JP3078076B2 - Treatment of radioactive liquid waste - Google Patents
Treatment of radioactive liquid wasteInfo
- Publication number
- JP3078076B2 JP3078076B2 JP03350136A JP35013691A JP3078076B2 JP 3078076 B2 JP3078076 B2 JP 3078076B2 JP 03350136 A JP03350136 A JP 03350136A JP 35013691 A JP35013691 A JP 35013691A JP 3078076 B2 JP3078076 B2 JP 3078076B2
- Authority
- JP
- Japan
- Prior art keywords
- activated carbon
- waste liquid
- adsorption
- fibrous activated
- treatment
- 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 - Lifetime
Links
- 230000002285 radioactive effect Effects 0.000 title claims description 4
- 239000010808 liquid waste Substances 0.000 title description 2
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 claims description 38
- 239000007788 liquid Substances 0.000 claims description 24
- 238000000034 method Methods 0.000 claims description 19
- 239000002901 radioactive waste Substances 0.000 claims description 12
- 238000001179 sorption measurement Methods 0.000 description 18
- 229910052770 Uranium Inorganic materials 0.000 description 11
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 11
- 239000003463 adsorbent Substances 0.000 description 10
- 239000002699 waste material Substances 0.000 description 9
- 229910052778 Plutonium Inorganic materials 0.000 description 7
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 description 7
- 230000005855 radiation Effects 0.000 description 7
- 239000013522 chelant Substances 0.000 description 3
- 125000000524 functional group Chemical group 0.000 description 3
- 239000011347 resin Substances 0.000 description 3
- 229920005989 resin Polymers 0.000 description 3
- 229920002972 Acrylic fiber Polymers 0.000 description 2
- ISWSIDIOOBJBQZ-UHFFFAOYSA-N Phenol Chemical compound OC1=CC=CC=C1 ISWSIDIOOBJBQZ-UHFFFAOYSA-N 0.000 description 2
- 239000011230 binding agent Substances 0.000 description 2
- 239000011300 coal pitch Substances 0.000 description 2
- 239000000835 fiber Substances 0.000 description 2
- 239000003456 ion exchange resin Substances 0.000 description 2
- 229920003303 ion-exchange polymer Polymers 0.000 description 2
- 238000000465 moulding Methods 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- MGRVRXRGTBOSHW-UHFFFAOYSA-N (aminomethyl)phosphonic acid Chemical compound NCP(O)(O)=O MGRVRXRGTBOSHW-UHFFFAOYSA-N 0.000 description 1
- 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 description 1
- 229920000297 Rayon Polymers 0.000 description 1
- 229910052792 caesium Inorganic materials 0.000 description 1
- TVFDJXOCXUVLDH-UHFFFAOYSA-N caesium atom Chemical compound [Cs] TVFDJXOCXUVLDH-UHFFFAOYSA-N 0.000 description 1
- 230000000052 comparative effect Effects 0.000 description 1
- 239000011521 glass Substances 0.000 description 1
- UETZVSHORCDDTH-UHFFFAOYSA-N iron(2+);hexacyanide Chemical compound [Fe+2].N#[C-].N#[C-].N#[C-].N#[C-].N#[C-].N#[C-] UETZVSHORCDDTH-UHFFFAOYSA-N 0.000 description 1
- 239000011159 matrix material Substances 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 150000002739 metals Chemical class 0.000 description 1
- 229920000620 organic polymer Polymers 0.000 description 1
- 239000000941 radioactive substance Substances 0.000 description 1
- 239000002964 rayon Substances 0.000 description 1
- 238000012958 reprocessing Methods 0.000 description 1
- 239000002915 spent fuel radioactive waste Substances 0.000 description 1
- 239000002351 wastewater Substances 0.000 description 1
- 238000004804 winding Methods 0.000 description 1
Landscapes
- Solid-Sorbent Or Filter-Aiding Compositions (AREA)
Description
【０００１】[0001]
【産業上の利用分野】本発明は、放射性核種を吸着して
分離除去するのに有用な放射性廃液の処理方法に関する
ものである。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a method for treating radioactive waste liquid which is useful for adsorbing and separating and removing radionuclides.
