JPS63188796A - Method of processing decontaminated waste liquor - Google Patents
Method of processing decontaminated waste liquorInfo
- Publication number
- JPS63188796A JPS63188796A JP2038987A JP2038987A JPS63188796A JP S63188796 A JPS63188796 A JP S63188796A JP 2038987 A JP2038987 A JP 2038987A JP 2038987 A JP2038987 A JP 2038987A JP S63188796 A JPS63188796 A JP S63188796A
- Authority
- JP
- Japan
- Prior art keywords
- decontamination
- waste liquid
- exchange resin
- cation exchange
- waste
- 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
- 239000002699 waste material Substances 0.000 title claims description 39
- 238000000034 method Methods 0.000 title claims description 18
- 238000005202 decontamination Methods 0.000 claims description 42
- 230000003588 decontaminative effect Effects 0.000 claims description 39
- 239000007788 liquid Substances 0.000 claims description 30
- 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 23
- 239000003729 cation exchange resin Substances 0.000 claims description 12
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 10
- 150000007524 organic acids Chemical class 0.000 claims description 7
- MUBZPKHOEPUJKR-UHFFFAOYSA-N Oxalic acid Chemical compound OC(=O)C(O)=O MUBZPKHOEPUJKR-UHFFFAOYSA-N 0.000 claims description 6
- 239000002253 acid Substances 0.000 claims description 5
- 239000007787 solid Substances 0.000 claims description 5
- 235000006408 oxalic acid Nutrition 0.000 claims description 2
- BDAGIHXWWSANSR-UHFFFAOYSA-N methanoic acid Natural products OC=O BDAGIHXWWSANSR-UHFFFAOYSA-N 0.000 claims 2
- OSWFIVFLDKOXQC-UHFFFAOYSA-N 4-(3-methoxyphenyl)aniline Chemical compound COC1=CC=CC(C=2C=CC(N)=CC=2)=C1 OSWFIVFLDKOXQC-UHFFFAOYSA-N 0.000 claims 1
- 235000019253 formic acid Nutrition 0.000 claims 1
- 239000003456 ion exchange resin Substances 0.000 description 19
- 229920003303 ion-exchange polymer Polymers 0.000 description 19
- 239000003795 chemical substances by application Substances 0.000 description 14
- 238000011282 treatment Methods 0.000 description 14
- 238000006864 oxidative decomposition reaction Methods 0.000 description 10
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical compound [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 description 8
- 150000004679 hydroxides Chemical class 0.000 description 8
- CURLTUGMZLYLDI-UHFFFAOYSA-N Carbon dioxide Chemical compound O=C=O CURLTUGMZLYLDI-UHFFFAOYSA-N 0.000 description 6
- 238000000926 separation method Methods 0.000 description 6
- 238000011038 discontinuous diafiltration by volume reduction Methods 0.000 description 5
- 238000010828 elution Methods 0.000 description 5
- 229910052742 iron Inorganic materials 0.000 description 4
- 238000007711 solidification Methods 0.000 description 4
- 230000008023 solidification Effects 0.000 description 4
- 239000001569 carbon dioxide Substances 0.000 description 3
- 229910002092 carbon dioxide Inorganic materials 0.000 description 3
- 239000004568 cement Substances 0.000 description 3
- KRKNYBCHXYNGOX-UHFFFAOYSA-N citric acid Chemical compound OC(=O)CC(O)(C(O)=O)CC(O)=O KRKNYBCHXYNGOX-UHFFFAOYSA-N 0.000 description 3
- 238000000354 decomposition reaction Methods 0.000 description 3
- 238000010586 diagram Methods 0.000 description 3
- 230000007774 longterm Effects 0.000 description 3
- 239000002901 radioactive waste Substances 0.000 description 3
- 238000004062 sedimentation Methods 0.000 description 3
- 125000000129 anionic group Chemical group 0.000 description 2
- 150000001450 anions Chemical class 0.000 description 2
- 150000001768 cations Chemical class 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 239000007800 oxidant agent Substances 0.000 description 2
