JPS639899A - Radioactive waste-liquor processor - Google Patents
Radioactive waste-liquor processorInfo
- Publication number
- JPS639899A JPS639899A JP15386386A JP15386386A JPS639899A JP S639899 A JPS639899 A JP S639899A JP 15386386 A JP15386386 A JP 15386386A JP 15386386 A JP15386386 A JP 15386386A JP S639899 A JPS639899 A JP S639899A
- Authority
- JP
- Japan
- Prior art keywords
- waste liquid
- radioactive waste
- radioactive
- dryer
- assimilation
- 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
- 230000002285 radioactive effect Effects 0.000 title claims description 10
- 239000007788 liquid Substances 0.000 claims description 47
- 239000002901 radioactive waste Substances 0.000 claims description 31
- 239000000463 material Substances 0.000 claims description 18
- 239000002699 waste material Substances 0.000 claims description 15
- 238000002156 mixing Methods 0.000 claims description 12
- 239000004033 plastic Substances 0.000 claims description 12
- 239000000843 powder Substances 0.000 claims description 11
- CBENFWSGALASAD-UHFFFAOYSA-N Ozone Chemical compound [O-][O+]=O CBENFWSGALASAD-UHFFFAOYSA-N 0.000 claims description 10
- 239000000126 substance Substances 0.000 claims description 10
- 239000007789 gas Substances 0.000 claims description 9
- 239000007800 oxidant agent Substances 0.000 claims description 5
- 239000003795 chemical substances by application Substances 0.000 claims description 4
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 claims description 2
- 239000001301 oxygen Substances 0.000 claims description 2
- 229910052760 oxygen Inorganic materials 0.000 claims description 2
- 238000012545 processing Methods 0.000 claims description 2
- 239000003999 initiator Substances 0.000 description 11
- 230000001603 reducing effect Effects 0.000 description 8
- 238000007711 solidification Methods 0.000 description 8
- 230000008023 solidification Effects 0.000 description 8
- 238000000034 method Methods 0.000 description 5
- 150000001451 organic peroxides Chemical class 0.000 description 5
- 239000003638 chemical reducing agent Substances 0.000 description 4
- 238000001035 drying Methods 0.000 description 3
- 239000012857 radioactive material Substances 0.000 description 3
- PPBRXRYQALVLMV-UHFFFAOYSA-N Styrene Chemical compound C=CC1=CC=CC=C1 PPBRXRYQALVLMV-UHFFFAOYSA-N 0.000 description 2
- 239000000203 mixture Substances 0.000 description 2
- 239000010409 thin film Substances 0.000 description 2
- 241000196324 Embryophyta Species 0.000 description 1
- -1 F 62 + Substances 0.000 description 1
- 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
- 244000017020 Ipomoea batatas Species 0.000 description 1
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 description 1
- 230000015572 biosynthetic process Effects 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 230000005587 bubbling Effects 0.000 description 1
- 239000000498 cooling water Substances 0.000 description 1
- 238000000354 decomposition reaction Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000012530 fluid Substances 0.000 description 1
- 239000002440 industrial waste Substances 0.000 description 1
- 230000007935 neutral effect Effects 0.000 description 1
- 229910017604 nitric acid Inorganic materials 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 230000003647 oxidation Effects 0.000 description 1
- 238000007254 oxidation reaction Methods 0.000 description 1
- 238000012958 reprocessing Methods 0.000 description 1
- 229920005989 resin Polymers 0.000 description 1
- 239000011347 resin Substances 0.000 description 1
- 230000035939 shock Effects 0.000 description 1
- 229910052708 sodium Inorganic materials 0.000 description 1
- 239000011734 sodium Substances 0.000 description 1
- 239000007787 solid Substances 0.000 description 1
- 229920006337 unsaturated polyester resin Polymers 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
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）
本発明は原子力発電所等の放射性物質取扱い施設におい
て発生する放射性廃液を処理する放射性廃液処理装置に
係り、特に放射性廃液を乾燥処理した後プラスチック固
化処理する方法に用いる放射性廃液処理装置に関する。[Detailed Description of the Invention] [Object of the Invention] (Industrial Field of Application) The present invention relates to a radioactive waste liquid treatment device for treating radioactive waste liquid generated in facilities handling radioactive materials such as nuclear power plants, and in particular, to The present invention relates to a radioactive waste liquid treatment device used in a method of drying and then solidifying plastic.
