cu Through this reaction, almost 100% of the metal ions in the oxidized decomposition solution are precipitated in the negative and recovered. can do.
このようにして金属イオンを析出させた残りの
電解残渣液は、この後、例えば木炭、イオウのよ
うな還元剤あるいはCuのようなイオン化傾向が
水素より低い金属と接触させながら加熱濃縮する
ことにより硫酸根が二酸化イオウに還元されて除
去され還元分解残渣液3が得られる。 The remaining electrolytic residue solution from which metal ions have been precipitated in this way is then heated and concentrated while being brought into contact with a reducing agent such as charcoal or sulfur, or a metal such as Cu, which has a lower ionization tendency than hydrogen. The sulfate radicals are reduced to sulfur dioxide and removed to obtain a reduced decomposition residue solution 3.
木炭、イオウのような還元剤を用いた場合に
は、硫酸イオンは二酸化イオウとなつてほぼ完全
に、またCuのような金属を用いた場合には理論
上その50%が分解される。 When a reducing agent such as charcoal or sulfur is used, the sulfate ion is almost completely converted to sulfur dioxide, and when a metal such as Cu is used, theoretically 50% of it is decomposed.
すなわち前者の場合には、例えば次の反応によ
り硫酸イオンは二酸化イオウとなり、
2H2SO4 +C −−→
2SO2↑+CO2↑+2H2O↑
後者の場合には液温が130℃以上となると酸化
分解液中の硫酸と銅とが次のように反応し、二酸
化イオウと等モルの硫酸銅が生成される。 In other words, in the former case, the sulfate ion becomes sulfur dioxide through the following reaction, 2H 2 SO 4 +C −-→ 2SO 2 ↑+CO 2 ↑+2H 2 O↑ In the latter case, when the liquid temperature becomes 130°C or higher, The sulfuric acid and copper in the oxidized decomposition liquid react as follows, and copper sulfate is produced in an equimolar amount to sulfur dioxide.
Cu+2H2SO4−−→
CuSO4+SO2↑+2H2O↑
すなわちCuとの反応においては、金属銅1モ
ルから硫酸銅1モルが生成され同時に硫酸イオン
1モルが二酸化イオウとして酸化分解液2から除
去されることになる。したがつて金属銅を用いた
場合でも50%の硫酸イオンを除去することができ
る。 Cu+2H 2 SO 4 −−→ CuSO 4 +SO 2 ↑+2H 2 O↑ In other words, in the reaction with Cu, 1 mol of copper sulfate is produced from 1 mol of metallic copper, and at the same time 1 mol of sulfate ion is released from the oxidative decomposition solution 2 as sulfur dioxide. It will be removed. Therefore, even when metallic copper is used, 50% of sulfate ions can be removed.
この脱硫反応において発生する二酸化イオウに
ついても、前述の樹脂の酸化分解反応に伴う炭酸
ガスや水蒸気と同様に放射能のガスへの移行は極
めて小さく、従来の廃ガス処理技術での処理が可
能である。 Regarding the sulfur dioxide generated in this desulfurization reaction, the transfer to radioactive gas is extremely small, similar to the carbon dioxide gas and water vapor that accompany the oxidative decomposition reaction of the resin mentioned above, and it can be treated using conventional waste gas treatment technology. be.