- 230000003647 oxidation Effects 0.000 description 2
- 238000007254 oxidation reaction Methods 0.000 description 2
- 230000002285 radioactive effect Effects 0.000 description 2
- 239000012857 radioactive material Substances 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 description 1
- HCHKCACWOHOZIP-UHFFFAOYSA-N Zinc Chemical compound [Zn] HCHKCACWOHOZIP-UHFFFAOYSA-N 0.000 description 1
- 239000010426 asphalt Substances 0.000 description 1
- 238000005341 cation exchange Methods 0.000 description 1
- 125000002091 cationic group Chemical group 0.000 description 1
- 238000005119 centrifugation Methods 0.000 description 1
- 239000002738 chelating agent Substances 0.000 description 1
- 238000009390 chemical decontamination Methods 0.000 description 1
- 239000013626 chemical specie Substances 0.000 description 1
- 229910017052 cobalt Inorganic materials 0.000 description 1
- 239000010941 cobalt Substances 0.000 description 1
- GUTLYIVDDKVIGB-UHFFFAOYSA-N cobalt atom Chemical compound [Co] GUTLYIVDDKVIGB-UHFFFAOYSA-N 0.000 description 1
- 238000001035 drying Methods 0.000 description 1
- 238000011049 filling Methods 0.000 description 1
- 238000001914 filtration Methods 0.000 description 1
- 239000012530 fluid Substances 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-M hydroxide Chemical compound [OH-] XLYOFNOQVPJJNP-UHFFFAOYSA-M 0.000 description 1
- 150000002500 ions Chemical class 0.000 description 1
- WPBNNNQJVZRUHP-UHFFFAOYSA-L manganese(2+);methyl n-[[2-(methoxycarbonylcarbamothioylamino)phenyl]carbamothioyl]carbamate;n-[2-(sulfidocarbothioylamino)ethyl]carbamodithioate Chemical compound [Mn+2].[S-]C(=S)NCCNC([S-])=S.COC(=O)NC(=S)NC1=CC=CC=C1NC(=S)NC(=O)OC WPBNNNQJVZRUHP-UHFFFAOYSA-L 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 235000005985 organic acids Nutrition 0.000 description 1
- 238000012856 packing Methods 0.000 description 1
- 230000005258 radioactive decay Effects 0.000 description 1
- 230000008929 regeneration Effects 0.000 description 1
- 238000011069 regeneration method Methods 0.000 description 1
- 239000011347 resin Substances 0.000 description 1
- 229920005989 resin Polymers 0.000 description 1
- 229910052708 sodium Inorganic materials 0.000 description 1
- 239000011734 sodium Substances 0.000 description 1
- 239000011701 zinc Substances 0.000 description 1
- 229910052725 zinc Inorganic materials 0.000 description 1
Landscapes
- Physical Water Treatments (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】
し発明の目的］
（産業上の利用分野）
本発明は原子力施設において生ずる除染廃液の処理方法
に関する。・
（従来の技術）
原子力発電所等の原子力施設では、機器、配管等に放射
性物質が付着し、そこで働く作業員の被曝の問題が生ず
る。したがって放射性物質をこれらの機器、配管等から
除去しなければならない。[Detailed Description of the Invention] [Object of the Invention] (Industrial Application Field) The present invention relates to a method for treating decontamination waste liquid generated in a nuclear facility. - (Conventional technology) At nuclear facilities such as nuclear power plants, radioactive materials adhere to equipment, piping, etc., creating the problem of radiation exposure for workers working there. Therefore, radioactive materials must be removed from these equipment, piping, etc.
この除去手段として除染剤を使用する化学的除去方法が
ある。A chemical removal method using a decontamination agent is available as a means for this removal.
除染剤を使用して機器、配管等を除染処理した廃液、す
なわち除染廃液は、使用する除染剤の濃度が数％と高い
ためにイオン交換樹脂で処理することができず、従来は
そのまま濃縮、固化等の処理を行なっていた。Waste liquid from decontaminating equipment, piping, etc. using decontamination agents, that is, decontamination waste liquid, cannot be treated with ion exchange resins because the concentration of the decontamination agent used is high, at several percent. It was then subjected to processing such as concentration and solidification.
