JPS629297A - Method of treating radioactive waste - Google Patents

Method of treating radioactive waste

Info

Publication number
JPS629297A
JPS629297A JP14817685A JP14817685A JPS629297A JP S629297 A JPS629297 A JP S629297A JP 14817685 A JP14817685 A JP 14817685A JP 14817685 A JP14817685 A JP 14817685A JP S629297 A JPS629297 A JP S629297A
Authority
JP
Japan
Prior art keywords
exhaust gas
heat exchanger
radioactive waste
air
cooled
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.)
Granted
Application number
JP14817685A
Other languages
Japanese (ja)
Other versions
JPH0558158B2 (en
Inventor
俊二 井上
高田 孝
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
NGK Insulators Ltd
Original Assignee
NGK Insulators Ltd
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by NGK Insulators Ltd filed Critical NGK Insulators Ltd
Priority to JP14817685A priority Critical patent/JPS629297A/en
Publication of JPS629297A publication Critical patent/JPS629297A/en
Publication of JPH0558158B2 publication Critical patent/JPH0558158B2/ja
Granted legal-status Critical Current

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  • Processing Of Solid Wastes (AREA)
  • Fertilizers (AREA)
  • Treatment Of Sludge (AREA)
  • Treating Waste Gases (AREA)
  • Gasification And Melting Of Waste (AREA)

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】 (産業上の利用分野) 本発明は、原子力発電所及び研究所等の放射性物質取扱
い施設において発生する可燃性雑固体廃棄物及び廃樹脂
等の放射性廃棄物の処理方法に関するものである。
Detailed Description of the Invention (Field of Industrial Application) The present invention relates to a method for treating radioactive waste such as flammable miscellaneous solid waste and waste resin generated in facilities handling radioactive materials such as nuclear power plants and research institutes. It is related to.

(従来の技術) 従来の放射性廃棄物の処理方法としては、第3図に示す
ように焼却炉51で燃焼した放射性廃棄物の燃焼ガスを
、1次セラミックフィルタ52および2次セラミックフ
ィルタ53よりなる除塵機で除塵した後、除塵後の50
0〜600℃の排ガスを約2倍量の空気混合により高性
能フィルタ54の耐熱温度である300℃以下にした後
、高性能フィルタ54で再除塵し、再除塵後の排ガスを
排ガスブロワ55で引いて大気中へ放出していた。
(Prior Art) As shown in FIG. 3, in the conventional radioactive waste processing method, the combustion gas of radioactive waste combusted in an incinerator 51 is filtered through a primary ceramic filter 52 and a secondary ceramic filter 53. After removing dust with a dust remover, 50% after removing dust
After reducing the exhaust gas at 0 to 600°C to below 300°C, which is the heat-resistant temperature of the high-performance filter 54, by mixing approximately twice the amount of air, the high-performance filter 54 removes dust again, and the exhaust gas after the re-dust removal is passed through the exhaust gas blower 55. It was then released into the atmosphere.

また、他の処理方法としては、第4図に示すように1次
セラミックフィルタ52および2次セラミックフィルタ
53よりなる除塵機で除塵された排ガスを水冷式熱交換
器56で冷却した後、高性能フィルタ54で再除塵し、
再除塵後の排ガスを更に洗浄塔51で洗浄して排ガスブ
ロワ55で引いて大気中へ放出していた。
In addition, as another treatment method, as shown in FIG. Dust is removed again using the filter 54,
The exhaust gas after the re-dedusting was further cleaned in a cleaning tower 51, pulled by an exhaust gas blower 55, and discharged into the atmosphere.

(発明が解決しようとする問題点) しかしながら、第3図に示した前者の場合は、空気を混
合して排ガスを冷却しているため排ガス量が約3倍とな
り、能力の大きな高性能フィルタ。
(Problem to be Solved by the Invention) However, in the former case shown in Fig. 3, the amount of exhaust gas is approximately tripled because the exhaust gas is cooled by mixing air, and a high-performance filter with a large capacity is required.

排ガスブロワ、煙道が必要となる欠点があった。It had the disadvantage of requiring an exhaust gas blower and flue.

また、高温乾式処理のため、ヨウ素、トリチウム等の揮
発性の放射性核種あるいはSOX 、NOX 。
In addition, due to the high-temperature dry process, volatile radionuclides such as iodine and tritium, SOX, and NOX are used.

HCJ2等の有害ガスが除去できない欠点もあった。There was also the drawback that harmful gases such as HCJ2 could not be removed.