なお、金属を用いた脱硫反応で残存した還元残
渣液3は、放射性イオン交換樹脂を分解するため
に再使用することができるのでこの反応液を使用
すれば、酸化分解のために新たに金属塩を使用す
る必要はなく、硫酸根をほぼ完全に分解除去する
ことができる。また、もし反応液中の放射能濃度
が許容量を越えるようであれば、必要に応じて再
度金属の析出を行なつた後、あるいはそのまま廃
液4として従来の廃液処理系で処理される。また
は、中和および乾燥処理をした後、得られた粉末
状の乾燥残渣5を、例えばポリエステル樹脂と混
合して固化処理して固化体6とするが、この方法
によれば、発生する固化体の量は、従来のイオン
交換樹脂をそのままセメント固化する場合の1/10
0、乾燥後プラスチツク固化する場合の1/20とす
ることができる。 Note that the reduced residue liquid 3 remaining from the desulfurization reaction using metals can be reused to decompose the radioactive ion exchange resin, so if this reaction liquid is used, new metal salts will be generated for oxidative decomposition. There is no need to use sulfate, and the sulfate radicals can be almost completely decomposed and removed. Furthermore, if the radioactivity concentration in the reaction solution exceeds the allowable amount, the metal may be precipitated again if necessary, or the solution may be treated as waste solution 4 in a conventional waste solution treatment system. Alternatively, after neutralization and drying treatment, the obtained powdered dry residue 5 is mixed with, for example, a polyester resin and solidified to form a solidified body 6. According to this method, the generated solidified body The amount of ion exchange resin is 1/10 that of conventional ion exchange resin solidified into cement.
0, it can be 1/20 of the case where the plastic hardens after drying.
[発明の実施例] 以下、本発明の実施例について説明する。[Embodiments of the invention] Examples of the present invention will be described below.
実施例 1
コンデンサー、攪拌器を備えた4つ頸フラスコ
に乾燥状態の粉末状混合イオン交換樹脂(商品
名:パウデツクス)とこのイオン交換樹脂100部
あたり5000部の水を加えて充分に混合し、次いで
H2O2としての濃度が10%となる量の過酸化水素
水およびFe2(SO4)3としての濃度が0.01モル/
となる量の硫酸第二鉄を加えて100℃に加温し、
この温度で1時間混合攪拌を続けた。反応の進行
につれてガスが発生し、溶液は最初濃濁色に濁つ
てくるが最終的には澄明な液体となる。ここで発
生したガスは、コンデンサで凝縮して凝縮液は反
応器中の反応残渣液に戻し、ガスはそのまま次の
ガス処理工程に導いた。Example 1 In a four-necked flask equipped with a condenser and a stirrer, a dry powdered mixed ion exchange resin (trade name: Powdex) and 5,000 parts of water per 100 parts of this ion exchange resin were added and thoroughly mixed. then
Hydrogen peroxide solution in an amount such that the concentration as H 2 O 2 is 10% and the concentration as Fe 2 (SO 4 ) 3 is 0.01 mol /
Add an amount of ferric sulfate and heat to 100℃,
Mixing and stirring was continued at this temperature for 1 hour. As the reaction progresses, gas is generated, and the solution initially becomes dark and turbid, but eventually becomes a clear liquid. The gas generated here was condensed in a condenser, the condensed liquid was returned to the reaction residue liquid in the reactor, and the gas was directly led to the next gas treatment step.
次に反応残渣液を陽極Pt、陰極をFeとした電
解精錬槽で電解し、電極に液中のFe分をほぼ100
%析出させた。次に電解残渣液に論理量の木炭粉
末をいれて加熱濃縮した。ほぼ130℃で硫酸イオ
ンと木炭との反応により液中から二酸化イオウと
炭酸ガスの発生が認められ180℃で、ほぼ100%の
硫酸イオンの分解したことが認められた。この液
状残留物はPH調整後従来の廃液処理系で処理し、
廃棄可能であり、またPH調整後の液状物を蒸発乾
燥処理してポリエステル樹脂を用いてプラスチツ
ク固化したところ酸化分解しただけで中和、蒸発
乾燥しプラスチツク固化処理した場合と比較して
約1/5に減容することができた。 Next, the reaction residue liquid was electrolyzed in an electrolytic refining tank with a Pt anode and Fe as a cathode, and the Fe content in the liquid was reduced to approximately 100% at the electrodes.
% precipitated. Next, a logical amount of charcoal powder was added to the electrolysis residue solution and concentrated by heating. At approximately 130°C, sulfur dioxide and carbon dioxide gas were generated from the liquid due to the reaction between sulfate ions and charcoal, and at 180°C, almost 100% of the sulfate ions were decomposed. This liquid residue is treated with a conventional waste liquid treatment system after adjusting the pH.
