JP2002243892A - Solidification method for radioactive alkaline waste liquid - Google Patents
Solidification method for radioactive alkaline waste liquidInfo
- Publication number
- JP2002243892A JP2002243892A JP2001046991A JP2001046991A JP2002243892A JP 2002243892 A JP2002243892 A JP 2002243892A JP 2001046991 A JP2001046991 A JP 2001046991A JP 2001046991 A JP2001046991 A JP 2001046991A JP 2002243892 A JP2002243892 A JP 2002243892A
- Authority
- JP
- Japan
- Prior art keywords
- waste liquid
- furnace slag
- blast furnace
- sodium hydroxide
- radioactive
- 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
Classifications
-
- C—CHEMISTRY; METALLURGY
- C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
- C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
- C04B28/00—Compositions of mortars, concrete or artificial stone, containing inorganic binders or the reaction product of an inorganic and an organic binder, e.g. polycarboxylate cements
- C04B28/006—Compositions of mortars, concrete or artificial stone, containing inorganic binders or the reaction product of an inorganic and an organic binder, e.g. polycarboxylate cements containing mineral polymers, e.g. geopolymers of the Davidovits type
-
- C—CHEMISTRY; METALLURGY
- C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
- C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
- C04B28/00—Compositions of mortars, concrete or artificial stone, containing inorganic binders or the reaction product of an inorganic and an organic binder, e.g. polycarboxylate cements
- C04B28/02—Compositions of mortars, concrete or artificial stone, containing inorganic binders or the reaction product of an inorganic and an organic binder, e.g. polycarboxylate cements containing hydraulic cements other than calcium sulfates
- C04B28/08—Slag cements
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/04—Treating liquids
- G21F9/06—Processing
- G21F9/16—Processing by fixation in stable solid media
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02P—CLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
- Y02P40/00—Technologies relating to the processing of minerals
- Y02P40/10—Production of cement, e.g. improving or optimising the production methods; Cement grinding
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
- Y02W30/00—Technologies for solid waste management
- Y02W30/50—Reuse, recycling or recovery technologies
- Y02W30/91—Use of waste materials as fillers for mortars or concrete
Landscapes
- Chemical & Material Sciences (AREA)
- Engineering & Computer Science (AREA)
- Ceramic Engineering (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Inorganic Chemistry (AREA)
- Materials Engineering (AREA)
- Structural Engineering (AREA)
- Organic Chemistry (AREA)
- Life Sciences & Earth Sciences (AREA)
- Environmental & Geological Engineering (AREA)
- General Life Sciences & Earth Sciences (AREA)
- Geochemistry & Mineralogy (AREA)
- Geology (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Processing Of Solid Wastes (AREA)
Abstract
Description
【０００１】[0001]
【発明の属する技術分野】本発明は、高速増殖炉の金属
ナトリウムから変換された水酸化ナトリウム廃液を、高
充填固化処理する放射性アルカリ廃液の固化処理方法に
関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a method for solidifying a radioactive alkali waste liquid, which solidifies a sodium hydroxide waste liquid converted from metallic sodium in a fast breeder reactor at a high filling rate.
【０００２】[0002]
【従来の技術】高速増殖炉で使用されている金属ナトリ
ウムは、水酸化ナトリウムへ変換される。この水酸化ナ
トリウム廃液は、セメント等で安定した固化体として保
管される。2. Description of the Related Art Metallic sodium used in fast breeder reactors is converted to sodium hydroxide. The sodium hydroxide waste liquid is stored as a stable solidified body with cement or the like.
【０００３】水酸化ナトリウム廃液は、そのままセメン
トにより固化すると、セメント成分であるＣ3Ａ（３Ｃ
ａＯ・Ａｌ2Ｏ3）およびＣ4ＡＦ（４ＣａＯ・Ａｌ2Ｏ3
・Ｆｅ 2Ｏ3）の水和を促進して急結化してしまうため、
塩酸または硫酸等により中和処理を行い、塩化ナトリウ
ムまたは硫酸ナトリウムの形態で、セメント固化処理さ
れている。[0003] The sodium hydroxide waste liquid is
When the cement is solidified, the cement component CThreeA (3C
aO ・ AlTwoOThree) And CFourAF (4CaO.AlTwoOThree
・ Fe TwoOThree) Promotes hydration and causes rapid setting,
Neutralize with hydrochloric acid or sulfuric acid, etc.