−力筒4図に示した後者の場合は、水冷式熱交換器56
と洗浄塔57を使用しているため上述した欠点は解消で
きるが、冷却用水が多量に必要であるとともに、熱交換
器が金属製であり排ガス側の液と接する面に酸が凝縮し
て金属が腐食される欠点があった。また、洗浄塔出口以
後は60℃以下の低温となるため排ガス中の腐食性ガス
あるいはミストが凝縮して排気系統が腐食される欠点も
あった。
- In the latter case shown in Figure 4, a water-cooled heat exchanger 56
Although the above-mentioned disadvantages can be solved by using a cleaning tower 57, a large amount of cooling water is required, and the heat exchanger is made of metal, so acid condenses on the surface in contact with the liquid on the exhaust gas side, causing metal damage. The disadvantage was that it corroded. In addition, since the temperature after the outlet of the cleaning tower is as low as 60° C. or less, corrosive gas or mist in the exhaust gas condenses and corrodes the exhaust system.

本発明の目的は上述した不具合を解消して、排ガスの温
度を低下させて処理すべき排ガス量を増加させないと共
に、排ガスの冷却時に排ガスから冷媒空気へ熱交換され
た空気を利用して酸の結露すなわちその結果化じる排気
系の腐食等も有効に防止できる放射性廃棄物の処理方法
を提供しようとするものである。
The purpose of the present invention is to eliminate the above-mentioned problems, to lower the temperature of exhaust gas so as not to increase the amount of exhaust gas to be treated, and to reduce the amount of acid by using air heat exchanged from exhaust gas to refrigerant air when cooling exhaust gas. It is an object of the present invention to provide a method for disposing of radioactive waste that can effectively prevent dew condensation and the resulting corrosion of the exhaust system.

(問題点を解決するための手段) 本発明の放射性廃棄物の処理方法によれば、放射性物質
取扱施設において発生する可燃性雑固体廃棄物、廃樹脂
等の放射性廃棄物を焼却炉で焼却して焼却灰とするとと
もに、前記焼却炉の燃焼排ガスを除塵機で除塵し除塵し
た排ガスを空冷式熱交換器により冷却し、冷却した排ガ
スを高性能フィルタでさらに除塵しこの除塵した排ガス
を洗浄塔により洗浄した後、前記排ガスの冷却時に加熱
された空冷式熱交換器の熱風空気を洗浄後のガスと合流
させ、前記合流排ガスを共通の排風機により大気中へ放
出することを特徴とするものである。
(Means for solving the problem) According to the radioactive waste processing method of the present invention, radioactive waste such as flammable miscellaneous solid waste and waste resin generated in a radioactive material handling facility is incinerated in an incinerator. At the same time, the combustion exhaust gas from the incinerator is removed with a dust remover, the removed exhaust gas is cooled with an air-cooled heat exchanger, the cooled exhaust gas is further removed with a high-performance filter, and the removed exhaust gas is sent to a cleaning tower. After cleaning the exhaust gas, hot air from an air-cooled heat exchanger heated during cooling of the exhaust gas is combined with the cleaned gas, and the combined exhaust gas is discharged into the atmosphere by a common exhaust fan. It is.

(作 用) 上述した構成により、空冷式の熱交換器によって除塵機
で除塵した後の高温の排ガスを冷Wして排ガス量を増加
させることなく高性能フィルタを使用できる温度に、す
ると共に、高温の排ガスから冷媒空気へ熱交換すること
により加熱された空気を使用して洗浄後の低温の排ガス
を再昇温することにより、排ガス中の腐食性ガスあるい
はミストが凝縮することがなく排気系統が腐食されるこ
ともない。
(Function) With the above-mentioned configuration, the air-cooled heat exchanger cools the high-temperature exhaust gas after dust removal with the dust remover to a temperature at which a high-performance filter can be used without increasing the amount of exhaust gas, and By exchanging heat from high-temperature exhaust gas to refrigerant air and using the heated air to re-heat the low-temperature exhaust gas after cleaning, the exhaust system is prevented from condensing corrosive gases or mist in the exhaust gas. will not be corroded.

