JPH0223840B2 - - Google Patents
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- Publication number
- JPH0223840B2 JPH0223840B2 JP58050005A JP5000583A JPH0223840B2 JP H0223840 B2 JPH0223840 B2 JP H0223840B2 JP 58050005 A JP58050005 A JP 58050005A JP 5000583 A JP5000583 A JP 5000583A JP H0223840 B2 JPH0223840 B2 JP H0223840B2
- Authority
- JP
- Japan
- Prior art keywords
- waste liquid
- cleaning
- detergent
- asphalt
- volume
- 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
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- Detergent Compositions (AREA)
Description
本発明は原子力発電所等において作業用衣服、
保安用具等の放射性物質や一般汚垢物質を洗浄に
よつて除去清浄化するための洗剤と、該洗剤によ
る洗浄廃液の処理方法に関するものである。
従来、衣類等の一般汚垢や放射性物質に汚染さ
れた場合の洗浄は、市販されている家庭用洗剤や
起泡性の大きい非イオン性界面活性剤の単独か、
あるいはキレート剤との併用による洗剤を用いた
り、鉱酸等による酸洗いの後キレート剤等を用い
る方法が採用されていた。
これら従来の方法は次のような欠点をもつてい
ることが問題になる。そのいくつかを挙げると、
市販洗剤や気泡性の大きい界面活性剤を用いて洗
浄した場合、放射能汚染物質の除去率の問題もさ
ることながら、放射性物質を含む洗浄廃液の加熱
濃縮工程において、激しい発泡性によつてキヤリ
オーバーが起こり、加熱濃縮が不可能になるか、
極めて複雑な処理を行なう必要がある。またポリ
リン酸塩などが配合されている場合には、リン酸
塩等の廃棄が規制されて難しい問題となつてきて
いる。またゼオライト等が含まれている場合、加
熱濃縮装置の配管や内部に沈積が激しく、安全な
濃縮を行ない難い。酸洗いの場合は衣服の損傷と
機械の腐蝕が甚だしいという欠点をもつている。
又、起泡性の少ない
を用いたトリポリリン酸ソーダと硫酸ソーダや炭
酸ソーダを含有する放射能汚染除去用洗剤が知ら
れているが、この洗剤は、近年、海域や湖沼、河
川のリン酸化合物、窒素化合物による富栄養化防
止に対する配慮から、できるだけ流入を少なくし
たいとする傾向に逆行する欠点を有する。また減
容化した洗剤とビルダーを含む廃液をアスフアル
ト中に混合し固化して、このものを水中に貯蔵し
た場合、ビルダーとして硫酸ソーダや炭酸ソーダ
などを含有する場合に、水と徐々に接触し、結晶
水を取り込んで結晶化が起こり、容積が極めて増
大する。
The present invention provides work clothes for nuclear power plants, etc.
The present invention relates to a detergent for cleaning and removing radioactive substances and general dirt from security equipment, etc., and a method for treating cleaning waste liquid using the detergent. Conventionally, when cleaning clothes contaminated with general dirt or radioactive materials, commercially available household detergents or highly foaming nonionic surfactants have been used alone, or
Alternatively, a method has been adopted in which a detergent is used in combination with a chelating agent, or a method is used in which a chelating agent or the like is used after pickling with mineral acid or the like. These conventional methods have the following drawbacks. To name a few:
When cleaning with commercially available detergents or surfactants with large foaming properties, not only is there a problem with the removal rate of radioactive contaminants, but also the severe foaming property of the cleaning waste liquid containing radioactive substances can cause a problem in the cleaning process. Overflow occurs and heating and concentration becomes impossible, or
It is necessary to perform extremely complex processing. Furthermore, when polyphosphates and the like are blended, disposal of the phosphates and the like is regulated and becomes a difficult problem. Furthermore, if zeolite or the like is contained, it will accumulate heavily in the pipes and inside of the heating concentrator, making it difficult to perform safe concentration. Acid washing has the drawbacks of severe damage to the clothes and corrosion of the machinery. Also, it has low foaming properties. A detergent for removing radioactive contamination containing sodium tripolyphosphate, sodium sulfate, and soda carbonate is known. It has the disadvantage of going against the trend of trying to minimize the inflow due to prevention considerations. Also, if a reduced volume of waste liquid containing detergent and builder is mixed in asphalt and solidified, and this is stored in water, or if it contains sodium sulfate or soda carbonate as a builder, it will gradually come into contact with water. , crystallization occurs by taking in crystal water, and the volume increases significantly.