Cement hardened in the form of
Have been.
【０００４】しかしながら、上記の方法では中和処理が
必要であるため、当該廃棄物の発生量が増大すると共
に、中和によって形成された硫酸ナトリウムは、２００
リットルドラム缶１個当たり、３０ｋｇ程度しか充填で
きないと云う問題があった。[0004] However, the above method requires a neutralization treatment, so that the amount of the waste is increased and the sodium sulfate formed by the neutralization is 200%.
There is a problem that only about 30 kg can be filled per liter drum.
【０００５】[0005]
【発明が解決しようとする課題】水酸化ナトリウム廃液
を直接固化することができれば、水酸化ナトリウムを２
００リットルドラム缶１個当たり約２００ｋｇの充填が
可能となり、中和処理による廃棄物の発生量の増大を防
止できると共に、従来に比べて高充填が可能となり、従
来のセメント固化法に比較して、固化体の発生量を６分
の１以下に低減することができる。その結果、固化体の
貯蔵スペースの減少と処理コストを大幅に削減できるこ
とが期待される。If the sodium hydroxide waste liquid can be directly solidified, the sodium hydroxide is reduced to 2%.
It is possible to fill about 200 kg per drum of 00 liters, which prevents the amount of waste generated by the neutralization process from increasing, and enables high filling compared to the conventional method. The amount of the solidified body can be reduced to 1/6 or less. As a result, it is expected that the storage space of the solidified body can be reduced and the processing cost can be significantly reduced.
【０００６】水酸化ナトリウムへセメントを添加すると
急結現象が起こり、水酸化ナトリウムとセメントを混練
することができなくなり、安定な固化体を作成すること
ができない。[0006] When cement is added to sodium hydroxide, a quick setting phenomenon occurs, so that it becomes impossible to knead the sodium hydroxide and the cement, and a stable solidified body cannot be produced.
【０００７】本発明の目的は、上記に鑑み高速増殖炉等
の金属ナトリウムから変換された水酸化ナトリウムを含
む廃液を、高充填で固化処理でき放射性アルカリ廃液の
固化処理方法の提供にある。In view of the above, an object of the present invention is to provide a method for solidifying a radioactive alkaline waste liquid which can solidify a waste liquid containing sodium hydroxide converted from metallic sodium in a fast breeder reactor or the like with high filling.
【０００８】[0008]
【課題を解決するための手段】前記の目的を達成する本
発明の要旨は次ぎのとおりである。The gist of the present invention to achieve the above object is as follows.
【０００９】（１） 放射性アルカリ廃液へ高炉水砕ス
ラグを添加して固化することを特徴とするものである。(1) The method is characterized in that granulated blast furnace slag is added to radioactive alkali waste liquid and solidified.
【００１０】（２） 水酸化ナトリウム廃液へ高炉水砕
スラグを添加して固化することを特徴とするものであ
る。(2) The granulated blast furnace slag is added to the sodium hydroxide waste liquid and solidified.
【００１１】（３） アルカリ廃液として、高速増殖炉
の金属ナトリウムから変換された水酸化ナトリウム廃液
へ高炉水砕スラグを添加して固化することを特徴とする
ものである。(3) Granulated blast-furnace slag is added to sodium hydroxide waste liquid converted from metallic sodium in a fast breeder reactor as an alkali waste liquid and solidified.
【００１２】上記において、アルカリ廃液に対し高炉水
砕スラグを重量で１〜１.５配合することが望ましい。In the above, it is desirable to mix the granulated blast furnace slag with the alkali waste liquid by 1 to 1.5 by weight.
【００１３】[0013]
【発明の実施の形態】水酸化ナトリウム溶液３０ｍｌ
（ＮａＯＨ濃度：３０重量％）、と高炉スラグの２０
ｇ，３０ｇおよび４０ｇのそれぞれを混練した結果、良
好な固化体が得られた。BEST MODE FOR CARRYING OUT THE INVENTION 30 ml of sodium hydroxide solution
(NaOH concentration: 30% by weight) and 20 pieces of blast furnace slag.
As a result of kneading each of g, 30 g and 40 g, a good solid was obtained.