(実施例) 第1図は本発明の放射性廃棄物の処理方法を実施するシ
ステムの一例を示す線図である。廃HEPAフィルタ、
可燃性雑固体物質、廃樹脂、廃油等の放射性廃棄物は、
投入機1またはフィーダ2aならびにノズル2bにより
焼却炉3に供給され、焼却炉3において燃焼される。燃
焼された焼却灰は焼却灰取出コンベア4により搬送され
、ホッパ5を介して高周波溶融炉6に投入され、ガラス
・保温材とともに溶融した後廃棄している。燃焼ガスは
バーナ7を具えるセラミックフィルタ8を通ってろ過さ
れる。バーナ7はセラミックフィルタ8の内部で燃焼ガ
ス中の未燃カーボンを燃やすために使用する。セラミッ
クフィルタ8で発生する2次廃棄物は焼却灰と同様焼却
灰取出コンベア4により搬送され、ホッパ5を介して高
周波溶融炉6に投入され焼却灰と同様な方法で廃棄され
る。
(Example) FIG. 1 is a diagram showing an example of a system for implementing the radioactive waste treatment method of the present invention. waste HEPA filter,
Radioactive waste such as flammable miscellaneous solid materials, waste resin, waste oil, etc.
It is supplied to the incinerator 3 by the injector 1 or the feeder 2a and the nozzle 2b, and is burned in the incinerator 3. The burnt incineration ash is conveyed by the incineration ash removal conveyor 4, fed into the high frequency melting furnace 6 via the hopper 5, and is disposed of after being melted together with the glass and heat insulating material. The combustion gases are filtered through a ceramic filter 8 with a burner 7. The burner 7 is used to burn unburned carbon in the combustion gas inside the ceramic filter 8. The secondary waste generated by the ceramic filter 8 is conveyed by the incinerated ash removal conveyor 4 in the same way as incinerated ash, is fed into the high frequency melting furnace 6 via the hopper 5, and is disposed of in the same manner as incinerated ash.

セラミックフィルタ8でろ過された燃焼ガスは空冷式熱
交換器9において冷却空気と熱交換することにより冷却
され、約300℃程度まで冷却されたM焼ガスは高性能
フィルタ10に供給される。この熱交換器9は空冷式の
ものであればどのようなタイプのものでも使用できるが
、セラミック質直交流型の熱交換器を使用すると腐食の
心配もなく熱効率の点で好ましい。また、高温の燃焼ガ
スを冷却するのは高性能フィルタ10の耐熱温度が約3
00℃であることと、高性能フィルタ10で処理するガ
スの量を増加させないためである。さらに、高性能フィ
ルタ10の前段に粗い繊維素材等からなる粗フーイルタ
を設置することにより、高性能フィルタの目詰りに大き
く影響を与える粗粒子を除去して高性能フィルタ10の
寿命を長くすることもできる。
The combustion gas filtered by the ceramic filter 8 is cooled by exchanging heat with cooling air in the air-cooled heat exchanger 9, and the M sintered gas cooled to about 300° C. is supplied to the high-performance filter 10. Although any type of heat exchanger 9 can be used as long as it is an air-cooled type, it is preferable to use a ceramic cross-flow type heat exchanger from the viewpoint of thermal efficiency without fear of corrosion. In addition, the high-performance filter 10 has a heat resistance temperature of about 3 to cool the high-temperature combustion gas.
This is because the temperature is 00° C. and the amount of gas processed by the high-performance filter 10 is not increased. Furthermore, by installing a coarse filter made of coarse fiber material or the like in the front stage of the high-performance filter 10, the life of the high-performance filter 10 can be extended by removing coarse particles that greatly affect the clogging of the high-performance filter. You can also do it.

高性能フィルタ10を通過した低温の燃焼ガスは洗浄塔
11に供給される。洗浄塔11では、供給された燃焼ガ
スの温度を下げその蒸気圧を下げて凝縮させ水洗するこ
とにより、放射性ヨウ素等の揮発性核種及び塩化水素等
の腐食性ガスを可能な限り除去している。洗浄塔11を
通過した低温の燃焼ガスは、熱交換器9において燃焼ガ
スを冷却する際使用され加熱された空気と約1:1の割
合で混合して昇温される。これは、燃焼ガスを高温化す
ることにより従来生じがちであった排気系統の機器への
燃焼ガス中の腐食性ガスあるいはミストの凝縮による腐
食を防止するためである。昇温された燃焼ガスは排ガス
ブロワ12により吸引され、排気口13より排気される
。なお、本実施例では熱交換器9において冷却に使われ
た加熱空気を混合に際し排ガスブロワ12により吸引し
ているため、冷却用空気を熱交換器9へ供給する例えば
送気ブロワ等は不要となる。
The low-temperature combustion gas that has passed through the high-performance filter 10 is supplied to a cleaning tower 11 . In the cleaning tower 11, volatile nuclides such as radioactive iodine and corrosive gases such as hydrogen chloride are removed as much as possible by lowering the temperature of the supplied combustion gas, lowering its vapor pressure, condensing it, and washing it with water. . The low-temperature combustion gas that has passed through the cleaning tower 11 is mixed at a ratio of approximately 1:1 with heated air used to cool the combustion gas in the heat exchanger 9, and is heated. This is to prevent corrosion of equipment in the exhaust system due to condensation of corrosive gas or mist in the combustion gas, which conventionally tends to occur due to the high temperature of the combustion gas. The heated combustion gas is sucked by the exhaust gas blower 12 and exhausted from the exhaust port 13. In this embodiment, the heated air used for cooling in the heat exchanger 9 is sucked in by the exhaust gas blower 12 during mixing, so there is no need for, for example, an air blower to supply cooling air to the heat exchanger 9. Become.

