JP2002031697A - Method for treating radioactive waste liquid - Google Patents
Method for treating radioactive waste liquidInfo
- Publication number
- JP2002031697A JP2002031697A JP2000216253A JP2000216253A JP2002031697A JP 2002031697 A JP2002031697 A JP 2002031697A JP 2000216253 A JP2000216253 A JP 2000216253A JP 2000216253 A JP2000216253 A JP 2000216253A JP 2002031697 A JP2002031697 A JP 2002031697A
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- Japan
- Prior art keywords
- waste liquid
- radioactive
- radioactive waste
- treatment
- filtration
- 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.)
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- Separation Using Semi-Permeable Membranes (AREA)
Abstract
Description
【０００１】[0001]
【発明の属する技術分野】本発明は、放射性廃液の処理
方法に関し、特に放射性核種イオンの除去を効率的に行
うようにした手段を有する放射性廃液の処理方法に関す
る。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a method for treating a radioactive liquid waste, and more particularly to a method for treating a radioactive liquid waste having means for efficiently removing radionuclide ions.
【０００２】[0002]
【従来の技術】核燃料再処理工場や原子力発電所など、
原子力施設から排出される廃液の中には、放射性物質が
多数含まれる放射性廃液があり、このような廃液が排出
される際には、放射性物質を除去するための様々な処理
が成されていた。2. Description of the Related Art Nuclear fuel reprocessing plants and nuclear power plants
Among the effluents discharged from nuclear facilities, there are radioactive effluents containing a large number of radioactive substances, and when such effluents were discharged, various treatments were performed to remove the radioactive substances. .
【０００３】例えば原子力発電所を例に挙げると、放射
性廃液として、洗濯廃液や床ドレン廃液、ホウ酸ナトリ
ウム廃液などといった廃液が排出される。For example, in the case of a nuclear power plant, wastewater such as laundry wastewater, floor drain wastewater, and sodium borate wastewater is discharged as radioactive wastewater.
【０００４】この際には、イオン交換樹脂を用いて放射
性核種の捕捉を行い、廃液中に含まれる放射性核種の減
少を図ったり、廃液を蒸発濃縮して廃液の量を減少させ
た後、凝縮液が放出基準を満たしていれば海洋放出を行
っていた。[0004] At this time, radionuclide is captured by using an ion exchange resin to reduce radionuclide contained in the waste liquid, or the amount of the waste liquid is reduced by evaporating and concentrating the waste liquid, and then condensing. If the liquid met release standards, it would have been released into the ocean.
【０００５】また、放射性核種を吸着した樹脂を硫酸や
水酸化ナトリウムで溶離させた樹脂溶離廃液について
は、蒸発濃縮させた後、濃縮廃液をセメント等で固形化
処理していた。[0005] Further, the resin-eluting waste liquid obtained by eluting the resin adsorbed with radionuclides with sulfuric acid or sodium hydroxide is concentrated by evaporation, and then the concentrated waste liquid is solidified with cement or the like.
【０００６】[0006]
【発明が解決しようとする課題】しかし、樹脂溶離廃液
やホウ酸ナトリウム廃液といった放射性廃液を蒸発濃縮
させた後、直接固形化処理する従来の方法では、本来は
固化する必要のない非放射性の塩までも、廃液に含まれ
るため放射性物質と共に固化していた。However, in the conventional method of evaporating and concentrating radioactive waste liquid such as resin elution waste liquid and sodium borate waste liquid and then directly solidifying the same, non-radioactive salts which do not originally need to be solidified are used. Until then, it was solidified together with radioactive substances because it was contained in the waste liquid.
【０００７】このため多くの場合、固化条件が放射性核
種よりも非放射性塩の含有量で規定され、固化体の増加
をもたらしていた。For this reason, in many cases, the solidification conditions are defined by the content of the non-radioactive salt rather than the radionuclide, and the solidification is increased.
【０００８】また、廃液に含まれる非放射性の塩によ
り、処分場内に非放射性の陽イオンや陰イオンが多量に
放出した場合には、処分場の核種吸着部位がこれら非放
射性のイオンを吸着するため、放射性核種保持性能の劣
化の可能性があった。[0008] When a large amount of non-radioactive cations and anions are released into the repository by non-radioactive salts contained in the waste liquid, the nuclide adsorption site of the repository adsorbs these non-radioactive ions. Therefore, there was a possibility that the radionuclide retention performance was deteriorated.