ところが近年、除染剤濃度が低くても効果的な除染が行
なえる希薄除染法が開発され、これにより発生する除染
廃液は除染剤濃度が低いためイオン交換樹脂により処理
することが可能となった。However, in recent years, a dilute decontamination method has been developed that allows effective decontamination even when the concentration of decontamination agent is low, and the decontamination waste liquid generated by this method cannot be treated with ion exchange resin because the concentration of decontamination agent is low. It has become possible.
イオン交換樹脂により処理する方法は、前述した濃厚除
染法に比較して処理廃棄物がコンパクトなイオン交換樹
脂の形であり取り扱い易いこと、除染によって余分な水
が生じないこと、除染廃液を受けるタンク等の追加設備
が不要なこと、廃液処理が容易なことなどの有利な点が
多い。国内においてはまだこの希薄除染法の本格的な適
用はなされていないが、国外においてはこれが主流とな
りつつあり、この廃棄物として生ずるイオン交換樹脂は
そのまま地中処分されている。なお国内では原子炉−次
系の炉水の浄化等にイオン交換樹脂を用いるが、使用済
みイオン交換樹脂は放射能の減衰を待つためと放射性廃
棄物の処分方法が最終的に確定していないことのため、
現在殆どタンク内に保管されている。Compared to the concentrated decontamination method mentioned above, the treatment method using ion-exchange resin has the advantage that the treated waste is in the form of a compact ion-exchange resin and is easier to handle, that no excess water is generated during decontamination, and that the decontamination waste liquid is There are many advantages such as no need for additional equipment such as a tank to receive the liquid, and waste liquid treatment is easy. Although this dilute decontamination method has not yet been fully applied in Japan, it is becoming mainstream overseas, and the ion exchange resin generated as waste is disposed of underground as is. In Japan, ion exchange resins are used to purify reactor water in the reactor system, but used ion exchange resins are used to wait for the radioactivity to decay, and the method for disposing of radioactive waste has not been finalized. For that reason,
Most of it is currently stored in tanks.
（発明が解決しようとする問題点）
上記したように、イオン交換樹脂で除染廃液を処理した
場合、使用済みのイオン交換樹脂は非常に多くの放射能
をその中にもっており、使用後すぐにその処理を行なう
ことは高線量作業となるので問題がある。また、これを
ドラム缶等に詰める場合も、ドラム缶表面の線量率の規
制（２００ｍＲ／Ｈｒ）から多く詰め込むことができず
、必然的にドラム缶本数が増加しゼしよう。その上、国
内においては放射性廃棄物の処分方芦がいまだ確定して
いないので、廃棄物は０庫等に保管しておかなければな
らず、廃棄物ドラム缶数の減少は一層手要な問題となる
。(Problems to be Solved by the Invention) As mentioned above, when decontamination waste liquid is treated with ion exchange resin, the used ion exchange resin contains a large amount of radioactivity, and There is a problem in performing this treatment because it involves high-dose work. Furthermore, when packing this into drums, it is not possible to pack a large amount due to the dose rate regulation on the surface of the drum (200 mR/Hr), and the number of drums will inevitably increase. Furthermore, in Japan, the method of disposing of radioactive waste has not yet been determined, so waste must be stored in storage bins, etc., and reducing the number of waste drums is an even more urgent issue. Become.
従来、一般に原子力発電所で使用されたイオン交換樹脂
は、前記したように放射能を減衰させるため貯蔵タンク
に保管されていた。ところが除染廃液を処理したイオン
交換樹脂の場合は、その他の系統で使用されたイオン交
換樹脂に比べて除染剤成分に由来するいろいろな化学種
を含有しているので、長期のタンク貯蔵に対する安全性
が充分に確証されているとは言えず、従来と同じように
タンク貯蔵することには問題がある。Conventionally, ion exchange resins used in nuclear power plants have been stored in storage tanks in order to attenuate radioactivity as described above. However, in the case of ion-exchange resins made from decontamination waste liquid, they contain a variety of chemical species derived from decontamination agent components compared to ion-exchange resins used in other systems, so they are not suitable for long-term storage in tanks. It cannot be said that its safety has been fully confirmed, and there are problems with storing it in tanks as in the past.