上述した実施例のうち粗フィルタを具える実施例におい
て、実際に毎時50kgの放射性廃棄物を処理したとき
の各部における燃焼ガス温度及び流量を第2図に示す。
FIG. 2 shows the temperature and flow rate of the combustion gas at each part when 50 kg of radioactive waste was actually treated per hour in the embodiment including a coarse filter among the embodiments described above.

第2図から明らかなように、熱交換器9では600℃の
ガスが300℃に冷却されると共に、洗浄塔11から放
出される60℃の排ガスは熱交換により400℃に加熱
された空気と混合し、200℃のガスとして外部へ放出
されているため、本発明の目的を達成することができる
。また、熱風混合により増加したガス量も2倍程度であ
るので、排ガスブロワ12の能力もそれほど大きなもの
を必要としない。
As is clear from Fig. 2, the gas at 600°C is cooled to 300°C in the heat exchanger 9, and the exhaust gas at 60°C discharged from the cleaning tower 11 is mixed with air heated to 400°C by heat exchange. The objects of the present invention can be achieved because they are mixed and released to the outside as a gas at 200°C. Further, since the amount of gas increased by hot air mixing is about twice as large, the capacity of the exhaust gas blower 12 does not need to be so large.

本発明は上述した実施例にのみ限定されるものではなく
、幾多の変形、変更が可能である。例えば上述した実施
例ではセラミックフィルタを1個だけしか設けていない
が、複数のセラミックフィルタを使用することもできる
The present invention is not limited only to the embodiments described above, and numerous modifications and changes are possible. For example, although only one ceramic filter is provided in the embodiments described above, a plurality of ceramic filters may also be used.

(発明の効果) 以上詳細に説明したところから明らかなように、本発明
の放射性廃棄物の処理方法によれば、空冷式熱交換器を
使用するとともに燃焼ガスを冷却するのに使用され加熱
された空気を使用して洗浄塔から排出される低温の燃焼
ガスを昇温しているため、高性能フィルタで処理すべき
燃焼ガス量を増加させないと共に、酸の結露すなわちそ
の結果生じる排気系の腐食等を有効に防止することがで
きる。また、熱交換器の冷却用空気と燃焼ガスとを同一
の4排気プロワで吸引することができるため、熱交換器
専用のブロワを必要としない。さらに、高性能フィルタ
の前段に粗フィルタを設置した場合は、高性能フィルタ
の寿命を長くすることができる。
(Effects of the Invention) As is clear from the detailed explanation above, according to the radioactive waste treatment method of the present invention, an air-cooled heat exchanger is used and the combustion gas is heated and used to cool it. The use of recycled air to raise the temperature of the low-temperature combustion gases exiting the scrubbing tower does not increase the amount of combustion gases that must be treated with high-performance filters, and reduces acid condensation and resulting exhaust system corrosion. etc. can be effectively prevented. Furthermore, since the cooling air and combustion gas for the heat exchanger can be sucked in by the same four-exhaust blower, there is no need for a dedicated blower for the heat exchanger. Furthermore, if a coarse filter is installed before a high-performance filter, the life of the high-performance filter can be extended.

【図面の簡単な説明】[Brief explanation of drawings]

第1図は本発明の放射性廃棄物の処理方法を実施するシ
ステムの一例を示す線図、 第2図は本発明の方法を実施する際の各部における燃焼
ガス温度及び流量を示す線図、第3図および第4図はそ
れぞれ従来の放射性廃棄物の処理方法を示す線図である
。 1・・・投入@      2a・・・フィーダ2b・
・・ノズル     3・・・焼却炉4・・・焼却灰取
出コンベア 5・・・ホッパ     6・・・高周波溶融炉7・・
・バーナ     8・・・セラミックフィルタ9・・
・空冷式熱交換器 10・・・高性能フィルタ11・・
・洗浄塔     12・・・排ガスブロワ13・・・
排気口
Fig. 1 is a diagram showing an example of a system for carrying out the radioactive waste treatment method of the present invention; Fig. 2 is a diagram showing combustion gas temperatures and flow rates at various parts when carrying out the method of the present invention; 3 and 4 are diagrams showing conventional radioactive waste disposal methods, respectively. 1... Input @ 2a... Feeder 2b.
...Nozzle 3...Incinerator 4...Incinerated ash removal conveyor 5...Hopper 6...High frequency melting furnace 7...
・Burner 8...Ceramic filter 9...
・Air-cooled heat exchanger 10...High performance filter 11...
・Cleaning tower 12...Exhaust gas blower 13...
exhaust port