【０００９】このため、処分場には放射性物質以外の塩
類を入れないことが望ましく、従来は、イオン交換樹脂
をそのままセメントで固化する方法と、キレート樹脂や
無機（イオン）吸着材を用いて、廃液から放射性核種だ
けを選択的に吸着する方法が考えられていた。For this reason, it is desirable that salts other than radioactive substances are not put into the disposal site. Conventionally, a method of solidifying an ion exchange resin with cement as it is, and a method using a chelate resin or an inorganic (ion) adsorbent are used. A method for selectively adsorbing only radioactive nuclides from wastewater has been considered.
【００１０】しかし、放射性核種を捕捉するために用い
られたイオン交換樹脂をキレート樹脂やセメントを用い
て固化する場合、放射性核種の半減期が長いため、固化
物の保存期間は長期に渡たり、樹脂が処分場で保存され
る間に徐々に劣化する恐れがある。However, when the ion exchange resin used for capturing the radionuclide is solidified by using a chelating resin or cement, the radionuclide has a long half-life, so that the storage time of the solidified product is long. The resin may gradually deteriorate while being stored at the repository.
【００１１】また、有機物は劣化後、放射性核種と錯体
を形成して核種の移行を促進するうえ、現在考えられて
いるように、放射性廃棄物を地中に埋蔵して保管する場
合を想定すると、地下への有機物の混入は抑制する。Further, it is assumed that the organic matter forms a complex with a radionuclide after deterioration to promote the transfer of the nuclide, and that radioactive waste is buried in the ground and stored as currently considered. In addition, the entry of organic matter into the underground is suppressed.
【００１２】そのため、放射性核種を捕捉した樹脂を、
無機質化することが望ましく、その処理が煩雑であっ
た。Therefore, the resin capturing the radionuclide is
It is desirable to mineralize, and the treatment was complicated.
【００１３】一方、無機吸着材が充分にその性能を発揮
するためには、廃液に含まれるコロイドを予め除去する
必要があり、コロイドが存在する場合には、無機交換体
吸着処理だけでは放射性核種を十分に除去することは困
難であった。On the other hand, in order for the inorganic adsorbent to sufficiently exhibit its performance, it is necessary to remove colloids contained in the waste liquid in advance. Was difficult to remove sufficiently.
【００１４】そこで、コロイドの除去に効果的である限
外ろ過に着目し、廃液に存在する放射性コロイド成分
を、孔径約３ｎｍ程度の限外ろ過膜またはそれ以下の孔
径のフィルターでろ過除去し、放射性核種の化学形態を
単純なイオンのみにすることが考えられる。Therefore, paying attention to ultrafiltration, which is effective for removing colloid, the radioactive colloid component present in the waste liquid is removed by filtration using an ultrafiltration membrane having a pore size of about 3 nm or a filter having a pore size smaller than that. It is conceivable to make the chemical form of the radionuclide only a simple ion.
【００１５】しかし現状では、孔径４５０ｎｍ程度の精
密ろ過フィルターの実績があるのみで、限外ろ過膜以下
の孔径のフィルターでは、目詰まりを起こしやすいため
実用化されておらず、無機吸着材による吸着処理性能に
も一定の限界があった。However, at present, there is only a track record of a microfiltration filter having a pore size of about 450 nm, and a filter having a pore size smaller than an ultrafiltration membrane is not practically used because of clogging. There were also certain limits on processing performance.
【００１６】そこで本発明では、放射性廃液からコロイ
ドを除去した後、無機交換体吸着処理を行い、放射性廃
棄物を無機形態で排出する放射性廃液の処理処分方法を
提供することを目的とする。Accordingly, an object of the present invention is to provide a method for treating and disposing of a radioactive waste liquid in which a radioactive waste is discharged in an inorganic form by performing an inorganic exchanger adsorption treatment after removing the colloid from the radioactive waste liquid.