【０００２】[0002]
【従来の技術】原子力発電所で発生する使用済み核燃料
を再処理する施設の各種廃液の中には、セシウム等の長
寿命β、γ核種、ウラン、プルトニウム等の放射性核種
（以下、ＴＲＵ核種という。）が含まれている。これら
の放射性廃液の処理においては、被曝を低減するために
廃液中の放射性核種を分離除去し、放射線レベルを低減
することが必要である。2. Description of the Related Art Various kinds of wastewater from facilities for reprocessing spent nuclear fuel generated at nuclear power plants include long-lived β and γ nuclides such as cesium, radionuclides such as uranium and plutonium (hereinafter referred to as TRU nuclides). .)It is included. In the treatment of these radioactive waste liquids, it is necessary to separate and remove radioactive nuclides in the waste liquid in order to reduce exposure, and to reduce the radiation level.
【０００３】従来、一般廃液中の金属の除去には、イオ
ン交換樹脂やキレート樹脂が使用されている。しかし、
放射性廃液の場合、有機高分子からなるイオン交換樹脂
やキレート樹脂は放射線による化学的作用により劣化し
やすく使用できないという問題がある。また、たとえ使
用できてもその選択性に問題があり、例えば多量のウラ
ン廃液中に含まれる、微量のプルトニウム等のＴＲＵ核
種を選択的に確実に分離除去できる吸着材あるいは処理
方法がないのが現状である。Conventionally, ion-exchange resins and chelate resins have been used to remove metals from general waste liquids. But,
In the case of a radioactive waste liquid, there is a problem that an ion exchange resin or a chelate resin composed of an organic polymer easily deteriorates due to a chemical action by radiation and cannot be used. Further, even if it can be used, there is a problem in its selectivity. For example, there is no adsorbent or treatment method capable of selectively separating and removing a small amount of TRU nuclides such as plutonium contained in a large amount of uranium waste liquid. It is the current situation.
【０００４】放射線に対する耐久性のある吸着材として
は無機系の吸着材が考えられるが、吸着性の優れたもの
は得られていないのが現状である。一方、有機物の母体
に無機系官能基を担持させた吸着材として、特開昭61−
4530号公報には、アクリル繊維にフェロシアン酸塩を担
持させた吸着剤が提案されている。しかし、この官能基
はＴＲＵ核種の選択的吸着性がなく、さらに母体が有機
物のため耐久性に問題があった。[0004] Inorganic adsorbents can be considered as adsorbents that are durable to radiation, but no adsorbents having excellent adsorbability have been obtained at present. On the other hand, as an adsorbent obtained by supporting an inorganic functional group on an organic matrix, JP-A-61-1986
No. 4530 proposes an adsorbent in which a ferrocyanate is supported on an acrylic fiber. However, this functional group has no selective adsorption of TRU nuclides, and has a problem in durability because the base is an organic substance.
【０００５】また、特公昭60-51491号公報には、アミノ
メチルホスホン酸系の官能基を有するフェノール系キレ
ート樹脂が提案され、ウランの吸着に優れることが記載
されているが、この樹脂は多量のウラン中のプルトニウ
ムを選択的に吸着する能力がなかった。Japanese Patent Publication No. 60-51491 proposes a phenol-based chelate resin having an aminomethylphosphonic acid-based functional group, and describes that it is excellent in uranium adsorption. There was no ability to selectively adsorb plutonium in uranium.
【０００６】[0006]
【発明が解決しようとする課題】上記のように、従来の
吸着材は、いずれも放射線に対して耐久性に問題があ
り、放射性廃液中のＴＲＵ核種を選択的に吸着できない
という問題があった。本発明は、放射線に対して耐久性
のある吸着材を用いて、ＴＲＵ核種を選択的に吸着可能
な放射性廃液の処理方法を提供することを技術的な課題
とするものである。As described above, all of the conventional adsorbents have a problem in durability against radiation, and have a problem that TRU nuclides in radioactive waste liquid cannot be selectively adsorbed. . An object of the present invention is to provide a method for treating a radioactive liquid waste capable of selectively adsorbing TRU nuclides using an adsorbent that is durable to radiation.