【表】
比重 比重
2.533 1.510
[Table] Specific gravity Specific gravity
2.533 1.510
【表】
比重 比重
2.533 1.440
以上の結果となり、アスフアルトやコンクリー
トで固化させた場合、この甚だしい容積増大率に
よつて、アスフアルトやコンクリート固化物が極
めて強い圧力を受けて、容易に崩壊してしまう。
固化物が崩壊すると固化内蔵させた放射能汚染物
質も流出逸散してしまうという極めて好ましから
ざる結果となる欠点をもつている。
本発明者らは以上のような放射能汚染物質と洗
浄に関する種々の問題点を解決した優れた洗浄剤
及び該洗浄剤の洗浄廃液の処理方法を見出すべく
鋭意研究の結果、本発明に到達した。
即ち、本発明は次の一般式(1)又は(2)
で表わされる非イオン界面活性剤の単独または混
合物0.5〜20重量％と硫酸カリウム又は（及び）
炭酸カリウム80〜95.5重量％とを必須成分として
含有することを特徴とする放射能汚染除去用洗剤
及びかかる洗剤による洗剤廃液を逆浸透法又は加
熱濃縮により減容化し、これをアスフアルト固化
することを特徴とする放射能汚染除去用洗剤の洗
浄廃液処理方法を提供するものである。
本発明の洗浄剤は起泡性が少なく、濃縮減容化
の高温蒸発濃縮工程や、逆浸透法による処理工程
中の塩類の漏洩もなく、減容化洗浄剤をアスフア
ルトで固定しても、従来のビルダーの如く多くの
結晶水を取り込み強い結晶圧が生じるということ
がないためアスフアルトを水中で崩壊させること
なく、安定、強固に保存させることができる。
硫酸カリウム（K2SO4）は結晶水をもつことな
く2K+＋SO2- 4にイオン化し、溶解拡散していく。
また炭酸カリウム（K2SO3）は極めて潮解性が強
く、溶解度が大きく、2K+＋CO2- 3にイオン化溶
解する。ナトリウムの硫酸塩や炭酸塩のように結
晶水を取り込んだ強固な結晶を生成しない。従つ
て容積増大も起こらないためアスフアルトやコン
クリートの固化物を崩壊させないことがわかつ
た。
本発明の洗剤は従来の市販洗剤及び非イオン性
界面活性剤またはポリリン酸ソーダを含む洗剤よ
りも、放射性物質のみでなく、衣服に付着する汚
垢や油汚れに対してより優れた洗浄性有し、低泡
性でその洗浄廃液の直接加熱濃縮化も又逆浸透法
による濃縮化も容易に行なえる洗浄剤であり、そ
の有用性は極めて大である。
本発明の洗剤を用いて洗浄を行なつた洗浄廃
液、即ち放射性物質の取扱い施設および原子力発
電所より発生する放射能を含む洗浄廃液の処理は
逆浸透装置あるいは廃液蒸発装置により濃縮され
て減容化し、最終濃縮水はアスフアルト等の水分
を蒸発させる固定装置により固化される。
逆浸透装置を用いたフローシートを第１図に示
す。この装置による洗浄廃液の処理は廃液タンク
１から出た洗浄廃液を循環タンク２に受入れ後逆
浸透装置３へ送られ浸透膜により放出可能な透過
水４と濃縮水５に分離される。濃縮水５は再び循
環タンク２に戻され、又系外へ放出した透過水４
の量だけ新たに循環タンク２へ廃液タンク１から
洗浄廃液が送られ徐々に濃縮、減容化される。一
定量の洗浄廃液を処理した後濃縮液は固化装置６
へ送られ固化される。
また廃液蒸発装置を用いたフローシートを第２
図に示す。この装置による洗浄廃液の処理は廃液
タンク１′から出た洗浄廃液を蒸発器本体２′に導
入した後、蒸発器本体２′より加熱器３′へ送り加
熱し蒸発器本体２′へ戻し蒸発により濃縮、減容
する。しかる後、減容、濃縮された液はライン
４′から固化装置５′へ送られ固化される。蒸発器
本体２′からライン６′に取り出された蒸発成分は
系外へ放出する。
以上の逆浸透装置および廃液蒸発装置にて濃
縮、減容化した場合、本発明による洗剤の成分組
成はリンを含まない無リン洗剤であつて、放出水
（第１図ではライン４、第２図ではライン６′）中
にはチツ素やリンが含まれず、プランクトン等の
栄養源となるものはない。又逆浸透装置あるいは
廃液蒸発装置にて減容化した濃縮液は主成分が硫
酸カリウム、炭酸カリウムであり、これらは
K2SO4、K2CO3又はK2CO3・1.5H2Oで表わされ
るように殆ど結晶水（nH2O）を持たない。その
ため固化処理実施後経過しても膨潤が起こらず放
射性廃棄物の最終処分用固化体として非常に適し
たものである。
以下、実施例により本発明を更に詳細に説明す
る。尚、実施例に用いた洗剤の組成を表−１にま
とめて示す。配合番号及びは比較のための非
イオン界面活性剤のみからなるものである。[Table] Specific gravity Specific gravity
2.533 1.440
As a result, when solidified with asphalt or concrete, the asphalt or concrete solidified product is subjected to extremely strong pressure due to this tremendous volume increase rate, and easily collapses.