【００１７】[0017]
【課題を解決するための手段】本発明の放射性廃液の処
理方法では、ろ過装置を用いて放射性廃液をろ過するろ
過工程と、前記ろ過工程の後、イオン交換装置を用いて
放射性核種イオンを除去する放射性核種イオン除去工程
とを具備し、前記ろ過装置は、物理的な衝撃を加えてろ
過膜の目詰まりを防止する手段を有する。According to the method for treating radioactive waste liquid of the present invention, a filtration step of filtering the radioactive waste liquid using a filtration device, and after the filtration step, removal of radionuclide ions using an ion exchanger. And a step of removing a radionuclide ion, wherein the filtration device has means for applying physical impact to prevent clogging of the filtration membrane.
【００１８】この構成では、ろ過膜に対して振動や超音
波など物理的な力を加える目詰まり防止手段を有するこ
とにより、ろ過膜の目詰まりによる透過能力の低下を防
止することが出来る。In this configuration, since the clogging prevention means for applying a physical force such as vibration or ultrasonic wave to the filtration membrane is provided, it is possible to prevent a decrease in the permeability due to the clogging of the filtration membrane.
【００１９】また、固化条件に大きな影響を与えていた
非放射性塩を放射性廃棄物と共に固化処理することを防
ぐことができるため、放射性物質に合わせた固化条件で
固化処理を行うことができる。Further, since the solidification treatment of the non-radioactive salt which has greatly affected the solidification conditions together with the radioactive waste can be prevented, the solidification treatment can be performed under the solidification conditions suitable for the radioactive substance.
【００２０】さらに、本発明の放射性廃棄物処理方法で
は、排出される放射性廃棄物が固化処理に適した態様で
あるため、そのままセメント系物質に固化処理すること
ができ、処理が容易である。Further, in the radioactive waste treatment method of the present invention, since the discharged radioactive waste is in a mode suitable for solidification treatment, it can be solidified as it is to a cement-based material, and the treatment is easy.
【００２１】また本発明では、無機吸着材を用いて放射
性核種を吸着除去することにより、放射性核種を保存期
間の長期化に伴う劣化に対して安定な形態で、廃液から
除去および回収を行うことができる。Further, in the present invention, the radionuclide is adsorbed and removed using an inorganic adsorbent, so that the radionuclide is removed and recovered from the waste liquid in a form which is stable against deterioration accompanying a prolonged storage period. Can be.
【００２２】[0022]
【発明の実施の形態】本発明による放射性廃液の処理処
分方法の一実施の形態を図１に示す。DESCRIPTION OF THE PREFERRED EMBODIMENTS FIG. 1 shows an embodiment of a method for treating and disposing of radioactive waste liquid according to the present invention.
【００２３】本発明では、施設１から排出された原廃液
を貯蔵する貯蔵タンク２、貯蔵された原廃液をろ過膜を
用いてろ過するろ過装置３、ろ液をイオン交換処理する
イオン交換装置４、イオン交換装置４によりイオン交換
を行ったろ液を貯留する処理タンク５を有する。In the present invention, a storage tank 2 for storing raw waste liquid discharged from the facility 1, a filtration device 3 for filtering the stored raw waste liquid using a filtration membrane, and an ion exchange device 4 for performing ion exchange treatment on the filtrate. And a treatment tank 5 for storing the filtrate subjected to ion exchange by the ion exchange device 4.
【００２４】そして、ろ過装置３には、ろ過膜として分
画分子量１万〜３０万の限外ろ過膜若しくは分画分子量
１５０〜１万のナノフィルターを有すると共に、ろ過膜
の目詰まりを防止するための目詰まり防止装置を有す
る。The filtration device 3 has an ultrafiltration membrane having a molecular weight cut-off of 10,000 to 300,000 or a nanofilter having a molecular weight cut-off of 150 to 10,000 as a filtration membrane and prevents clogging of the filtration membrane. For preventing clogging.
【００２５】なお、ろ過膜として、限外ろ過膜やナノフ
ィルターと同様のろ過機能を有する限外ろ過カラムなど
を用いてもよい。As the filtration membrane, an ultrafiltration column having the same filtration function as an ultrafiltration membrane or a nanofilter may be used.