本発明は上記情況に鑑みてなされたもので、化学除染廃
液の取扱いを容易にし、かつ廃棄物固化体量を減少させ
ることのできる除染廃液処理方法をｊ足イ共することを
目的とするものである。The present invention was made in view of the above circumstances, and aims to provide a decontamination waste liquid treatment method that facilitates the handling of chemical decontamination waste liquid and reduces the amount of solidified waste. It is something to do.
［発明の構成］
（問題点を解決するための手段）
本発明は、除染廃液を陽イオン交換樹脂で処理した俊、
該陽イオン交換樹脂を有機酸を用いて溶出処理し、（ｑ
られた溶出液を酸化分解し、酸化分解液から固体酸化物
あるいは水酸化物を分離することを特徴とする除染廃液
の処理方法に関する。[Structure of the Invention] (Means for Solving the Problems) The present invention provides a method for treating decontamination waste liquid with a cation exchange resin.
The cation exchange resin is eluted using an organic acid to obtain (q
The present invention relates to a method for treating decontamination waste liquid, which is characterized by oxidatively decomposing the eluate obtained and separating solid oxides or hydroxides from the oxidatively decomposed liquid.
（作 用）
第１図は本発明の除染廃液処理工程の一例を示す図でお
る。第１図を参照しながら本発明の工程とその作用を説
明する。(Function) FIG. 1 is a diagram showing an example of the decontamination waste liquid treatment process of the present invention. The steps of the present invention and their effects will be explained with reference to FIG.
除染廃液中の放射能の殆どはコバルト、マンガン、鉄、
亜鉛、ナトリウムなどの陽イオンの形態で存在する。一
方、除染廃液中の陰イオンは除染剤成分としての有機酸
（クエン酸、シュウ酸等）。Most of the radioactivity in decontamination waste fluid is cobalt, manganese, iron,
It exists in the form of cations such as zinc and sodium. On the other hand, the anions in the decontamination waste liquid are organic acids (citric acid, oxalic acid, etc.) that are components of the decontamination agent.
キレート剤等であり、陰イオン成分で放射性であるのは
わずかな陰イオン性核種と本来陽イオンであるが除染剤
成分と錯イオンを作って陰イオンとなったものなどごく
わずかである。These are chelating agents, etc., and only a few anionic nuclides are anionic components that are radioactive.Although they are originally cationic, only a small number of them become anions by forming complex ions with decontamination agent components.
この除染廃液をまず陽イオン交換樹脂で処理する。そう
すると、該イオン交換樹脂中に放射性核種の大部分が天
吊の鉄と共に捕集される。次にこのイオン交換樹脂を有
機酸で溶出処理すると、これらが溶出され、この溶出液
を酸化分解すると、これらが酸化物品るいは水酸化物と
なる。このようにイオン交換樹脂で捕集された物質を酸
化物あるいは水酸化物とするのは、これらの放射性核種
等がイオン交換樹脂中に存在するよりも固体の形態で存
在する方が保管上安定でおり、長期の貯蔵に適している
からである。溶出に用いる有機酸は、酸化分解後の廃棄
物を増やさないという観点からキ酸ヤシュウ酸のように
酸化分解され易くかつ酸化分解の結果水と炭酸ガスのみ
になるものが好ましい。This decontamination waste liquid is first treated with a cation exchange resin. Then, most of the radionuclides are collected in the ion exchange resin along with the suspended iron. Next, when this ion exchange resin is subjected to elution treatment with an organic acid, these are eluted, and when this eluate is oxidized and decomposed, these become oxides or hydroxides. The reason why the substances collected by ion exchange resins are oxides or hydroxides is that these radionuclides are more stable for storage when they exist in solid form than in ion exchange resins. This is because it is suitable for long-term storage. The organic acid used for elution is preferably one that is easily oxidized and decomposed to produce only water and carbon dioxide as a result of oxidative decomposition, such as chelic acid and cyanoxalic acid, from the viewpoint of not increasing waste products after oxidative decomposition.