This has the disadvantage that when the solidified material collapses, the solidified radioactive contaminants also leak out and escape, which is an extremely undesirable result. The present inventors have arrived at the present invention as a result of intensive research to find an excellent cleaning agent that solves the various problems related to radioactive contaminants and cleaning as described above, and a method for treating the cleaning waste liquid of the cleaning agent. . That is, the present invention relates to the following general formula (1) or (2) 0.5 to 20% by weight of a nonionic surfactant represented by the formula or a mixture thereof and potassium sulfate or (and)
A detergent for removing radioactive contamination characterized by containing 80 to 95.5% by weight of potassium carbonate as an essential component, and reducing the volume of detergent waste liquid from such a detergent by reverse osmosis or heating concentration, and solidifying it with asphalt. The present invention provides a method for treating cleaning waste liquid of a detergent for removing radioactive contamination. The cleaning agent of the present invention has low foaming properties, does not leak salts during the high-temperature evaporation concentration step for concentration and volume reduction, or the reverse osmosis treatment process, and even when the volume reduction cleaning agent is fixed with asphalt. Unlike conventional builders, the asphalt does not take in a lot of crystal water and generate strong crystal pressure, so asphalt does not disintegrate in water and can be stored stably and firmly. Potassium sulfate (K 2 SO 4 ) ionizes to 2K + +SO 2- 4 without having crystal water, and dissolves and diffuses.
Furthermore, potassium carbonate (K 2 SO 3 ) has extremely strong deliquescent properties and high solubility, and is ionized and dissolved in 2K + +CO 2- 3 . It does not form strong crystals that incorporate water of crystallization like sodium sulfates and carbonates. Therefore, it was found that the solidified asphalt and concrete did not collapse because no volume increase occurred. The detergent of the present invention has better cleaning properties against not only radioactive substances but also dirt and oil stains on clothes than conventional commercial detergents and detergents containing nonionic surfactants or sodium polyphosphate. However, it is a low-foaming cleaning agent that allows the cleaning waste liquid to be easily concentrated by direct heating or by reverse osmosis, making it extremely useful. The cleaning waste liquid that has been cleaned using the detergent of the present invention, that is, the cleaning waste liquid that contains radioactivity generated from facilities handling radioactive materials and nuclear power plants, is concentrated and reduced in volume using a reverse osmosis device or a waste liquid evaporation device. The final concentrated water is solidified using a fixing device such as asphalt that evaporates water. A flow sheet using a reverse osmosis device is shown in Figure 1. In the treatment of cleaning waste liquid by this device, the cleaning waste liquid discharged from a waste liquid tank 1 is received in a circulation tank 2, and then sent to a reverse osmosis device 3, where it is separated by an osmotic membrane into permeated water 4 and concentrated water 5, which can be released. The concentrated water 5 is returned to the circulation tank 2 again, and the permeated water 4 released outside the system is
A new amount of cleaning waste liquid is sent from the waste liquid tank 1 to the circulation tank 2, where it is gradually concentrated and reduced in volume. After processing a certain amount of cleaning waste liquid, the concentrated liquid is sent to the solidification device 6.
sent to and solidified. In addition, a second flow sheet using a waste liquid evaporator was developed.