【０００７】[0007]
【課題を解決するための手段】本発明者らは、このよう
な課題を解決するために鋭意検討の結果、無機系の骨格
を持つ繊維状活性炭は放射線に対する耐久性に優れ、し
かもウラン廃液中に含まれる微量のプルトニウム等のＴ
ＲＵ核種を選択的に、かつ確実に分離除去できることを
見い出して本発明に到達した。Means for Solving the Problems The present inventors have made intensive studies to solve such problems, and as a result, a fibrous activated carbon having an inorganic skeleton has excellent durability against radiation, and furthermore, has a high uranium concentration. Of trace amounts of plutonium etc. contained in
The present invention has been found that RU nuclides can be selectively and reliably separated and removed.
【０００８】すなわち、本発明は、放射性廃液中に含ま
れるＴＲＵ核種を分離除去するに際し、比表面積が 600
ｍ2/ｇ以上の繊維状活性炭で処理することを特徴とする
放射性廃液の処理方法を要旨とするものである。That is, according to the present invention, when separating and removing TRU nuclides contained in a radioactive waste liquid, the specific surface area is 600
The gist of the present invention is a method for treating a radioactive waste liquid, wherein the method comprises treating with a fibrous activated carbon of m 2 / g or more.
【０００９】以下、本発明について詳細に説明する。Hereinafter, the present invention will be described in detail.
【００１０】本発明は、繊維状活性炭を用いて放射性廃
液を処理するものである。本発明者らは、ウラン廃液中
の微量のＴＲＵ核種が、繊維状活性炭の処理により驚く
べきことに粒状の活性炭に比較して非常に良好に吸着さ
れることを見い出した。その理由は明確ではないが、繊
維状活性炭は粒状活性炭に比べて繊維径が細く、吸着速
度が著しく速いことに起因するのではないかと推定され
る。ここで使用される繊維状活性炭は、石炭ピッチ、レ
ーヨン、フェノール繊維、アクリル繊維等から得られる
ものであればいずれでもよいが、石炭ピッチ系の繊維状
活性炭が好ましい。According to the present invention, a radioactive waste liquid is treated using fibrous activated carbon. The present inventors have found that trace amounts of TRU nuclides in uranium waste liquor are surprisingly better adsorbed by treatment of fibrous activated carbon compared to granular activated carbon. Although the reason is not clear, it is presumed that the fibrous activated carbon has a smaller fiber diameter than the granular activated carbon and has an extremely high adsorption speed. The fibrous activated carbon used here may be any of those obtained from coal pitch, rayon, phenol fiber, acrylic fiber, etc., but coal pitch based fibrous activated carbon is preferred.
【００１１】上記で使用する繊維状活性炭の比表面積は
600ｍ2/ｇ以上であることが必要であり、比表面積は大
きいほど吸着量が大となり、しかも選択吸着性が向上す
るので、特に1500〜2500ｍ2/ｇのものが好ましい。比表
面積が 600ｍ2/ｇ未満になると、吸着量が少なく、選択
吸着性も低下する。The specific surface area of the fibrous activated carbon used above is
It is necessary to be at least 600 m 2 / g, and the larger the specific surface area, the larger the adsorption amount and the better the selective adsorption property. Therefore, those having a specific surface area of 1500 to 2500 m 2 / g are particularly preferable. When the specific surface area is less than 600 m 2 / g, the amount of adsorption is small and the selective adsorbability is also lowered.
【００１２】本発明において、放射性廃液を処理する際
の具体的手段は、従来のいずれの手段を採用してもよ
い。例えば、吸着槽によるバッチ法、吸着塔によるカラ
ム通液法あるいはそれらの併用したもの等を利用するこ
とができるが、一般にはカラム通液法やカートリッジ通
液法が好ましい。また、繊維状活性炭をシートやカート
リッジ等に成形し、それを利用した通液方法を採用して
もよい。In the present invention, as a specific means for treating the radioactive waste liquid, any conventional means may be employed. For example, a batch method using an adsorption tank, a column flow method using an adsorption tower, or a combination thereof can be used. Generally, a column flow method or a cartridge flow method is preferable. Alternatively, a fibrous activated carbon may be formed into a sheet, a cartridge, or the like, and a liquid passing method using the same may be employed.