It can be disposed of, and when the liquid material after pH adjustment is evaporated and dried and solidified into plastic using polyester resin, it is only oxidized and decomposed, and the cost is about 1/1 compared to when it is neutralized, evaporated and solidified into plastic. We were able to reduce the volume to 5.
実施例 2
実施例1で使用した4つ頸フラスコに乾燥状態
の粉末状混合イオン交換樹脂(商品名:パウデツ
クス)とこのイオン交換樹脂100部あたり1500部
の、金属銅としての濃度が約6000ppmの硫酸銅水
溶液を入れ、加熱して温度を80〜100℃とした。
次いで攪拌機により攪拌しながら、濃度60%の過
酸化水素水溶液を一定流量で乾燥イオン交換樹脂
1gあたり30ml加えてイオン交換樹脂を酸化し、
ガス状生成物と液状残留物に分解した。上記分解
液の残りを陽極をPt、陰極をCuとした電気精錬
槽で電解しCu電極に液中のCu分をほぼ100%析出
させた。しかる後、電解残渣液を析出した金属銅
と接触させながら加熱濃縮した。ほぼ130℃で硫
酸イオンの分解により液中から二酸化イオウの発
生が認められ、150℃で理論量の50%の硫酸イオ
ンの分解したことが認められた。この液状残留物
はPH調整後従来の廃液処理系で処理し、廃棄可能
であり、またPH調整後の液状物を蒸発乾燥処理し
てポリエステル樹脂を用いてプラスチツク固化し
たところ酸化分解しただけで中和、蒸発乾燥しプ
ラスチツク固化処理した場合と比較して約1/2に
減容することができた。Example 2 Into the four-necked flask used in Example 1, a dry powdered mixed ion exchange resin (trade name: Powdex) and 1500 parts per 100 parts of this ion exchange resin with a concentration of about 6000 ppm as metallic copper were added. A copper sulfate aqueous solution was added and heated to a temperature of 80 to 100°C.
Next, while stirring with a stirrer, a hydrogen peroxide solution with a concentration of 60% was added to the dry ion exchange resin at a constant flow rate.
Add 30ml per 1g to oxidize the ion exchange resin,
Decomposed into gaseous products and liquid residue. The remainder of the decomposed solution was electrolyzed in an electrolytic refining tank with a Pt anode and a Cu cathode, so that almost 100% of the Cu content in the solution was deposited on the Cu electrode. Thereafter, the electrolytic residue solution was heated and concentrated while being brought into contact with the precipitated metallic copper. At approximately 130°C, sulfur dioxide was observed to be generated from the liquid due to decomposition of sulfate ions, and at 150°C, 50% of the theoretical amount of sulfate ions were decomposed. After adjusting the pH, this liquid residue can be treated with a conventional waste liquid treatment system and disposed of.Also, when the liquid after adjusting the pH is evaporated and dried and solidified into plastic using polyester resin, it is only oxidized and decomposed. The volume could be reduced to about 1/2 compared to the case of plastic solidification treatment by evaporation drying.
またこの硫酸イオンを分解した硫酸銅含有残渣
液を過酸化水素水溶液と併用して再度同様の廃イ
オン交換樹脂分解処理を行なつたが、この場合に
も金属塩水溶液と過酸化水素水を使用した場合と
同様の含イオウ有機廃棄物分解能を有することが
認められた。 In addition, the copper sulfate-containing residual solution obtained by decomposing this sulfate ion was used in combination with an aqueous hydrogen peroxide solution to perform the same waste ion exchange resin decomposition treatment again, but in this case, a metal salt aqueous solution and a hydrogen peroxide solution were also used. It was confirmed that the method had the same ability to decompose sulfur-containing organic waste.