酸化分解した溶出液は水中に酸化物あるいは水酸化物が
混合している状態となっているが、沈降分離等の分離処
理を行なってこれらを分離する。The oxidatively decomposed eluate contains oxides or hydroxides mixed in water, but these are separated by performing a separation process such as sedimentation.
分離した酸化物あるいは水酸化物は放射能減衰のために
保管される。酸化物あるいは水酸化物を分離除去した後
の清澄水は再使用ことができる。The separated oxide or hydroxide is stored for radioactive decay. Clear water after separating and removing oxides or hydroxides can be reused.
一方、陽イオン交換樹脂を通して陽イオン成分を除去し
た後の除染廃液処理液は、わずかな放射能と除染剤成分
を含有するだけであるので、そのままセメント固化など
の処理を行なって最終廃棄物形態のドラム缶にすること
ができる。放射能が少ないので固化作業が安全でおり、
また同化前に濃縮、屹燥、焼却などの減容処理をするこ
ともできる。表面線量率が低いので充填量の制限も問題
にならない。On the other hand, the decontamination waste solution after removing cation components through a cation exchange resin contains only a small amount of radioactivity and decontamination agent components, so it can be treated as it is by cement solidification, etc., and then finally disposed of. It can be made into a physical drum. Solidification work is safe because it has little radioactivity.
It is also possible to perform volume reduction treatments such as concentration, drying, and incineration before assimilation. Since the surface dose rate is low, limiting the amount of filling is not a problem.
なお、本発明において除染廃液中の放射能を一旦イオン
交換樹脂に捕集した後に溶出して酸化分解するのは、次
の理由からである。The reason why, in the present invention, the radioactivity in the decontamination waste liquid is once captured in an ion exchange resin and then eluted and oxidized and decomposed is as follows.
（１）除染剤の成分の中には酸化分解が起こりにくいも
のもある。また、分解後に水および炭酸ガス以外の生成
物ができると、その後の水処理に影響が出る場合もある
。イオン交換樹脂処理することによって、これらの成分
を酸化分解の対象から外すことができる。(1) Some components of decontamination agents are difficult to cause oxidative decomposition. Furthermore, if products other than water and carbon dioxide are produced after decomposition, subsequent water treatment may be affected. By treating with an ion exchange resin, these components can be removed from the target of oxidative decomposition.
（２）除染剤の全量に較べて溶出液の母は少ないので、
溶出液を酸化分解すれば酸化分解が小規模ですむ。酸化
分解は現状原子力施設における通常の処理系統として組
まれていないので、酸化分解を行なうには小規模である
必要がおる。(2) Since the amount of eluate is small compared to the total amount of decontamination agent,
If the eluate is subjected to oxidative decomposition, the oxidative decomposition can be done on a small scale. At present, oxidative decomposition is not included as a normal treatment system in nuclear facilities, so it is necessary to carry out oxidative decomposition on a small scale.
（実施例） 本発明の実施例を第２図を参照して説明する。(Example) An embodiment of the present invention will be described with reference to FIG.
第２図は本発明の一実施例を示す概略系統図である。第
２図において、１は除染対象物（機器。FIG. 2 is a schematic system diagram showing one embodiment of the present invention. In Figure 2, 1 is the object to be decontaminated (equipment).
配管等）でおり、除染対象物１を除染した除染廃液は強
酸型陽イオン交換樹脂塔２で処理される。The decontamination waste liquid that has decontaminated the object 1 to be decontaminated is treated in a strong acid type cation exchange resin column 2.
ここで陽イオン交換樹脂はＨ型である必要はなく、廃液
中の放射性核種と容易に置換でき、かつ廃液□中に放出
してもその後の処理に影響しないものであればよい（例
えばＮａ型）。イオン交換処理された１娶、除染廃液は
そのまま減容装置３で減容処理され、次に同化装置４に
おいてセメントとともに固化されて廃棄物ドラム缶５と
なる。Here, the cation exchange resin does not need to be H-type; it may be one that can easily replace radionuclides in the waste liquid and does not affect subsequent treatment even if released into the waste liquid (for example, Na-type ). The ion-exchanged decontamination waste liquid is subjected to a volume reduction treatment in a volume reduction device 3 as it is, and then solidified together with cement in an assimilation device 4 to become a waste drum 5.