As shown in the figure. Processing of cleaning waste liquid by this device is to introduce the cleaning waste liquid from the waste liquid tank 1' into the evaporator body 2', send it from the evaporator body 2' to the heater 3', heat it, and return it to the evaporator body 2' for evaporation. Concentrate and reduce volume. Thereafter, the volume-reduced and concentrated liquid is sent from line 4' to solidification device 5' and solidified. The evaporated components taken out from the evaporator body 2' to the line 6' are discharged to the outside of the system. When concentrated and reduced in volume using the reverse osmosis device and waste liquid evaporation device described above, the component composition of the detergent according to the present invention is a phosphorus-free detergent that does not contain phosphorus, and the discharged water (line 4 and 2 in FIG. In the figure, line 6') does not contain nitrogen or phosphorus, and there is nothing that can serve as a nutrient source for plankton or the like. In addition, the main components of the concentrated liquid reduced in volume using reverse osmosis equipment or waste liquid evaporation equipment are potassium sulfate and potassium carbonate, which are
It has almost no water of crystallization (nH 2 O) as expressed by K 2 SO 4 , K 2 CO 3 or K 2 CO 3 ·1.5H 2 O. Therefore, it does not swell even after the solidification process has been carried out, making it very suitable as a solidified material for final disposal of radioactive waste. Hereinafter, the present invention will be explained in more detail with reference to Examples. The compositions of the detergents used in the Examples are summarized in Table 1. Formulation numbers and numbers consist only of nonionic surfactants for comparison.
【表】【table】
【表】
実施例 １
本発明洗剤の洗浄力と起泡性について試験を行
なつた結果を表−２に示す。尚洗浄力試験と起泡
力試験は次に示す方法で行なつた。
＜洗浄力試験＞
酸化第二鉄、ベントナイト、カーボンブラツ
ク、脱水ラノリン等を用い、乾式で汚染した反射
率30％の汚染布を用いて、40℃においてターゴト
メーターによつて常法通り洗浄を行ない次の洗浄
率算出式によつて洗浄率を算出した。
洗浄率＝洗浄した汚染布の反射率−未洗浄汚染布
の反射率／元の白布の反射率−洗浄前な汚染布の反射率
×100
＜起泡力試験＞
Ross−Miles法によつて、常法通り発泡性を測
定した。[Table] Example 1 Table 2 shows the results of testing the detergency and foaming properties of the detergent of the present invention. The cleaning power test and the foaming power test were conducted using the following methods. <Cleaning power test> Using ferric oxide, bentonite, carbon black, dehydrated lanolin, etc., dry-contaminated cloth with a reflectance of 30% was cleaned in the usual manner using a tergotometer at 40°C. The cleaning rate was calculated using the following cleaning rate calculation formula. Cleaning rate = reflectance of washed contaminated cloth - reflectance of unwashed contaminated cloth / reflectance of original white cloth - reflectance of contaminated cloth before cleaning x 100 <Foaming power test> By Ross-Miles method, Foaming properties were measured in a conventional manner.
【表】【table】
【表】
実施例 ２
実施例１の方法に準じて洗浄を行なつた洗浄廃
液を第１図に示した逆浸透法によつて減容化を行
なつた。
その諸元と結果を表−３に示す。
表−３に示すように濃縮進行にともなう濃度上
昇による透過水量の減少は見られるがスケール析
出等による急激な減少は見られず濃縮処理が可能
であり、又、従来品に比べ低下度も小さく良好で
あることがわかる。
透過水量比＝各濃縮比での透過水量／濃縮比１で
の透過水量[Table] Example 2 The washing waste liquid obtained by washing according to the method of Example 1 was reduced in volume by the reverse osmosis method shown in FIG. The specifications and results are shown in Table 3. As shown in Table 3, there is a decrease in the amount of permeated water due to an increase in concentration as the concentration progresses, but there is no rapid decrease due to scale precipitation, etc., and concentration treatment is possible, and the degree of decrease is smaller than with conventional products. It can be seen that it is in good condition. Permeated water amount ratio = permeated water amount at each concentration ratio / permeated water amount at concentration ratio 1
【表】【table】
【表】
実施例 ３
濃縮減容を行なつた洗浄剤廃液は、アスフアル
ト固化を行ない、アスフアルトの凝集力、および
付着力をタフネスとテナシテイ試験で評価した。
試験に用いたアスフアルトは、針入度60〜80の
ものを用いてアスフアルト92部、洗浄剤濃縮液８
部の混合物を軟化点より少し高い温度の82℃に加
熱し、約50ｇの溶融試料を測定カツプにとり、こ
れに一定の大きさの金属半球を球面を下にして、
アスフアルト中に埋め60〜90分空冷し、後25℃の
水槽中に48時間放置した後、引つ張り速度30cm／
minで、25℃において、荷重一曲線を測定する。
この測定によつてアスフアルトの把握力（タフネ
ス）と粘結力（テナシテイ）を比較した。本発明
の洗浄剤廃液は結晶水を取り込み結晶が容積増大
する従来品に比べて、タフネスとテナシテイが、
アスフアルト単独の場合の値に近く、アスフアル
トを崩壊させていないことがわかる。結果は表−
４に示す。[Table] Example 3 The cleaning agent waste liquid that had been concentrated and reduced in volume was solidified with asphalt, and the cohesive force and adhesive force of asphalt were evaluated by toughness and tenacity tests. The asphalt used in the test had a penetration rate of 60 to 80, and contained 92 parts of asphalt and 8 parts of detergent concentrate.