（従来の技術）
一般に沸騰水型原子力発電所、核燃料再処理工場等の放
射性物質取扱い施設で発生する放射性廃液は、濶縮乾燥
され主としてばｔ酸ナトリウムや硝酸す１・１戸りムか
らなる粉体とされた後同化材により固化される。(Prior art) Generally, radioactive waste liquid generated in facilities handling radioactive materials such as boiling water nuclear power plants and nuclear fuel reprocessing plants is dried by drying and consists mainly of sodium batate and nitric acid. After being turned into a powder, it is solidified using an assimilating agent.
この同化処理方法としては、硬化性プラスデックからな
る同化Ｈにより同化処理を行うプラスチック同化処理方
法が、軽■で機械的衝撃に強い固化体パッケージが得ら
れるところから近時有望視されている。As this assimilation treatment method, a plastic assimilation treatment method in which assimilation is performed using assimilation H made of hardenable plus deck has recently been viewed as promising because it provides a solidified package that is lightweight and resistant to mechanical shock.
このプラスチック同化処理方法に用いる装置は、放射性
廃液を貯蔵する廃液貯蔵タンクと、放射性廃液を放射性
粉体とする竪型薄膜乾燥機等の乾燥機と、この放射性粉
体とプラスチック同化材とを混合する混合装置とを備え
ている。そして廃液貯蔵タンクから送られた放射性廃液
は、乾燥機にて放射性粉体とされた後混合装置内に移送
され、この放射性粉体は混合装置内にて硬化性プラスチ
ック固化材と混合され、この混合物がドラム缶等の容器
内に充填されて一体に固化され固化体パッケージに形成
される。The equipment used in this plastic assimilation treatment method consists of a waste liquid storage tank that stores radioactive waste liquid, a dryer such as a vertical thin film dryer that converts the radioactive waste liquid into radioactive powder, and a mixer that mixes this radioactive powder with a plastic assimilation material. It is equipped with a mixing device. The radioactive waste liquid sent from the waste liquid storage tank is turned into radioactive powder in a dryer and then transferred to a mixing device.This radioactive powder is mixed with a curable plastic solidifying material in the mixing device. The mixture is filled into a container such as a drum and solidified into a solid package.
プラスチック同化材としてはスチレンで希釈した不飽和
ポリエステル樹脂等が用いられ、有機過酸化物を同化開
始剤として使用し、同化材を重合固化させる方法が一般
的に採用されている。An unsaturated polyester resin diluted with styrene is used as the plastic assimilation material, and a method is generally employed in which the assimilation material is polymerized and solidified using an organic peroxide as an assimilation initiator.
（発明が解決しようとする問題点）
しかし敢ｑ旧生廃液中に還元性物質、例えば、Ｆｅ２＋
、Ｃｕ＋、５Ｏ３２−１ＮＯ２−等が多Ｈに含まれてい
ると、これらの還元性物質が有機過酸化物等の固化開始
剤の分解により生じたラジカルを消費して同化開始剤と
しての効力を失わせるため、固化材の硬化が妨害され、
形成された固化体パッケージの硬度が低く、従って同化
体パッケージの機械的強度や安定性が低くなるという問
題があった。(Problem to be solved by the invention) However, reducing substances such as Fe2+ are present in the old waste liquid.
, Cu+, 5O32-1NO2-, etc., are contained in poly-H, these reducing substances consume radicals generated by the decomposition of solidification initiators such as organic peroxides, reducing their effectiveness as assimilation initiators. hardening of the solidifying agent is hindered,
There is a problem in that the hardness of the formed solidified package is low, and therefore the mechanical strength and stability of the assimilated package are low.
本発明は、このような従来の問題に対処するためになさ
れたもので、放射性廃液中の還元性物質により同化材の
硬化が妨げられることなく、機械的強度、安定性を向上
さぜｆこ固化体パッケージを形成する放射性廃液処理装
置を提供することを目的とする。The present invention was made to address these conventional problems, and improves the mechanical strength and stability of the assimilated material without hindering the curing of the assimilated material by reducing substances in radioactive waste fluid. An object of the present invention is to provide a radioactive waste liquid treatment device that forms a solidified package.
［発明の構成］
（問題点を解決するための手段〉
本発明の放射性廃液処理装置は、放射性廃液を貯蔵する
廃液貯蔵タンクと、この廃液貯蔵タンクから送られた放
射性廃液を乾燥して放射性粉体とする乾燥機と、この乾
燥機から送られた前記放射性粉体と硬化性プラスチック
材料とを混合する混合装置とを備えた放射性廃液処理装
置において、前記乾燥機内にオゾン含有気体又はＨ２Ｏ
２を供給する酸化剤供給装置を配設したものである。[Structure of the Invention] (Means for Solving the Problems) The radioactive waste liquid processing apparatus of the present invention includes a waste liquid storage tank for storing radioactive waste liquid, and a radioactive waste liquid sent from the waste liquid storage tank that is dried to form radioactive powder. A radioactive waste liquid treatment apparatus equipped with a dryer as a dryer and a mixing device for mixing the radioactive powder sent from the dryer with a curable plastic material.