[発明の効果]
以上の説明からも明らかなように本発明の方法
によれば、従来法と比較して高い減容性が得られ
る。また発生ガスへの放射能の移行がほとんどな
いので、通常の廃ガス処理で対処することができ
る。[Effects of the Invention] As is clear from the above explanation, according to the method of the present invention, a higher volume reduction property can be obtained compared to the conventional method. Furthermore, since there is almost no transfer of radioactivity to the generated gas, it can be dealt with by normal waste gas treatment.
また含イオウ有機廃棄物に由来する硫酸イオン
が分解されるので、2次廃棄物の量が極めて少な
くなる。 Furthermore, since sulfate ions originating from sulfur-containing organic waste are decomposed, the amount of secondary waste is extremely reduced.
図面は本発明の工程を概略的に示す工程図であ
る。
1……廃イオン交換樹脂、2……酸化分解液、
3……還元残渣液、4……廃液、5……乾燥残
渣、6……固化体。
The drawings are process diagrams schematically showing the steps of the present invention. 1... Waste ion exchange resin, 2... Oxidized decomposition liquid,
3... Reduction residue liquid, 4... Waste liquid, 5... Dry residue, 6... Solidified body.
Claims (1)
素または酸素含有ガスを酸化剤として酸化分解し
て硫酸イオンを含有する分解液を生成する酸化分
解工程と、この分解液を還元剤又は水素よりイオ
ン化傾向の大きい金属の存在下に加熱濃縮し、硫
酸イオンを二酸化イオウに分解して除去する硫酸
イオン除去工程とを有することを特徴とする放射
性含イオウ有機廃棄物分解液の処理方法。 2 酸化分解工程は、放射性含イオウ有機廃棄物
を金属塩水溶液中で過酸化水素と接触させて酸化
分解する特許請求の範囲第1項記載の放射性含イ
オウ有機廃棄物分解液の処理方法。 3 酸化分解工程は、放射性含イオウ有機廃棄物
を含む液中に、加熱加圧下に酸素を含むガスを圧
入して前記放射性含イオウ有機廃棄物を酸化分解
する特許請求の範囲第1項記載の放射性含イオウ
有機廃棄物分解液の処理方法。 4 酸化分解工程は、温度200〜300℃、圧力20〜
100気圧において酸素を含むガスを圧入して放射
性含イオウ有機廃棄物を酸化分解する特許請求の
範囲第3項記載の放射性含イオウ有機廃棄物分解
液の処理方法。 5 金属塩は、硫酸第一鉄、硫酸第二鉄、硝酸第
一鉄、硝酸第二鉄および硫酸銅から選ばれた1種
または2種以上からなる特許請求の範囲第2項記
載の放射性含イオウ有機廃棄物分解液の処理方
法。 6 水溶液中の金属塩の濃度は、金属イオン換算
で、500〜10000ppmである特許請求の範囲第2項
記載の放射性含イオウ有機廃棄物分解液の処理方
法。 7 水溶液中の過酸化水素の濃度は、H2O2換算
で1〜40%である特許請求の範囲第2項記載の放
射性含イオウ有機廃棄物分解液の処理方法。 8 酸化分解工程は、80〜100℃の温度で行われ
る特許請求の範囲第2項記載の放射性含イオウ有
機廃棄物分解液の処理方法。 9 放射性含イオウ有機廃棄物を液中で過酸化水
素または酸素含有ガスを酸化剤として酸化分解し
て硫酸イオンを含有する分解液を生成する酸化分
解工程と、この分解液を還元剤又は水素よりイオ
ン化傾向の大きい金属の存在下に加熱濃縮し、硫
酸イオンを二酸化イオウに分解して除去する硫酸
イオン除去工程と、この硫酸イオン除去工程後の
分解液をPH調整し蒸発乾燥処理する乾燥工程と、
この乾燥処理後の乾燥残渣を固化材と混合して固
化させる固化処理工程とを有することを特徴とす
る放射性含イオウ有機廃棄物分解液の減容固化方
法。 10 酸化分解工程は、放射性含イオウ有機廃棄
