JPS636498A - Method of processing decontaminated waste liquor - Google Patents
Method of processing decontaminated waste liquorInfo
- Publication number
- JPS636498A JPS636498A JP14821186A JP14821186A JPS636498A JP S636498 A JPS636498 A JP S636498A JP 14821186 A JP14821186 A JP 14821186A JP 14821186 A JP14821186 A JP 14821186A JP S636498 A JPS636498 A JP S636498A
- Authority
- JP
- Japan
- Prior art keywords
- waste liquid
- decontamination
- exchange resin
- radioactivity
- cation exchange
- 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 41
- 238000000034 method Methods 0.000 title claims description 14
- 238000005202 decontamination Methods 0.000 claims description 40
- 230000003588 decontaminative effect Effects 0.000 claims description 36
- 239000007788 liquid Substances 0.000 claims description 32
- 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 25
- 239000003729 cation exchange resin Substances 0.000 claims description 16
- 238000011282 treatment Methods 0.000 claims description 15
- 239000002253 acid Substances 0.000 claims description 8
- 238000007711 solidification Methods 0.000 claims description 7
- 230000008023 solidification Effects 0.000 claims description 7
- 238000011038 discontinuous diafiltration by volume reduction Methods 0.000 claims description 6
- 239000003456 ion exchange resin Substances 0.000 description 14
- 229920003303 ion-exchange polymer Polymers 0.000 description 14
- 239000003795 chemical substances by application Substances 0.000 description 13
- MUBZPKHOEPUJKR-UHFFFAOYSA-N Oxalic acid Chemical compound OC(=O)C(O)=O MUBZPKHOEPUJKR-UHFFFAOYSA-N 0.000 description 3
- 150000001450 anions Chemical class 0.000 description 3
- 150000001768 cations Chemical class 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
- 238000004140 cleaning Methods 0.000 description 3
- 230000002285 radioactive effect Effects 0.000 description 3
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical compound [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 239000012857 radioactive material Substances 0.000 description 2
- 239000002901 radioactive waste Substances 0.000 description 2
- 239000011347 resin Substances 0.000 description 2
- 229920005989 resin Polymers 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 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
- 125000000129 anionic group Chemical group 0.000 description 1
- 239000010426 asphalt Substances 0.000 description 1
- 239000002738 chelating agent Substances 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
- 239000012530 fluid Substances 0.000 description 1
- 238000005342 ion exchange Methods 0.000 description 1
- 150000002500 ions Chemical class 0.000 description 1
- 229910052742 iron Inorganic materials 0.000 description 1
- 230000007774 longterm Effects 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
- 150000007524 organic acids Chemical class 0.000 description 1
- 235000005985 organic acids Nutrition 0.000 description 1
- 150000002894 organic compounds Chemical class 0.000 description 1
- 235000006408 oxalic acid Nutrition 0.000 description 1
- 238000006864 oxidative decomposition reaction Methods 0.000 description 1
- 238000012805 post-processing Methods 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 229910052708 sodium Inorganic materials 0.000 description 1
- 239000011734 sodium Substances 0.000 description 1
- 239000000126 substance 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】
［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。DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Field of Industrial Application) The present invention relates to a method for treating decontamination waste liquid generated in a nuclear facility.
（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。(Prior Art) In nuclear power 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
ためにこれをイオン交換樹脂で処理することができず、
従来は除染廃液をそのまま濃縮、固化などの処理を行な
うしかなかった。Waste liquid from decontaminating equipment, piping, etc. using a decontamination agent, that is, decontamination waste liquid, cannot be treated with ion exchange resin because the concentration of the decontamination agent used is high, at several percent. ,
Previously, decontamination waste liquid could only be processed by concentrating, solidifying, etc.
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のでイオン交換樹脂による処理
が可能となった。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おり、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。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 can be treated with ion exchange resin because the concentration of decontamination agent is low. became. 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 this reason, most of them are currently stored in tanks.
（発明が解決しようとする問題点）
原子力施設において希薄除染法により発生する除染廃液
は、上記したようにイオン交換樹脂で処理することがで
きるが、処理した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てしまう。その上、国内において
は放射性廃棄物の処分方法がいまだ確定していないので
、廃棄物は倉庫等に保管しておかなければならないため
、廃棄物ドラム缶数の減少は重要である。。(Problem to be solved by the invention) Decontamination waste liquid generated by dilute decontamination methods at nuclear facilities can be treated with ion exchange resin as described above, but the treated used ion exchange resin is extremely It contains a lot of radioactivity, and it is problematic to dispose of it immediately after use because it involves high-dose work. Furthermore, when this is packed into drums or the like, it is not possible to pack a large amount due to restrictions on the dose rate on the surface of the drum, and the number of drums inevitably increases. Furthermore, since the disposal method for radioactive waste has not yet been determined in Japan, the waste must be stored in warehouses, etc., so reducing the number of waste drums is important. .