This system is equipped with an oxidizing agent supply device that supplies oxidizing agent 2.
（作用）
本発明の放射性廃液処理装置において、乾燥機内にオゾ
ン含有気体又はＨ２０２の酸化剤が供給されることによ
って、放射性廃液中の還元性物質は酸化されて還元性を
失い、有機過酸化物等の固化開始剤と反応しなくなる。(Function) In the radioactive waste liquid treatment apparatus of the present invention, by supplying an ozone-containing gas or an oxidizing agent such as H202 into the dryer, the reducing substance in the radioactive waste liquid is oxidized and loses its reducibility, and organic peroxides are formed. It does not react with solidification initiators such as.
従って同化開始剤の効力が失われないため固化体パッケ
ージ形成時に固化材の硬化が妨害されることがなく、機
械的強度、安定性を向上させた同化体パッケージを形成
することかできる。Therefore, since the effectiveness of the assimilation initiator is not lost, the curing of the solidifying material is not hindered during the formation of the solidified package, making it possible to form an assimilated package with improved mechanical strength and stability.
（実施例） 次に本発明の実施例について説明する。(Example) Next, examples of the present invention will be described.
本発明の実施例の放射性廃液処理装置は図に示す構成と
なっている。A radioactive waste liquid treatment apparatus according to an embodiment of the present invention has a configuration shown in the figure.
原子力発電所等で発生した成用性廃液は、廃液貯蔵タン
ク１に一旦貯留された後、給液ポンプ２により例えば竪
型薄膜乾燥機等の乾燥機３に導かれる。またｔＪＩｌ躬
性廃液性廃液中性物質を検出するために、廃液貯蔵タン
ク１と給液ポンプ２との間にＣＯＤ （化学的酸素要求
足）検出器４が配設されている。そしてＣＯＤ検出器４
により還元性物質が検出されると、オゾン含有気体タン
ク５からその還元性物質を酸化するために必要である量
よりやや過剰のオゾン含有気体が、オゾン含有気体移送
ポンプ６により乾燥機３内に供給される。A commercial waste liquid generated at a nuclear power plant or the like is once stored in a waste liquid storage tank 1 and then guided by a liquid supply pump 2 to a dryer 3 such as a vertical thin film dryer. In addition, a COD (chemical oxygen demand) detector 4 is disposed between the waste liquid storage tank 1 and the liquid supply pump 2 in order to detect neutral substances in the waste liquid. and COD detector 4
When a reducing substance is detected, an ozone-containing gas slightly in excess of the amount required to oxidize the reducing substance from the ozone-containing gas tank 5 is transferred into the dryer 3 by an ozone-containing gas transfer pump 6. Supplied.
乾燥機３で乾燥され粉体化された放射性物質は一旦粉体
貯蔵タンク７に貯蔵されある一定量溜まったところで混
合装置８内に送られる。そしてプラスチックタンク９、
同化開始剤タンク１０、同化促進剤ランク１１から、移
送ポンプ１２．１３．１４によりプラスチック同化材、
固化開始剤、固化促進剤が混合装置８内に送り込まれて
上記の放射性粉体と混合される。そして隈拌機１５によ
って充分混合されたこの混合物は、ドラム缶１６に収容
され同化体パッケージに形成される。The radioactive material dried and powdered in the dryer 3 is temporarily stored in a powder storage tank 7, and when a certain amount has accumulated, it is sent into a mixing device 8. and plastic tank 9,
Assimilation initiator tank 10, assimilation promoter rank 11, plastic assimilate material by transfer pump 12.13.14;
A solidification initiator and a solidification accelerator are fed into the mixing device 8 and mixed with the radioactive powder. This mixture, thoroughly mixed by the stirrer 15, is placed in a drum 16 and formed into an assimilate package.
プラスチック同化材としては、例えば不飽和ポリニスデ
ル樹脂、同化開始剤としては例えば有機過酸化物が使用
可能である。As the plastic assimilation agent, for example, an unsaturated polynisderian resin can be used, and as the assimilation initiator, for example, an organic peroxide can be used.
図中、１７．１８は流量計、１９はモータ、２０は冷却
水、２１はコンデンサ、２２は丈ンプルタンク、２３は
排気装置、２４．２５は排気口である。In the figure, 17 and 18 are flowmeters, 19 are motors, 20 are cooling water, 21 are condensers, 22 are long pull tanks, 23 are exhaust devices, and 24.25 are exhaust ports.