一方、陽イオン交換樹脂は溶出（再生）装置６において
有機酸で溶出処理され、樹脂中に付着している鉄おＪζ
び放射性核種を溶出する。溶出液は酸化分解装置７で酸
化分解され、その結果有は酸は水と炭酸ガスに分解し、
鉄と放射性核種はそれぞれ酸化物あるいは水酸化物に変
化する。これらの固形物は沈降分離槽８において分離さ
れた後保管され、一方固形物分離後の清ｉｆｆ水は廃棄
物９８理系統において処理された後、再使用される。な
お、溶出装置６には溶出液タンク９が接続されており、
酸化分解槽７には酸化剤タンク１０が接続されている。On the other hand, the cation exchange resin is eluted with an organic acid in the elution (regeneration) device 6, and the iron adhering to the resin is removed.
and elute radionuclides. The eluate is oxidized and decomposed in the oxidative decomposition device 7, and as a result, the acid is decomposed into water and carbon dioxide gas.
Iron and radionuclides transform into oxides or hydroxides, respectively. These solids are separated in the settling tank 8 and then stored, while the clear water after the solids separation is treated in the waste 98 system and then reused. Note that an eluate tank 9 is connected to the elution device 6.
An oxidizer tank 10 is connected to the oxidation decomposition tank 7.
上記実施例においては酸化物あるいは水酸化物の分離は
沈降分離法によって行なったが、濾過分離、遠心分離な
どによって行なってもよい。また、イオン交換樹脂で処
理した俊の除染廃液の減容処理は、除染剤の性状に応じ
て種々の方法を採用することができ、例えば除染剤が有
機成分が多く、酸化分解されやすいものである場合は酸
化分解の方法も効果的である。ざらに同化方法も、上記
実施例で示したセメント固化の他にアスファルト同化、
プラスチック固化等が可能である。In the above examples, separation of oxides or hydroxides was carried out by a sedimentation separation method, but separation by filtration, centrifugation, etc. may also be used. In addition, various methods can be used to reduce the volume of Shun's decontamination waste liquid treated with ion exchange resin depending on the properties of the decontamination agent. If the material is easy to decompose, oxidative decomposition is also effective. In addition to the cement solidification shown in the above example, the assimilation method also includes asphalt assimilation,
It is possible to solidify plastic.
［発明の効果］
本発明の除染廃液処理方法は、放射能の高い成分を陽イ
オン交換樹脂に捕集したのち、これを溶出して酸化物あ
るいは水酸化物に変化させ、この形態で保管処理するの
で、放射性廃棄物の各組を著しく減少させることができ
る上、長期保管に適した廃棄物とすることができる。一
方、人里の除染剤成分は放射能を除去された後減容およ
び同化処理に付されるので、これらの作業を安全に行う
ことができる。[Effects of the invention] The decontamination waste liquid treatment method of the present invention collects highly radioactive components in a cation exchange resin, elutes the components, converts them into oxides or hydroxides, and stores them in this form. By processing, each set of radioactive waste can be significantly reduced and the waste can be made suitable for long-term storage. On the other hand, since the decontamination agent components in human areas are subjected to volume reduction and assimilation treatment after radioactivity has been removed, these operations can be carried out safely.