【００１４】これは、上記高炉スラグはＣａＯ，ＳｉＯ
2，Ａｌ2Ｏ3，ＭｇＯ等で構成されており、その表面に
透過性が低い不定形のアルミノシリケート水和物（Ａ−
Ｓ−Ｈ６）の膜が形成されており、該高炉スラグの粒子
内部への水の侵透や、粒子からのイオンの溶出を抑制す
るため、通常の雰囲気では水和は進行しにくい。This is because the blast furnace slag is made of CaO, SiO
2 , Al 2 O 3 , MgO, etc., whose surface has an amorphous aluminosilicate hydrate (A-
Since a film of S-H6) is formed and water permeation into the particles of the blast furnace slag and elution of ions from the particles are suppressed, hydration hardly proceeds in a normal atmosphere.
【００１５】本実施例では、水酸化ナトリウムは高炉ス
ラグにＯＨ-を吸着させてガラス構造を破壊し、Ｃａ
Ｏ，ＳｉＯ2，Ａｌ2Ｏ3，ＭｇＯ等の溶出を促進させ
る。そのため、液相中の各イオン濃度を高めて水和物を
継続して析出させ、溶出した各イオンはカルシウムシリ
ケート水和物や、カルシウムアルミネート水和物を生成
して硬化させたものを用いる。In the present embodiment, sodium hydroxide causes OH - to be adsorbed on the blast furnace slag to destroy the glass structure, and Ca
Promotes elution of O, SiO 2 , Al 2 O 3 , MgO, etc. For this reason, the hydrate is continuously precipitated by increasing the concentration of each ion in the liquid phase, and the eluted ions use calcium silicate hydrate or calcium aluminate hydrate, which is hardened. .
【００１６】上記水酸化ナトリウムと高炉スラグを練り
混ぜることで、良好な固化体が得られることを利用した
ものである。[0016] The present invention utilizes the fact that a good solidified body can be obtained by kneading and mixing the above sodium hydroxide and blast furnace slag.
【００１７】放射性アルカリ廃液の固化体作成装置の概
要を図１に示す。該装置は、放射性アルカリ廃液を供給
するアルカリ廃液タンク１、高炉スラグを貯留する高炉
スラグ貯留ホッパー２、これらを計量する廃液計量器
３、高炉スラグ計量器４、および、アリカリ廃液と高炉
スラグを混練する混練機５により構成される。FIG. 1 shows an outline of an apparatus for producing a solidified radioactive alkali waste liquid. The apparatus comprises: an alkaline waste liquid tank 1 for supplying a radioactive waste liquid; a blast furnace slag storage hopper 2 for storing blast furnace slag; It is constituted by a kneading machine 5.
【００１８】次ぎに上記装置を用い、本発明の放射性ア
ルカリ廃液の固化処理方法を説明する。Next, the method for solidifying a radioactive alkaline waste liquid of the present invention using the above-described apparatus will be described.
【００１９】例えば、アルカリ廃液と高炉スラグの比が
１：１（重量比）となるように、廃液計量器３と高炉ス
ラグ計量器４でそれぞれ計量したアルカリ廃液と高炉ス
ラグを混練機５に投入する。For example, the alkali waste liquid and the blast furnace slag which are respectively measured by the waste liquid measuring device 3 and the blast furnace slag measuring device 4 are put into the kneader 5 so that the ratio of the alkali waste liquid to the blast furnace slag becomes 1: 1 (weight ratio). I do.
【００２０】混練機５内で、放射性のアルカリ廃液と高
炉スラグとを所定時間混練した後、混練物をドラム缶６
に排出する。After the radioactive alkaline waste liquid and the blast furnace slag are kneaded in the kneader 5 for a predetermined time, the kneaded material is transferred to a drum 6
To be discharged.
【００２１】上記のような作成工程により、水酸化ナト
リウムと高炉スラグを十分混練することが可能となり、
水酸化ナトリウムと、高炉スラグのセメント成分である
Ｃ3Ａ（３ＣａＯ・Ａｌ2Ｏ3）およびＣ4ＡＦ（４ＣａＯ
・Ａｌ2Ｏ3・Ｆｅ2Ｏ3）の水和を促進することがない。
その結果、十分に混練され、良好な物性を有する固化体
を作成することができる。By the above-described preparation process, it becomes possible to sufficiently knead the sodium hydroxide and the blast furnace slag,
Sodium hydroxide and C 3 A (3CaO.Al 2 O 3 ) and C 4 AF (4CaO) which are cement components of blast furnace slag
· Does not promote hydration of Al 2 O 3 · Fe 2 O 3 ).