このように構成された放射性廃液処理装置を使用するに
あたり、Ｎａ２ｓＯ＋を２０ｗｔ％含み、固止材の硬化
妨害物質としてＮａ２ＮＯ２が２０００ｐｐｍ存在する
溶液を模擬廃液として用いて、実施例の装置により乾燥
処理、固化処理を行なった。When using the radioactive waste liquid treatment apparatus configured as described above, a solution containing 20 wt% Na2SO+ and 2000 ppm of Na2NO2 as a substance that interferes with curing of the fixing material was used as a simulated waste liquid, and was dried by the apparatus of the example. Solidification treatment was performed.
このとき模擬廃液−ｍ、ｃに対して、４０’Ｃの温度に
てオゾン含有気体（オゾン含母 ％）をバブリングに
より１ｉＱ／ｍｉｎで３０分間接触させることにより酸
化処理を行なった。これとは別に比較のため上記の模擬
廃液に従来の放射性廃液処理装置を用いて乾燥処理、同
化処理を行なった。尚このとき用いた同化材、固化開始
剤、同化促進剤およびこの結果、実施例の装置を用いて
形成した同化体は硬化が完全で必り、固化体の一軸圧縮
強度は８００Ｋ（］／ｃＪで機械的強度が良好であった
。一方従来の装置を用いて形成した固化体は硬化が不完
全であった。At this time, the simulated waste liquids-m and c were subjected to oxidation treatment by contacting them with an ozone-containing gas (ozone content %) at a temperature of 40'C for 30 minutes at 1 iQ/min by bubbling. Separately, for comparison, the above simulated waste liquid was subjected to drying and assimilation using a conventional radioactive waste liquid treatment device. It should be noted that the assimilated material, solidification initiator, and assimilation promoter used at this time, and as a result, the assimilated material formed using the apparatus of the example were completely cured, and the unconfined compressive strength of the solidified material was 800 K (]/cJ. On the other hand, the solidified material formed using the conventional equipment was incompletely cured.
この結果かられかるように、実施例においてオゾン含有
気体が乾燥機３内に吹き込まれることにより放射性廃液
中の還元性物質、例えばＦ ６２ ＋、Ｃｕ÷、５０３
２″″、ＮＯ２−等は酸化されて、Ｆｅ３＋、Ｃｕ２＋
、５Ｏ４２−１ＮＯ３−等になる。そのため上記の還元
性物質は還元性を失い有機過酸化物などの固化開始剤と
反応しなくなるので、固化開始剤の効力は失なわれず、
同化材の硬化が妨害されない。As can be seen from this result, in the example, ozone-containing gas is blown into the dryer 3 to reduce reducing substances in the radioactive waste liquid, such as F 62 +, Cu÷, 503
2″″, NO2−, etc. are oxidized to Fe3+, Cu2+
, 5O42-1NO3-, etc. Therefore, the above-mentioned reducing substance loses its reducing property and stops reacting with the solidification initiator such as organic peroxide, so the effectiveness of the solidification initiator is not lost.
Hardening of the assimilated material is not hindered.
従つ゛にの放射性廃液処理装置を用いれば、還元性物質
が存在する放射性廃液を、機械的強度、安定性を向上さ
せた固化体パッケージとして９８埋することができる。Accordingly, by using the radioactive waste liquid treatment apparatus, radioactive waste liquid containing reducing substances can be buried as a solidified package with improved mechanical strength and stability.
尚実施例では酸化剤としてオゾン含有気体を用いたが、
Ｈ２Ｏ２を用いてもよい。この場合Ｈ２Ｏ２は放射性廃
液を乾燥機内に移送するための供給管内に導入される。Although ozone-containing gas was used as the oxidizing agent in the examples,
H2O2 may also be used. In this case, H2O2 is introduced into the supply pipe for transporting the radioactive waste liquid into the dryer.
［発明の効果］
以上説明したように、本発明の放射性廃液処理装置を用
いれば、放射性廃液中の還元性物質によって同化材の硬
化が妨害されることかなく、放射性廃液を機械的強度、
安定性を向上させた固化体としてＬｌ即することができ
る。[Effects of the Invention] As explained above, if the radioactive waste liquid treatment device of the present invention is used, the curing of the assimilation material will not be hindered by the reducing substances in the radioactive waste liquid, and the radioactive waste liquid will be improved in mechanical strength,
It can be used as a solidified product with improved stability.