Heat the mixture to 82°C, a temperature slightly higher than the softening point, take about 50g of the molten sample into a measuring cup, place a metal hemisphere of a certain size on it with the spherical side facing down,
It was buried in asphalt and air-cooled for 60 to 90 minutes, then left in a water tank at 25℃ for 48 hours, and then pulled at a pulling speed of 30cm/
Measure the load curve at 25°C at min.
Through this measurement, the gripping force (toughness) and cohesive force (tenacity) of asphalt were compared. The detergent waste liquid of the present invention has higher toughness and tenacity than conventional products in which crystal water is taken in and crystals increase in volume.
It can be seen that the value is close to that of asphalt alone, indicating that asphalt is not destroyed. The results are in the table-
4.
第１図は逆浸透装置による洗浄廃液処理方法を
示すフローシート、第２図は廃液蒸発装置による
洗浄廃液処理方法を示すフローシートである。
FIG. 1 is a flow sheet showing a cleaning waste liquid treatment method using a reverse osmosis device, and FIG. 2 is a flow sheet showing a cleaning waste liquid treatment method using a waste liquid evaporation device.
Claims (1)
合物0.5〜20重量％と硫酸カリウム又は（及び）
炭酸カリウム80〜95.5重量％とを必須成分として
含有することを特徴とする放射能汚染除去用洗
剤。[Claims] 1. The following general formula (1) or (2) 0.5 to 20% by weight of a nonionic surfactant represented by the formula or a mixture thereof and potassium sulfate or (and)
A detergent for removing radioactive contamination, characterized by containing 80 to 95.5% by weight of potassium carbonate as an essential component.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP5000583A JPS59174800A (en) | 1983-03-25 | 1983-03-25 | Detergent for removing radioactive pollution and processing of waste liquid purified |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP5000583A JPS59174800A (en) | 1983-03-25 | 1983-03-25 | Detergent for removing radioactive pollution and processing of waste liquid purified |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS59174800A JPS59174800A (en) | 1984-10-03 |
| JPH0223840B2 true JPH0223840B2 (en) | 1990-05-25 |
Family
ID=12846879
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP5000583A Granted JPS59174800A (en) | 1983-03-25 | 1983-03-25 | Detergent for removing radioactive pollution and processing of waste liquid purified |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS59174800A (en) |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE59204525D1 (en) * | 1991-09-26 | 1996-01-11 | Klaus Dr Bous | CLEANING LIQUID, ESPECIALLY FOR EMERGENCY SETS, AND THEIR USE. |
| JP2001021687A (en) * | 1999-07-02 | 2001-01-26 | Ebara Kogyo Senjo Kk | Method for treating radioactive contaminant and device used for this method |
| US6605158B1 (en) * | 2001-10-12 | 2003-08-12 | Bobolink, Inc. | Radioactive decontamination and translocation method |
Family Cites Families (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5321399A (en) * | 1976-08-11 | 1978-02-27 | Mitsubishi Heavy Ind Ltd | Detergent for removing radioactive contamination and its washed water liquid treating method |
| JPS55112600A (en) * | 1979-02-23 | 1980-08-30 | Ebara Mfg | Method of stopping operation of asphalt solidification |
-
1983
- 1983-03-25 JP JP5000583A patent/JPS59174800A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS59174800A (en) | 1984-10-03 |
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