物を含む液中に、加熱加圧下に酸素を含むガスを
圧入して前記放射性含イオウ有機廃棄物を酸化分
解する特許請求の範囲第9項記載の放射性含イオ
ウ有機廃棄物分解液の減容固化方法。 11 酸化分解工程は、温度200〜300℃、圧力20
〜100気圧において酸素を含むガスを圧入して放
射性含イオウ有機廃棄物を酸化分解する特許請求
の範囲第10項記載の放射性含イオウ有機廃棄物
分解液の減容固化方法。 12 酸化分解工程は、放射性含イオウ有機廃棄
物を金属塩水溶液中で過酸化水素と接触させて酸
化分解する特許請求の範囲第9項記載の放射性含
イオウ有機廃棄物分解液の減容固化方法。 13 金属塩は、硫酸第一鉄、硫酸第二鉄、硝酸
第一鉄、硝酸第二鉄および硫酸銅から選ばれた1
種または2種以上からなる特許請求の範囲第12
項記載の放射性含イオウ有機廃棄物分解液の減容
固化方法。 14 水溶液中の金属塩の濃度は、金属イオン換
算で、500〜10000ppmである特許請求の範囲第1
2項記載の放射性含イオウ有機廃棄物分解液の減
容固化方法。 15 水溶液中の過酸化水素の濃度は、H2O2換
算で1〜40%である特許請求の範囲第12項記載
の放射性含イオウ有機廃棄物分解液の減容固化方
法。 16 酸化分解工程は、80〜100℃の温度で行わ
れる特許請求の範囲第12項記載の放射性含イオ
ウ有機廃棄物分解液の減容固化方法。[Scope of Claims] 1. An oxidative decomposition step in which radioactive sulfur-containing organic waste is oxidized and decomposed in a liquid using hydrogen peroxide or an oxygen-containing gas as an oxidizing agent to produce a decomposed liquid containing sulfate ions, and this decomposed liquid A radioactive sulfur-containing organic waste decomposition solution comprising a sulfate ion removal step in which sulfate ions are heated and concentrated in the presence of a reducing agent or a metal having a greater ionization tendency than hydrogen, and sulfate ions are decomposed into sulfur dioxide and removed. processing method. 2. The method for treating a radioactive sulfur-containing organic waste decomposition liquid according to claim 1, wherein the oxidative decomposition step involves oxidatively decomposing the radioactive sulfur-containing organic waste by contacting it with hydrogen peroxide in an aqueous metal salt solution. 3. The oxidative decomposition step is the step of oxidatively decomposing the radioactive sulfur-containing organic waste by injecting oxygen-containing gas under heat and pressure into the liquid containing the radioactive sulfur-containing organic waste. A method for treating radioactive sulfur-containing organic waste decomposition liquid. 4 The oxidative decomposition process is performed at a temperature of 200 to 300℃ and a pressure of 20 to 300℃.