As a result, it is possible to produce a solid that is sufficiently kneaded and has good physical properties.
【００２２】[0022]
【発明の効果】本発明は、高炉スラグがアルカリと反応
して硬化する際の潜在性硬化性を用いることにより、水
酸化ナトリウムの急結現象を防止し、放射性アルカリ廃
液の固化処理を可能としたものである。According to the present invention, the rapid hardening phenomenon of sodium hydroxide can be prevented by using the latent curing property when blast furnace slag reacts with alkali and hardens, and the solidification of radioactive alkali waste liquid becomes possible. It was done.
【００２３】即ち、水酸化ナトリウムと高炉スラグは、
混練すると水酸化ナトリウムと、高炉スラグのセメント
成分であるＣ3Ａ（３ＣａＯ・Ａｌ2Ｏ3）およびＣ4ＡＦ
（４ＣａＯ・Ａｌ2Ｏ3・Ｆｅ2Ｏ3）が、水和を促進する
ことないので十分な混練ができ、良好な物性の固化体を
容易に作成することができる。That is, sodium hydroxide and blast furnace slag
When kneaded, sodium hydroxide and C 3 A (3CaO.Al 2 O 3 ) and C 4 AF which are cement components of blast furnace slag are mixed.
Since (4CaO.Al 2 O 3 .Fe 2 O 3 ) does not promote hydration, sufficient kneading can be performed, and a solid having good physical properties can be easily produced.
【図１】放射性アルカリ廃液の固化体作成装置の概要を
示す構成図である。FIG. 1 is a configuration diagram showing an outline of an apparatus for producing a solidified body of radioactive alkali waste liquid.
１…アルカリ廃液タンク、２…高炉スラグ貯留ホッパ
ー、３…廃液計量器、４…高炉スラグ計量器、５…混練
機、６…ドラム缶。DESCRIPTION OF SYMBOLS 1 ... Alkaline waste liquid tank, 2 ... Blast furnace slag storage hopper, 3 ... Waste liquid measuring device, 4 ... Blast furnace slag measuring device, 5 ... Kneader, 6 ... Drum can.
───────────────────────────────────────────────────── フロントページの続き (72)発明者 深澤 哲生 茨城県日立市幸町三丁目１番１号 株式会 社日立製作所原子力事業部内 (72)発明者 川崎 弘嗣 茨城県東茨城郡大洗町成田町4002番地 核 燃料サイクル開発機構 大洗工学センター 内 (72)発明者 仲井 悟 茨城県東茨城郡大洗町成田町4002番地 核 燃料サイクル開発機構 大洗工学センター 内 (72)発明者 今堀 真司 茨城県東茨城郡大洗町成田町4002番地 核 燃料サイクル開発機構 大洗工学センター 内 (72)発明者 小西 賢介 茨城県東茨城郡大洗町成田町4002番地 核 燃料サイクル開発機構 大洗工学センター 内 ──────────────────────────────────────────────────続 き Continuing on the front page (72) Inventor Tetsuo Fukasawa 3-1-1 Kochicho, Hitachi-shi, Ibaraki Pref. Nuclear Power Division, Hitachi, Ltd. (72) Inventor Hiroshi Kawasaki Narita-cho, Oarai-cho, Higashiibaraki-gun, Ibaraki 4002 Nuclear Fuel Cycle Development Organization Oarai Engineering Center (72) Inventor Satoru Nakai 4002 Nuclear Fuel Cycle Development Organization Oarai Engineering Center in Higashiibaraki-gun, Ibaraki Pref. 4002 Narita-cho, Oarai-machi Nuclear Fuel Cycle Development Organization Oarai Engineering Center (72) Inventor Kensuke Konishi 4002 Narita-cho, Oarai-machi, Higashiibaraki-gun, Ibaraki Nuclear Fuel Cycle Development Organization Oarai Engineering Center
Claims (4)
添加して固化することを特徴とする放射性アルカリ廃液
の固化処理方法。1. A method for solidifying radioactive alkali waste liquid, comprising adding granulated blast furnace slag to the radioactive alkali waste liquid and solidifying it.