従来、−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
が充分には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 commonly used in nuclear power plants have been stored in storage tanks 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. Its safety has not been fully established, and there are problems with storing it in tanks as in the past.
［発明の構成］
（問題点を解決するための手段）
本発明は、除染廃液を強酸型カチオン交換樹脂で処理し
た後、使用済みの強酸型カチオン交換樹脂を貯蔵タンク
に貯蔵して放射能を減衰させ、一方処理した除染廃液は
放射能減衰処理することなく固化処理することにより、
除染廃液の処理を安全に行なうことができるようにした
ものである。[Structure of the Invention] (Means for Solving the Problems) The present invention involves treating decontamination waste liquid with a strong acid type cation exchange resin, and then storing the used strong acid type cation exchange resin in a storage tank to remove radioactivity. By attenuating the radioactivity while solidifying the treated decontamination waste liquid without subjecting it to radioactivity attenuation treatment,
This allows safe treatment of decontamination waste fluid.
（作 用）
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。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）、キレート剤等でおり、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
イオンでおるか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。(Effect) Most of the radioactivity in decontamination waste liquid is cobalt, manganese, iron,
It exists in the form of cations such as zinc and sodium. The anions in the decontamination waste liquid are organic acids (citric acid, oxalic acid, etc.) as decontamination agent components, chelating agents, etc. Among the anion components, only a few anionic nuclides and cations are radioactive. There are only a few that form complex ions with the decontamination agent components and become anions.
したがって、除染廃液を強酸型カチオン交換樹脂で処理
した場合、廃液中の陽イオンが選択的にこれに捕集され
るので放射能成分の殆どはこのカチオン交換樹脂に取り
込まれることになり、処理後の廃液中にはごくわずかの
放射能しか存在しない。Therefore, when decontamination waste liquid is treated with a strong acid type cation exchange resin, the cations in the waste liquid are selectively captured by this cation exchange resin, and most of the radioactive components are taken into this cation exchange resin. Only a small amount of radioactivity is present in the subsequent waste liquid.
そしてカチオン交換樹脂には除染剤成分が含まれないの
で、原子力発電所の仙の系統から生じた廃イオン交換樹
脂と同様にタンク貯蔵が可能であり、また放射能が多い
のでタンク貯蔵により放射能を減衰させた後処理するの
か適当である。Since cation exchange resin does not contain any decontamination agent components, it can be stored in tanks in the same way as waste ion exchange resin generated from the nuclear power plant system, and since it is highly radioactive, storage in tanks can reduce the amount of radiation released. It is appropriate to perform post-processing to attenuate the performance.
一方処理後の除染廃液はわずかな放射能しか含有してい
ない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
少ないので同化作業が安全であり、また同化前に濃縮、
乾燥、焼却などの減容処理をすることもできる。On the other hand, since the decontamination waste liquid after treatment contains only a small amount of radioactivity, it can be processed as it is, such as cement solidification, and turned into drums in the form of final waste. The assimilation process is safe because the radioactivity is low, and concentration and concentration are necessary before assimilation.
Volume reduction treatments such as drying and incineration can also be performed.
（実施例）
図面に本発明の一実施例の工程図を示す。図面において
、除染対象物１から生じた除染廃液は強酸型カチオン交
換樹脂塔２で処理される。この強酸型カチオン交換樹脂
はＨ型である必要はなく、廃液中の放射性核種と容易に
置換ができ、かつ廃液中に存在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）。カチオン
交換樹脂は洗浄装置３で表面に付着している除染剤を除
去し、放射能の減衰を待つために使用済樹脂貯蔵タンク
４に貯蔵する。−方、処理された後の除染廃液と樹脂の
洗浄液はそのまま減容装置５を経て、セメントとともに
同化装置６において固化し、廃棄物ドラム缶７を作製す
る。(Example) The drawings show a process diagram of an example of the present invention. In the drawing, a decontamination waste liquid generated from an object to be decontaminated 1 is treated in a strong acid type cation exchange resin column 2. This strong acid-type cation exchange resin does not need to be H-type, as long as it can easily replace radionuclides in the waste liquid and does not affect subsequent treatment even if it exists in the waste liquid (for example, Na-type cation exchange resin). ). The cation exchange resin is used to remove the decontamination agent adhering to the surface by a cleaning device 3, and is stored in a used resin storage tank 4 to wait for the radioactivity to decay. - On the other hand, the treated decontamination waste liquid and resin cleaning liquid pass through the volume reduction device 5 as they are, and are solidified together with cement in the assimilation device 6 to produce a waste drum 7.