【００１３】カラム通液法においては、吸着塔に繊維状
活性炭を充填して放射性廃液を通液するが、繊維状活性
炭の充填層の厚みは 200mm以上で, 特に 500〜2000mmと
することが好ましい。充填層の厚さが200mm 未満では、
リークによる漏れが生じやすくて好ましくない。通液速
度は液の性状により異なるが、ＳＶ（空間速度）0.５hr
-1以上で, 特に１〜10hr-1とすることが好ましい。In the column flow method, fibrous activated carbon is filled in an adsorption tower and radioactive waste liquid is passed therethrough. The packed layer of fibrous activated carbon has a thickness of 200 mm or more, preferably 500 to 2000 mm. . If the thickness of the packed bed is less than 200 mm,
It is not preferable because the leakage easily occurs. The liquid passing speed varies depending on the properties of the liquid, but the SV (space velocity) is 0.5 hr.
-1 or more, particularly preferably 1 to 10 hr -1 .
【００１４】カートリッジ通液法は、円筒状あるいは円
柱状に成形したカートリッジをハウジングケースにセッ
トし、通液する方法である。カートリッジの場合、装
着、脱着の取扱いが容易となり、使用済みカートリッジ
の廃棄処理も簡単で、特に放射性物質を扱う場合には非
常に有効である。カートリッジの成形方法は、例えば、
繊維状活性炭を湿式成形する方法、抄紙法あるいは乾式
法で繊維状活性炭シートを成形し、それを巻き固めてカ
ートリッジとする方法等がある。カートリッジに成形す
る場合は、若干量の無機バインダーや有機バインダーを
配合することもできる。The cartridge passage method is a method in which a cartridge formed into a cylindrical shape or a column shape is set in a housing case and liquid is passed. In the case of a cartridge, the handling of mounting and demounting becomes easy, and the disposal of used cartridges is easy, and it is very effective especially when handling radioactive substances. The molding method of the cartridge is, for example,
There are a method of wet-forming fibrous activated carbon, a method of forming a fibrous activated carbon sheet by a papermaking method or a dry method, and winding it into a cartridge to form a cartridge. When molding into a cartridge, a small amount of an inorganic binder or an organic binder may be blended.
【００１５】[0015]
【作用】本発明においては、吸着材として、優れた選択
吸着性と耐久性を有する繊維状活性炭を使用することに
より、放射性核種を含有する廃液、特にウラン廃液中か
らプルトニウムなどのＴＲＵ核種を選択的に吸着処理す
ることが可能となり、従来困難であった放射性廃液を容
易に処理することができる。According to the present invention, a TRU nuclide such as plutonium is selected from a waste liquid containing a radionuclide, particularly a uranium waste liquid, by using fibrous activated carbon having excellent selective adsorption and durability as an adsorbent. Thus, the radioactive waste liquid, which has been conventionally difficult, can be easily treated.
【００１６】[0016]
【実施例】次に、本発明を実施例により具体的に説明す
る。Next, the present invention will be described in detail with reference to examples.
【００１７】実施例１ 繊維状活性炭（ユニチカ社製Ａ−20：比表面積2116ｍ2/
ｇ) を、内径14.8mm、高さ 500mmのガラス製カラムに9.
０ｇ充填した。このときの充填層の高さは 400mmであっ
た。Example 1 Fibrous activated carbon (A-20 manufactured by Unitika Ltd .: specific surface area: 2116 m 2 /
g) into a glass column with an inner diameter of 14.8 mm and a height of 500 mm.
0 g was charged. The height of the packed bed at this time was 400 mm.