図は、本発明の実施例の放射性廃液処理装置の配管系統
図である。
１・・・・・・・・・廃液貯蔵タンク
訃・・・・・・・・乾燥機
４・・・・・・・・・ＣＯＤ検出器
５・・・・・・・・・オゾン含有気体タンク７・・・・
・・・・・勿体貯蔵タンク
８・・・・・・・・・混合装置The figure is a piping system diagram of a radioactive waste liquid treatment apparatus according to an embodiment of the present invention. 1...... Waste liquid storage tank... Dryer 4... COD detector 5... Ozone-containing gas Tank 7...
...Mattai storage tank 8...Mixing device
Claims (2)
液貯蔵タンクから送られた放射性廃液を乾燥して放射性
粉体とする乾燥機と、この乾燥機から送られた前記放射
性粉体と硬化性プラスチック材料とを混合する混合装置
とを備えた放射性廃液処理装置において、前記乾燥機内
にオゾン含有気体又はＨ＿２Ｏ＿２を供給する酸化剤供
給装置を配設したことを特徴とする放射性廃液処理装置
。(1) A waste liquid storage tank that stores radioactive waste liquid, a dryer that dries the radioactive waste liquid sent from the waste liquid storage tank to turn it into radioactive powder, and a curing agent for the radioactive powder sent from this dryer. What is claimed is: 1. A radioactive waste liquid processing apparatus comprising a mixing device for mixing a plastic material and a mixing device for mixing with a plastic material, characterized in that an oxidizing agent supply device for supplying ozone-containing gas or H_2O_2 is disposed in the dryer.
化学的酸素要求量を測定する検出器が設置されているこ
とを特徴とする特許請求の範囲第１項記載の放射性廃液
処理装置。(2) A radioactive waste liquid treatment apparatus according to claim 1, characterized in that a detector for measuring the chemical oxygen demand of the radioactive waste liquid is installed between the waste liquid storage tank and the dryer. .
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP15386386A JPS639899A (en) | 1986-06-30 | 1986-06-30 | Radioactive waste-liquor processor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP15386386A JPS639899A (en) | 1986-06-30 | 1986-06-30 | Radioactive waste-liquor processor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS639899A true JPS639899A (en) | 1988-01-16 |
Family
ID=15571749
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP15386386A Pending JPS639899A (en) | 1986-06-30 | 1986-06-30 | Radioactive waste-liquor processor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS639899A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6382399A (en) * | 1986-09-26 | 1988-04-13 | 日揮株式会社 | Method of processing radioactive waste liquor |
-
1986
- 1986-06-30 JP JP15386386A patent/JPS639899A/en active Pending
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6382399A (en) * | 1986-09-26 | 1988-04-13 | 日揮株式会社 | Method of processing radioactive waste liquor |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| AU572510B2 (en) | Treating contaminated insoluble organic solid material | |
| US4086325A (en) | Process for drying solutions containing boric acid | |
| US4628837A (en) | Method and apparatus for processing spent ion exchange resin | |
| JPS61104299A (en) | Method of disposing radioactive decontaminated waste liquor | |
| JP2978542B2 (en) | Method and apparatus for concentrating dissolved and solid radioactive materials | |
| JPS639899A (en) | Radioactive waste-liquor processor | |
| JPS62291599A (en) | Radioactive waste liquor processor | |
| US3721624A (en) | Process for treating waste effluent | |
| WO1992003829A1 (en) | Organic material oxidation process utilizing no added catalyst | |
| US5419840A (en) | Effluent treatment | |
| JPH02222798A (en) | Pretreatment of sludge | |
| JPS5535976A (en) | Treatment of waste water containing oxidizable substance | |
| JPS6382399A (en) | Method of processing radioactive waste liquor | |
| JP2003236569A (en) | Method of hydrothermal oxidation reaction | |
| Hawash et al. | Study of ozonation reaction in phenolic effluents | |
| JPS6061697A (en) | Method of decomposig and treating radioactive liquid organic waste | |
| JPS61258199A (en) | Method of processing radioactive solid waste | |
| JPS58170591A (en) | Purification of waste water contg. organic substance | |
| JPH01119386A (en) | Treatment of chemical washing waste liquid and equipment therefor | |
| JPH01317599A (en) | Treatment of organic sludge | |
| JPS60105997A (en) | Method of decomposing radioactive waste organic phosphoric acid esters | |
| JPS61270698A (en) | Cement solidifying method of radioactive waste liquor | |
| Nash | Review of Options for Ammonia/Ammonium Management | |
| CA1211413A (en) | Method of treating contaminated insoluble organic solid material | |
| JPH05273387A (en) | Resolving organic matter in radioactive waste liquid |