第１図は本発明の除染発液処理工程の一例を示す流れ図
、第２図は本発明の実施例を示す概略系統図である。
１・・・・・・除染対象物、２・・・・・・陽イオン交
換塔３・・・・・・減容装置、 ４・・・・・・同化装
置５・・・・・・廃棄物ドラム缶
６・・・・・・溶出塔、 ７・・・・・・酸化分解
槽８・・・・・・沈降分離槽
９・・・・・・溶出液タンク
１０・・・・・・酸化剤タンク
（８７３３）代理人 弁理士 猪 股 祥 晃（ほか
１名）
１＝ｉ イ更“丁ロ イ芽、勾ｆ
第１図FIG. 1 is a flow chart showing an example of the decontamination liquid treatment process of the present invention, and FIG. 2 is a schematic system diagram showing an embodiment of the present invention. 1...Object to be decontaminated, 2...Cation exchange tower 3...Volume reduction device, 4...Assimilation device 5... Waste drum 6... Elution tower, 7... Oxidation decomposition tank 8... Sedimentation separation tank 9... Eluate tank 10... Oxidizer tank (8733) Agent: Yoshiaki Inomata, patent attorney (and others)
1 person) 1 = i
Figure 1
Claims (3)
イオン交換樹脂を有機酸を用いて溶出処理し、得られた
溶出液を酸化分解し、酸化分解液から固体酸化物あるい
は水酸化物を分離することを特徴とする除染廃液の処理
方法。(1) After treating the decontamination waste liquid with a cation exchange resin, the cation exchange resin is eluted using an organic acid, the obtained eluate is oxidized and decomposed, and solid oxides or water are extracted from the oxidized decomposed liquid. A method for treating decontamination waste liquid characterized by separating oxides.
囲第１項記載の除染廃液の処理方法。(2) The method for treating decontamination waste liquid according to claim 1, wherein the organic acid is oxalic acid or formic acid.
る特許請求の範囲第１項記載の除染廃液の処理方法。(3) The method for treating decontamination waste liquid according to claim 1, wherein the cation exchange resin is a strong acid type cation exchange resin.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2038987A JPS63188796A (en) | 1987-02-02 | 1987-02-02 | Method of processing decontaminated waste liquor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2038987A JPS63188796A (en) | 1987-02-02 | 1987-02-02 | Method of processing decontaminated waste liquor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS63188796A true JPS63188796A (en) | 1988-08-04 |
Family
ID=12025664
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP2038987A Pending JPS63188796A (en) | 1987-02-02 | 1987-02-02 | Method of processing decontaminated waste liquor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS63188796A (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP2819125A1 (en) | 2013-06-21 | 2014-12-31 | Hitachi-GE Nuclear Energy, Ltd. | Radioactive organic waste treatment method and system |
| JP2016001115A (en) * | 2014-06-11 | 2016-01-07 | 日立Ｇｅニュークリア・エナジー株式会社 | Organic-based radioactive waste treatment system and organic-based radioactive waste treatment method |
| JP2016090522A (en) * | 2014-11-11 | 2016-05-23 | 日立Ｇｅニュークリア・エナジー株式会社 | Chemical decontamination secondary waste reduction method, secondary waste elution and recovery apparatus and chemical decontamination system |
| WO2022135731A1 (en) * | 2020-12-24 | 2022-06-30 | Framatome Gmbh | Mineralization of organic compounds with boron-doped-diamond electrode during radionuclides stripping process |
-
1987
- 1987-02-02 JP JP2038987A patent/JPS63188796A/en active Pending
Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP2819125A1 (en) | 2013-06-21 | 2014-12-31 | Hitachi-GE Nuclear Energy, Ltd. | Radioactive organic waste treatment method and system |
| JP2015064334A (en) * | 2013-06-21 | 2015-04-09 | 日立Ｇｅニュークリア・エナジー株式会社 | Radioactive organic waste treatment method and radioactive organic waste treatment system |
| US9336913B2 (en) | 2013-06-21 | 2016-05-10 | Hitachi-Ge Nuclear Energy, Ltd. | Radioactive organic waste treatment method |
| JP2016001115A (en) * | 2014-06-11 | 2016-01-07 | 日立Ｇｅニュークリア・エナジー株式会社 | Organic-based radioactive waste treatment system and organic-based radioactive waste treatment method |
| JP2016090522A (en) * | 2014-11-11 | 2016-05-23 | 日立Ｇｅニュークリア・エナジー株式会社 | Chemical decontamination secondary waste reduction method, secondary waste elution and recovery apparatus and chemical decontamination system |
| WO2022135731A1 (en) * | 2020-12-24 | 2022-06-30 | Framatome Gmbh | Mineralization of organic compounds with boron-doped-diamond electrode during radionuclides stripping process |
| CN116635335A (en) * | 2020-12-24 | 2023-08-22 | 法玛通股份有限公司 | Mineralizing organic compounds with boron doped diamond electrodes during radionuclide stripping |
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