4. The method for treating a radioactive sulfur-containing organic waste decomposition solution according to claim 3, wherein the radioactive sulfur-containing organic waste is oxidized and decomposed by injecting oxygen-containing gas under pressure at 100 atmospheres. 5. The metal salt is a radioactive compound as set forth in claim 2, consisting of one or more selected from ferrous sulfate, ferric sulfate, ferrous nitrate, ferric nitrate, and copper sulfate. A method for treating sulfur organic waste decomposition liquid. 6. The method for treating a radioactive sulfur-containing organic waste decomposition solution according to claim 2, wherein the concentration of the metal salt in the aqueous solution is 500 to 10,000 ppm in terms of metal ions. 7. The method for treating a radioactive sulfur-containing organic waste decomposition solution according to claim 2, wherein the concentration of hydrogen peroxide in the aqueous solution is 1 to 40% in terms of H 2 O 2 . 8. The method for treating a radioactive sulfur-containing organic waste decomposition liquid according to claim 2, wherein the oxidative decomposition step is carried out at a temperature of 80 to 100°C. 9 An oxidative decomposition step in which radioactive sulfur-containing organic waste is oxidized and decomposed in a liquid using hydrogen peroxide or an oxygen-containing gas as an oxidizing agent to produce a decomposed liquid containing sulfate ions, and this decomposed liquid is treated with a reducing agent or hydrogen. A sulfate ion removal step in which sulfate ions are decomposed into sulfur dioxide and removed by heating and condensing in the presence of metals with a high ionization tendency, and a drying step in which the decomposition liquid after this sulfate ion removal step is subjected to pH adjustment and evaporation drying. ,
A method for volume reduction and solidification of a radioactive sulfur-containing organic waste decomposition solution, comprising a solidification step of mixing the dry residue after the drying treatment with a solidification material and solidifying it. 10. The oxidative decomposition step is the step of oxidizing and decomposing the radioactive sulfur-containing organic waste by injecting a gas containing oxygen under heat and pressure into the liquid containing the radioactive sulfur-containing organic waste. Volume reduction and solidification method of radioactive sulfur-containing organic waste decomposition liquid. 11 The oxidative decomposition process is performed at a temperature of 200 to 300℃ and a pressure of 20℃.
11. The method for volume reduction and solidification of a radioactive sulfur-containing organic waste decomposition liquid according to claim 10, wherein the radioactive sulfur-containing organic waste is oxidized and decomposed by injecting oxygen-containing gas under pressure at ~100 atmospheres. 12. The method for volume reduction and solidification of a radioactive sulfur-containing organic waste decomposition solution according to claim 9, in which the oxidative decomposition step comprises oxidatively decomposing the radioactive sulfur-containing organic waste by contacting it with hydrogen peroxide in an aqueous metal salt solution. . 13 The metal salt is selected from ferrous sulfate, ferric sulfate, ferrous nitrate, ferric nitrate and copper sulfate.
Claim 12 consisting of a species or two or more species
A method for volume reduction and solidification of a radioactive sulfur-containing organic waste decomposition solution as described in . 14 The concentration of the metal salt in the aqueous solution is 500 to 10,000 ppm in terms of metal ions.
2. The method for volume reduction and solidification of a radioactive sulfur-containing organic waste decomposition solution according to item 2. 15. The method for volume reduction and solidification of a radioactive sulfur-containing organic waste decomposition solution according to claim 12 , wherein the concentration of hydrogen peroxide in the aqueous solution is 1 to 40% in terms of H2O2 . 16. The method for volume reduction and solidification of a radioactive sulfur-containing organic waste decomposition liquid according to claim 12, wherein the oxidative decomposition step is carried out at a temperature of 80 to 100°C.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP5970483A JPS59184899A (en) | 1983-04-05 | 1983-04-05 | Method of treating and volume-decreasing decomposition solution of sulfur-containing radioactive organic waste |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP5970483A JPS59184899A (en) | 1983-04-05 | 1983-04-05 | Method of treating and volume-decreasing decomposition solution of sulfur-containing radioactive organic waste |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS59184899A JPS59184899A (en) | 1984-10-20 |
| JPH0574040B2 true JPH0574040B2 (en) | 1993-10-15 |
Family
ID=13120865
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP5970483A Granted JPS59184899A (en) | 1983-04-05 | 1983-04-05 | Method of treating and volume-decreasing decomposition solution of sulfur-containing radioactive organic waste |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS59184899A (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS61110099A (en) * | 1984-11-02 | 1986-05-28 | 株式会社東芝 | Method of disposing radioactive organic waste |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4851156A (en) * | 1980-09-10 | 1989-07-25 | The United States Of America As Represented By The United States Department Of Energy | Retention of radio-ruthenium in acid processing of nuclear waste |
-
1983
- 1983-04-05 JP JP5970483A patent/JPS59184899A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS59184899A (en) | 1984-10-20 |
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