【００２６】目詰まり防止装置は、ろ過膜を振動させる
振動機構やろ過膜を回転させる回転機構、ろ過膜に超音
波を照射する超音波照射機構など、ろ過膜に対して物理
的な衝撃を加える機構を有し、膜のファウリング（目詰
まり）を防止する。The clogging prevention device applies a physical shock to the filtration membrane, such as a vibration mechanism for vibrating the filtration membrane, a rotation mechanism for rotating the filtration membrane, and an ultrasonic irradiation mechanism for irradiating the filtration membrane with ultrasonic waves. It has a mechanism to prevent fouling (clogging) of the membrane.
【００２７】また、イオン交換装置は、無機吸着材（選
択的核種吸着無機イオン交換体）が設置されており、Ｃ
ｓ−１３４、Ｃｓ−１３７、Ｓｒ−９０などのアルカリ
金属およびアルカリ土類金属核種、Ｃｏ−５８、Ｃｏ−
６０、Ｎｉ−６３、Ｍｎ−５４などの遷移金属核種、Ｉ
−１２５、Ｉ−１２９、Ｃ−１４、Ｔｃ−９９、Ｃｌ−
３６などのハロゲン核種、Ａｍ−２４１、Ｎｐ−２３
７、Ｕ−２３８などの超ウラン元素といった放射性イオ
ン核種を吸着する。Further, the ion exchange apparatus is provided with an inorganic adsorbent (selective nuclide-adsorbed inorganic ion exchanger).
Alkali metal and alkaline earth metal nuclides such as s-134, Cs-137, Sr-90, Co-58, Co-
Transition metal nuclides such as 60, Ni-63 and Mn-54;
-125, I-129, C-14, Tc-99, Cl-
Halogen nuclides such as 36, Am-241, Np-23
7. Adsorb radioactive nuclides such as transuranium elements such as U-238.
【００２８】なお、ろ液に含まれる放射性イオン核種に
応じて、無機吸着材を選択すると共に、異なる種類の無
機吸着材を組み合わせてもよい。The inorganic adsorbent may be selected according to the radionuclide contained in the filtrate, and different types of inorganic adsorbents may be combined.
【００２９】放射性廃液の処理処分は、まず、原子力発
電所や核燃料再処理工場といった施設１から排出された
原廃液を貯蔵タンク２を経由してろ過装置３に輸送す
る。In the treatment and disposal of the radioactive waste liquid, first, the raw waste liquid discharged from a facility 1 such as a nuclear power plant or a nuclear fuel reprocessing plant is transported to a filtration device 3 via a storage tank 2.
【００３０】ろ過装置３では、ろ過膜を用いて原廃液に
含まれるコロイド成分程度の粒径までの不溶解性物質を
除去する。In the filtration device 3, an insoluble substance having a particle size of about the colloid component contained in the raw waste liquid is removed by using a filtration membrane.
【００３１】そして、ろ過装置３を通過したろ液はイオ
ン交換装置４に運ばれ、無機吸着材を用いて放射性核種
を除去処理され、処理液として処理タンクに貯留され
る。The filtrate that has passed through the filtration device 3 is conveyed to the ion exchange device 4, where it is treated to remove radionuclides using an inorganic adsorbent, and stored in a treatment tank as a treatment solution.
【００３２】処理タンクにおいて、処理液が放射能を有
していないことを確認した後、一般的な排水処理を施
し、海洋等に放出される。After confirming that the treatment liquid does not have radioactivity in the treatment tank, it is subjected to general wastewater treatment and discharged to the ocean or the like.
【００３３】原液の放射能レベルが高い場合には処理液
に放射能が確認される場合があるが、その際には、処理
液を再びイオン交換装置に通過させるか、低レベル放射
性廃液として処理する。When the radioactivity level of the undiluted solution is high, radioactivity may be confirmed in the treatment solution. In this case, the treatment solution is passed again through the ion exchanger or treated as a low-level radioactive waste solution. I do.
【００３４】なお、ろ過装置３により廃液から分離され
た不溶解性沈殿物質は貯蔵タンク２に運ばれて蓄積され
る。The insoluble precipitate separated from the waste liquid by the filtration device 3 is carried to the storage tank 2 and accumulated therein.
【００３５】また、貯蔵タンク２に蓄積された不溶解性
沈殿物質及びコロイド成分が一定の濃度に達したら排出
し、使用済みイオン交換体と共にセメント等で固化処理
する。When the insoluble precipitate and colloid components accumulated in the storage tank 2 reach a certain concentration, they are discharged and solidified with a used ion exchanger using cement or the like.