Claims (1)

【特許請求の範囲】 1、放射性物質取扱施設において発生する可燃性雑固体
廃棄物、廃樹脂等の放射性廃棄物を焼却炉で焼却して焼
却灰とするとともに、前記焼却炉の燃焼排ガスを除塵機
で除塵し除塵した排ガスを空冷式熱交換器により冷却し
、冷却した排ガスを高性能フィルタでさらに除塵しこの
除塵した排ガスを洗浄塔により洗浄した後、前記排ガス
の冷却時に加熱された空冷式熱交換器の熱風空気を洗浄
後のガスと合流させ、前記合流排ガスを共通の排風機に
より大気中へ放出することを特徴とする放射性廃棄物の
処理方法。 2、前記除塵機としてセラミックフィルタを使用する特
許請求の範囲第1項記載の放射性廃棄物の処理方法。 3、前記空冷式熱交換器としてセラミック質直交流型熱
交換器を使用する特許請求の範囲第1項記載の放射性廃
棄物の処理方法。 4、前記高性能フィルタの前段に粗フィルタを設けて、
前記冷却した排ガスを粗フィルタを通した後高性能フィ
ルタに通す特許請求の範囲第1項記載の放射性廃棄物の
処理方法。 5、前記空冷式熱交換器出口の排ガス温度が150〜3
00℃である特許請求の範囲第1項記載の放射性廃棄物
の処理方法。
[Claims] 1. Radioactive waste such as combustible miscellaneous solid waste and waste resin generated in a radioactive material handling facility is incinerated into incineration ash, and the combustion exhaust gas of the incinerator is removed from dust. The exhaust gas that has been cleaned and dusted by the machine is cooled by an air-cooled heat exchanger, the cooled exhaust gas is further removed by a high-performance filter, and the dust-removed exhaust gas is washed by a cleaning tower. A method for treating radioactive waste, comprising: combining hot air from a heat exchanger with gas after cleaning; and releasing the combined exhaust gas into the atmosphere using a common exhaust fan. 2. The radioactive waste treatment method according to claim 1, wherein a ceramic filter is used as the dust remover. 3. The radioactive waste treatment method according to claim 1, wherein a ceramic cross-flow heat exchanger is used as the air-cooled heat exchanger. 4. Providing a coarse filter before the high-performance filter,
The method for treating radioactive waste according to claim 1, wherein the cooled exhaust gas is passed through a coarse filter and then a high-performance filter. 5. The exhaust gas temperature at the outlet of the air-cooled heat exchanger is 150-3
The method for treating radioactive waste according to claim 1, wherein the temperature is 00°C.
JP14817685A 1985-07-08 1985-07-08 Method of treating radioactive waste Granted JPS629297A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP14817685A JPS629297A (en) 1985-07-08 1985-07-08 Method of treating radioactive waste

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP14817685A JPS629297A (en) 1985-07-08 1985-07-08 Method of treating radioactive waste

Publications (2)

Publication Number Publication Date
JPS629297A true JPS629297A (en) 1987-01-17
JPH0558158B2 JPH0558158B2 (en) 1993-08-25

Family

ID=15446948

Family Applications (1)

Application Number Title Priority Date Filing Date
JP14817685A Granted JPS629297A (en) 1985-07-08 1985-07-08 Method of treating radioactive waste

Country Status (1)

Country Link
JP (1) JPS629297A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH06242293A (en) * 1993-02-23 1994-09-02 Ngk Insulators Ltd Ceramic filter and incinerator using it
KR20230082933A (en) * 2021-12-02 2023-06-09 주식회사 오리온이엔씨 system and method that compresses radioactive waste filters of nuclear power plant with efficiency

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH06242293A (en) * 1993-02-23 1994-09-02 Ngk Insulators Ltd Ceramic filter and incinerator using it
KR20230082933A (en) * 2021-12-02 2023-06-09 주식회사 오리온이엔씨 system and method that compresses radioactive waste filters of nuclear power plant with efficiency

Also Published As

Publication number Publication date
JPH0558158B2 (en) 1993-08-25

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