【００１８】このカラムに、ウラン濃度0.26mg／ml、プ
ルトニウム濃度3.９×10-5mg／mlのウラン廃液を、流通
速度176ml/hrで 400mlの通液処理を行った。その結果、
Ｐｕの吸着量1.０×10-2mg、その吸着率64％、Ｕの吸着
量46mg、その吸着率44％であった。A uranium waste liquid having a uranium concentration of 0.26 mg / ml and a plutonium concentration of 3.9 × 10 −5 mg / ml was passed through the column at a flow rate of 176 ml / hr for 400 ml. as a result,
The adsorption amount of Pu was 1.0 × 10 −2 mg, the adsorption rate was 64%, the adsorption amount of U was 46 mg, and the adsorption rate was 44%.
【００１９】比較例１ 比表面積 545ｍ2/ｇの繊維状活性炭9.０ｇを実施例１と
同様にカラムに充填し、ウラン廃液の通液処理を行っ
た。その結果、Ｐｕの吸着量2.５×10-3mg、その吸着率
16％、Ｕの吸着量16mg、その吸着率15％といずれも低い
ものであった。Comparative Example 1 9.0 g of a fibrous activated carbon having a specific surface area of 545 m 2 / g was packed in a column in the same manner as in Example 1, and uranium waste liquid was passed through the column. As a result, the adsorption amount of Pu was 2.5 × 10 -3 mg, and the adsorption rate
16%, the amount of adsorption of U was 16 mg, and the adsorption rate was 15%, all of which were low.
【００２０】[0020]
【発明の効果】本発明によれば、放射線に対して耐久性
のある吸着材を用いて、例えば多量のウラン廃液中に含
まれる、微量のプルトニウム等のＴＲＵ核種を選択的に
確実に分離除去することが可能となる。According to the present invention, a small amount of TRU nuclides such as plutonium contained in, for example, a large amount of uranium waste liquid can be selectively and reliably separated and removed using an adsorbent that is resistant to radiation. It is possible to do.
───────────────────────────────────────────────────── フロントページの続き (56)参考文献 特開 平５−168917（ＪＰ，Ａ) 特開 平５−157896（ＪＰ，Ａ) 特開 昭60−214299（ＪＰ，Ａ) 特開 昭57−162642（ＪＰ，Ａ) 特開 昭57−40693（ＪＰ，Ａ) 特開 昭53−5399（ＪＰ，Ａ) (58)調査した分野(Int.Cl.7，ＤＢ名) G21F 9/12 G21F 9/06 ────────────────────────────────────────────────── ─── Continuation of the front page (56) References JP-A-5-168917 (JP, A) JP-A-5-157896 (JP, A) JP-A-60-214299 (JP, A) JP-A-57- 162642 (JP, A) JP-A-57-40693 (JP, A) JP-A-53-5399 (JP, A) (58) Fields investigated (Int. Cl. 7 , DB name) G21F 9/12 G21F 9 / 06
Claims (1)
離除去するに際し、比表面積が 600ｍ2/ｇ以上の繊維状
活性炭で処理することを特徴とする放射性廃液の処理方
法。1. A method for treating a radioactive waste liquid, comprising treating a radioactive nuclide contained in the radioactive waste liquid with fibrous activated carbon having a specific surface area of at least 600 m 2 / g.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP03350136A JP3078076B2 (en) | 1991-12-09 | 1991-12-09 | Treatment of radioactive liquid waste |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP03350136A JP3078076B2 (en) | 1991-12-09 | 1991-12-09 | Treatment of radioactive liquid waste |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH05157896A JPH05157896A (en) | 1993-06-25 |
| JP3078076B2 true JP3078076B2 (en) | 2000-08-21 |
Family
ID=18408474
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP03350136A Expired - Lifetime JP3078076B2 (en) | 1991-12-09 | 1991-12-09 | Treatment of radioactive liquid waste |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP3078076B2 (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP5880851B2 (en) * | 2012-06-15 | 2016-03-09 | 株式会社神戸製鋼所 | Radionuclide decontamination system and radionuclide decontamination method |
-
1991
- 1991-12-09 JP JP03350136A patent/JP3078076B2/en not_active Expired - Lifetime
Also Published As
| Publication number | Publication date |
|---|---|
| JPH05157896A (en) | 1993-06-25 |
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