を添加して固化することを特徴とする放射性アルカリ廃
液の固化処理方法。2. A method for solidifying a radioactive alkali waste liquid, comprising adding granulated blast furnace slag to the sodium hydroxide waste liquid to solidify it.
れた水酸化ナトリウム廃液へ高炉水砕スラグを添加して
固化することを特徴とする放射性アルカリ廃液の固化処
理方法。3. A method for solidifying radioactive alkali waste liquid, which comprises adding granulated blast furnace slag to sodium hydroxide waste liquid converted from metallic sodium in a fast breeder reactor and solidifying it.
スラグを重量で１〜１.５配合する請求項１，２または
３に記載の放射性アルカリ廃液の固化処理方法。4. The method for solidifying a radioactive alkali waste liquid according to claim 1, wherein the granulated blast furnace slag is blended in an amount of 1 to 1.5 by weight with respect to the alkali waste liquid.
Priority Applications (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2001046991A JP2002243892A (en) | 2001-02-22 | 2001-02-22 | Solidification method for radioactive alkaline waste liquid |
| FR0202209A FR2821203A1 (en) | 2001-02-22 | 2002-02-21 | Radioactive alkaline liquid residue solidification comprises adding granulated blast furnace slag |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2001046991A JP2002243892A (en) | 2001-02-22 | 2001-02-22 | Solidification method for radioactive alkaline waste liquid |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JP2002243892A true JP2002243892A (en) | 2002-08-28 |
Family
ID=18908510
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP2001046991A Pending JP2002243892A (en) | 2001-02-22 | 2001-02-22 | Solidification method for radioactive alkaline waste liquid |
Country Status (2)
| Country | Link |
|---|---|
| JP (1) | JP2002243892A (en) |
| FR (1) | FR2821203A1 (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2881740A1 (en) * | 2005-02-04 | 2006-08-11 | Inertec Snc | PROCESS FOR SOLIDIFYING AND STABILIZING AQUEOUS SOLUTION OF CONCENTRATED SODIUM HYDROXIDE |
| JP2010002379A (en) * | 2008-06-23 | 2010-01-07 | Toshiba Corp | Manufacturing method for radioactive waste processing material, radioactive waste processing method, and radioactive waste backfilling method |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP1837882A1 (en) * | 2006-03-22 | 2007-09-26 | Enco S.r.l. | Methods and compositions for disposal of radioactive liquid wastes |
| CN113069708B (en) * | 2021-03-30 | 2022-05-17 | 北京荣创岩土工程股份有限公司 | Method for treating caustic sludge by combining chemical conditioning with vacuum preloading |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2479541A1 (en) * | 1980-03-27 | 1981-10-02 | Gagneraud Pere Fils Entr | METHOD FOR BLOCKING ALKALI AND ALKALINE-EARTH RADIO-ACTIVE ELEMENTS |
-
2001
- 2001-02-22 JP JP2001046991A patent/JP2002243892A/en active Pending
-
2002
- 2002-02-21 FR FR0202209A patent/FR2821203A1/en active Pending
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2881740A1 (en) * | 2005-02-04 | 2006-08-11 | Inertec Snc | PROCESS FOR SOLIDIFYING AND STABILIZING AQUEOUS SOLUTION OF CONCENTRATED SODIUM HYDROXIDE |
| WO2006082346A3 (en) * | 2005-02-04 | 2006-09-28 | Inertec | Method for solidifying and stabilizing a concentrated aqueous sodium hydroxide solution |
| GB2439472A (en) * | 2005-02-04 | 2007-12-27 | Inertec | Method for solidifying and stabilizing a concentrated aqueous sodium hydroxide solution |
| GB2439472B (en) * | 2005-02-04 | 2010-09-08 | Inertec | Process for the solidification and stabilization of concentrated aqueous sodium hydroxide solution |
| US7812209B2 (en) | 2005-02-04 | 2010-10-12 | Inertec | Method for solidifying and stabilizing a concentrated aqueous sodium hydroxide solution |
| JP2010002379A (en) * | 2008-06-23 | 2010-01-07 | Toshiba Corp | Manufacturing method for radioactive waste processing material, radioactive waste processing method, and radioactive waste backfilling method |
Also Published As
| Publication number | Publication date |
|---|---|
| FR2821203A1 (en) | 2002-08-23 |
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