【００３６】以下、実施例を用いて、さらに詳しく説明
する。Hereinafter, the present invention will be described in more detail with reference to examples.
【００３７】[0037]
【実施例１】放射性廃液として、放射能濃度１００Ｂｑ
／ｍｌ（Ｃｏ−６０、Ｎｉ−６３）、０．１Ｍ・ＮａＮ
Ｏ３（ｐＨ９）の放射性廃液１０Ｌを用意し、ろ過装置
の有無による無機イオン交換樹脂処理後の放射能濃度の
違いを比較した。[Example 1] As radioactive waste liquid, radioactivity concentration 100Bq
/ Ml (Co-60, Ni-63), 0.1M NaN
10 L of radioactive waste liquid of O 3 (pH 9) was prepared, and the difference in the radioactivity concentration after the inorganic ion exchange resin treatment depending on the presence or absence of a filtration device was compared.
【００３８】なお、ろ過装置では、限外ろ過膜（分画分
子数３００００）を用い、廃液の処理流量は、１Ｌ／ｈ
とした。In the filtration device, an ultrafiltration membrane (number of molecules of fractionation: 30,000) was used, and the treatment flow rate of the waste liquid was 1 L / h.
And
【００３９】この結果を表１に示す。Table 1 shows the results.
【００４０】 このように、無機イオン交換体による処理を施す前に、
限外ろ過処理を行うことにより、廃液中の放射能濃度を
大幅に低下させることができる。[0040] Thus, before performing the treatment with the inorganic ion exchanger,
By performing the ultrafiltration treatment, the radioactivity concentration in the waste liquid can be significantly reduced.
【００４１】[0041]
【実施例２】放射性廃液として、放射能濃度１０Ｂｑ／
ｍｌ（Ｃｏ−６０、Ｎｉ−６３）、０．１Ｍ・Ｎａ２Ｓ
Ｏ４（ｐＨ９）の放射性廃液１０Ｌを用意し、ろ過装置
の有無による無機イオン交換樹脂処理後の放射能濃度の
違いを比較した。Example 2 As a radioactive waste liquid, a radioactivity concentration of 10 Bq /
ml (Co-60, Ni-63), 0.1 M Na 2 S
10 L of O 4 (pH 9) radioactive waste liquid was prepared, and the difference in the radioactivity concentration after the inorganic ion exchange resin treatment depending on the presence or absence of a filtration device was compared.
【００４２】なお、ろ過装置では、限外ろ過膜（分画分
子数３００００）を用い、廃液の処理流量は、１Ｌ／ｈ
とした。In the filtration apparatus, an ultrafiltration membrane (the number of molecules of the fractionation is 30,000) was used, and the treatment flow rate of the waste liquid was 1 L / h.
And
【００４３】この結果を表２に示す。Table 2 shows the results.
【００４４】 このように、吸着による処理を施す前に、限外ろ過処理を
行うことにより、廃液中の放射能濃度を大幅に低下させ
ることができる。[0044] As described above, by performing the ultrafiltration treatment before performing the treatment by the adsorption, the radioactivity concentration in the waste liquid can be significantly reduced.
【００４５】また本発明では、無機吸着材の処理能力を
超えない限り、放射能濃度の高い低いに関係なく、放射性
核種の除去を良好に行うことができる。In the present invention, as long as the processing capacity of the inorganic adsorbent is not exceeded, the removal of radionuclides can be performed satisfactorily regardless of the radioactivity concentration.
【００４６】[0046]
【発明の効果】本発明では、低伝導度、高伝導度、再処
理廃液といった原廃液の種類に関係なく、放射性廃液
を、放射能の無いまたは低い塩類を多量に含む処理液
と、放射能が高く塩類を含まない無機吸着材とに分離す
ることができる。According to the present invention, a radioactive waste liquid is treated with a treatment liquid containing a large amount of salts having no or low radioactivity, regardless of the type of raw waste liquid such as low conductivity, high conductivity, and reprocessing waste liquid. , And can be separated from inorganic adsorbents that do not contain salts.