イオン交換処理後の除染廃液の減容処理は除染剤の性状
に応じて変えられる。例えば除染剤に有機成弁が多い場
合は、酸化分解等の方法も効果的である。また、固化方
法もセメント同化のほかにアスファルト同化、プラスチ
ック固化なども可能で必る。The volume reduction treatment of the decontamination waste liquid after ion exchange treatment can be changed depending on the properties of the decontamination agent. For example, when the decontamination agent contains many organic compounds, methods such as oxidative decomposition are also effective. In addition, as for the solidification method, in addition to cement assimilation, asphalt assimilation and plastic solidification are also possible.
［発明の効果］
本発明では、除染廃液の処理に強酸型カチオン交換樹脂
を使用するので、放射能の殆どはこのカチオン交換樹脂
によって除去され、廃液中にはわずかな放射能しか存在
しない。放射能を吸着したカチオン交換樹脂は貯蔵タン
クに貯えられて放射能を減衰する。一方処理後の廃液は
放射能を僅かしか含んでいないので、減容処理、固化処
理などの作業を安全に行なうことができる。[Effects of the Invention] In the present invention, since a strong acid type cation exchange resin is used to treat decontamination waste liquid, most of the radioactivity is removed by this cation exchange resin, and only a small amount of radioactivity is present in the waste liquid. The cation exchange resin that has adsorbed radioactivity is stored in a storage tank to attenuate the radioactivity. On the other hand, since the waste liquid after treatment contains only a small amount of radioactivity, operations such as volume reduction treatment and solidification treatment can be performed safely.
図面は本発明の一実施例を説明する工程図である。
１・・・・・・・・・除染対象物
２・・・・・・・・・強酸型カチオン交換樹脂塔３・・
・・・・・・・洗浄装置
４・・・・・・・・・廃イオン交換樹脂貯蔵タンク５・
・・・・・・・・減容装置
６・・・・・・・・・固化装置
７・・・・・・・・・廃棄物ドラム缶
Ｃ８７３３）代理人 弁理士 猪 股 祥 晃（ばか
１名）The drawings are process diagrams for explaining one embodiment of the present invention. 1...Object to be decontaminated 2...Strong acid type cation exchange resin tower 3...
......Cleaning device 4...Waste ion exchange resin storage tank 5.
...... Volume reduction device 6 ..... Solidification device 7 ..... Waste drum C8733) Agent Patent attorney Yoshiaki Inomata (baka)
1 person)
Claims (2)
、使用済みの強酸型カチオン交換樹脂を貯蔵タンクに貯
蔵して放射能を減衰させ、一方処理した除染廃液は放射
能減衰処理することなく固化処理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 strong acid type cation exchange resin, the used strong acid type cation exchange resin is stored in a storage tank to attenuate its radioactivity, while the treated decontamination waste liquid is subjected to radioactivity attenuation treatment. A method for treating decontamination waste liquid, which is characterized by solidifying the waste liquid without any solidification.
１項記載の除染廃液の処理方法。(2) A method for treating decontamination waste liquid according to claim 1, which performs volume reduction treatment before solidification treatment.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP14821186A JPS636498A (en) | 1986-06-26 | 1986-06-26 | Method of processing decontaminated waste liquor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP14821186A JPS636498A (en) | 1986-06-26 | 1986-06-26 | Method of processing decontaminated waste liquor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS636498A true JPS636498A (en) | 1988-01-12 |
Family
ID=15447752
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP14821186A Pending JPS636498A (en) | 1986-06-26 | 1986-06-26 | Method of processing decontaminated waste liquor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS636498A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2014032060A (en) * | 2012-08-02 | 2014-02-20 | Nicchu Tohoku Bussan Kk | Decontamination method |
-
1986
- 1986-06-26 JP JP14821186A patent/JPS636498A/en active Pending
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2014032060A (en) * | 2012-08-02 | 2014-02-20 | Nicchu Tohoku Bussan Kk | Decontamination method |
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