【００４７】このため、処理液が放出基準を満たす場合
には、海洋等に放出することが可能であり、放射性廃棄
物として処理を行う放射性廃液の量を大幅に減少させる
ことができる。Therefore, when the treatment liquid satisfies the discharge standard, it can be discharged to the sea or the like, and the amount of radioactive waste liquid to be treated as radioactive waste can be greatly reduced.
【００４８】また、放射性核種を吸着した無機吸着材に
は塩類が含まれず、物理的化学的に安定しているため、
ホウ酸、硝酸、硫酸等の塩類が処分場内に取り込まれる
ことを防止することができると共に、セメントなどで固
化処理した後、時間の経過と共に塩類が染み出すことに
よる、処分場周辺の環境破壊を防止することもできる。Further, since the inorganic adsorbent which has adsorbed the radionuclide does not contain salts and is physically and chemically stable,
In addition to preventing salts such as boric acid, nitric acid, and sulfuric acid from being taken into the disposal site, it also prevents the destruction of the environment around the disposal site due to salt seeping out over time after solidification with cement. It can also be prevented.
【００４９】さらに、透過膜で不溶解性物質とコロイド
成分とが濃縮された廃液は、そのままセメント系物質に
固化処理することが出来るため、処理が容易である。Further, the waste liquid in which the insoluble substance and the colloid component are concentrated in the permeable membrane can be directly solidified into a cement-based substance, so that the treatment is easy.
【図１】本発明による放射性廃液の処理処分方法を示す
構成図FIG. 1 is a block diagram showing a method for treating and disposing of radioactive waste liquid according to the present invention.
１…施設 ２…貯蔵タンク ３…ろ過装置 ４…イオン交換装置 ５…処理タンク DESCRIPTION OF SYMBOLS 1 ... Facility 2 ... Storage tank 3 ... Filtration apparatus 4 ... Ion exchange apparatus 5 ... Processing tank
───────────────────────────────────────────────────── フロントページの続き (72)発明者 渋谷 守 茨城県東茨城郡大洗町成田町2205 日揮株 式会社技術研究所内 Ｆターム(参考） 4D006 GA06 KA47 KB11 KB12 KB14 MB05 PA02 PB08 PC33 ────────────────────────────────────────────────── ─── Continued on the front page (72) Inventor Mamoru Shibuya 2205 Narita-cho, Oarai-machi, Higashiibaraki-gun, Ibaraki F-term in JGC Corporation Technical Research Institute 4D006 GA06 KA47 KB11 KB12 KB14 MB05 PA02 PB08 PC33
Claims (2)
過工程と、 前記ろ過工程の後、イオン交換装置を用いて放射性核種
イオンを除去する放射性核種イオン除去工程とを具備
し、 前記ろ過装置は、物理的な衝撃を加えてろ過膜の目詰ま
りを防止する手段を有することを特徴とする放射性廃液
の処理方法。A filtration step for filtering radioactive waste liquid using a filtration device; and a radionuclide ion removal step for removing radionuclide ions using an ion exchange device after the filtration step. Is a method for treating a radioactive waste liquid, comprising means for applying a physical impact to prevent clogging of a filtration membrane.
無機吸着材を用いることを特徴とする請求項１記載の放
射性廃液の処理方法。2. In the step of removing radionuclide ions,
The method for treating a radioactive waste liquid according to claim 1, wherein an inorganic adsorbent is used.
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| JP2000216253A JP2002031697A (en) | 2000-07-17 | 2000-07-17 | Method for treating radioactive waste liquid |
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| JP2015059852A (en) * | 2013-09-19 | 2015-03-30 | 日立Ｇｅニュークリア・エナジー株式会社 | Method for treating radioactive waste liquid and apparatus for treating radioactive waste liquid |
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| JP2015059852A (en) * | 2013-09-19 | 2015-03-30 | 日立Ｇｅニュークリア・エナジー株式会社 | Method for treating radioactive waste liquid and apparatus for treating radioactive waste liquid |
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| JP2021120662A (en) * | 2020-01-31 | 2021-08-19 | 日立Ｇｅニュークリア・エナジー株式会社 | Radioactive waste liquid treatment system and method for treating radioactive waste liquid |
| JP7312709B2 (en) | 2020-01-31 | 2023-07-21 | 日立Ｇｅニュークリア・エナジー株式会社 | Radioactive waste liquid treatment system and radioactive waste liquid treatment method |
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