JP2948754B2 - Radioactive waste gas treatment method - Google Patents
Radioactive waste gas treatment methodInfo
- Publication number
- JP2948754B2 JP2948754B2 JP3154496A JP3154496A JP2948754B2 JP 2948754 B2 JP2948754 B2 JP 2948754B2 JP 3154496 A JP3154496 A JP 3154496A JP 3154496 A JP3154496 A JP 3154496A JP 2948754 B2 JP2948754 B2 JP 2948754B2
- Authority
- JP
- Japan
- Prior art keywords
- waste gas
- ruo
- radioactive waste
- hcl
- temperature
- 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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- Solid-Sorbent Or Filter-Aiding Compositions (AREA)
- Treating Waste Gases (AREA)
Description
【0001】[0001]
【発明の属する技術分野】本発明は、放射性廃棄物の焼
却や溶融により発生するRuO4を含有する放射性廃ガスの
処理方法に関するものである。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a method for treating a radioactive waste gas containing RuO 4 generated by incineration or melting of radioactive waste.
【0002】[0002]
【従来の技術】原子力発電所等から発生するRu(ルテニ
ウム)で汚染された塩化ビニル樹脂やゴム等の放射性廃
棄物は、従来はそのままドラム缶等に詰めて保管されて
いた。しかし保管スペースの確保に限界があるため、近
年これらを焼却または溶融処理することにより減容化す
ることが求められている。2. Description of the Related Art Conventionally, radioactive waste such as vinyl chloride resin and rubber contaminated with Ru (ruthenium) generated from a nuclear power plant or the like has been stored in a drum or the like as it is. However, since there is a limit in securing a storage space, it has recently been required to reduce the volume by incineration or melting.
【0003】このようなRuで汚染された塩化ビニル樹脂
やゴム等を焼却したり溶融すると、RuO4、HCl 、SOX 等
のガスが発生することとなり、これらは放出規制上ある
いは設備の腐食防止上、除去することが必要である。こ
のために従来は図5のフローシートに示したような処理
方法が提案されていた。[0003] When such vinyl chloride resin or rubber contaminated with Ru is incinerated or melted, gases such as RuO 4 , HCl, and SO X are generated, and these gases are generated due to emission regulations or corrosion prevention of equipment. Above, it is necessary to remove. For this purpose, conventionally, a processing method as shown in a flow sheet of FIG. 5 has been proposed.
【0004】この従来方法では、まず焼却炉から排出さ
れたRuO4を含有する放射性廃ガスを700 〜800 ℃の温度
域で高温濾過してダストを除去する。次に水噴霧を行っ
てガス温度を200 〜250 ℃程度まで下げたうえ、アルカ
リ性あるいは中性の洗浄水による洗浄を行いHCl 、SOX
等を除去する。次にガス中の水分を凝縮させて除去した
うえで80℃程度まで加熱して更に乾燥させ、その後にシ
リカゲルによりRuO4を吸着させて除去するのである。In this conventional method, first, radioactive waste gas containing RuO 4 discharged from an incinerator is filtered at a high temperature in a temperature range of 700 to 800 ° C. to remove dust. Next, the temperature of the gas is reduced to about 200 to 250 ° C. by spraying with water, and then washed with alkaline or neutral washing water to remove HCl, SO X
Etc. are removed. Next, the water in the gas is condensed and removed, heated to about 80 ° C. and further dried, and then RuO 4 is adsorbed and removed by silica gel.
【0005】しかしこの図5の方法では、洗浄及び凝縮
工程から放射性成分を含んだ多量の廃液が発生すること
となり、この廃液処理に多大な設備と運転作業が必要と
なるという問題があった。また高温の廃ガスを洗浄及び
凝縮工程で一度冷却したうえで、シリカゲルに接触でき
るように乾燥させる目的で再度加熱しており、エネルギ
ーロスが多いという問題もあった。However, the method shown in FIG. 5 has a problem that a large amount of waste liquid containing radioactive components is generated from the washing and condensation steps, and this waste liquid treatment requires a large amount of equipment and operation work. Further, since the high-temperature waste gas is once cooled in the washing and condensation steps, it is heated again for the purpose of drying it so that it can be brought into contact with the silica gel, and there is also a problem that a large amount of energy is lost.
【0006】[0006]
【発明が解決しようとする課題】本発明は上記した従来
の問題点を解決し、RuO4を含有する放射性廃ガスを、廃
液を生じさせることなく、また廃ガスの再加熱のような
エネルギーロスを必要とせずに処理することができる放
射性廃ガスの処理方法を提供するためになされたもので
ある。DISCLOSURE OF THE INVENTION The present invention solves the above-mentioned conventional problems and reduces the radioactive waste gas containing RuO 4 without generating a waste liquid and energy loss such as reheating of the waste gas. The purpose of the present invention is to provide a method for treating radioactive waste gas that can be treated without the need for wastewater.
【0007】[0007]
【課題を解決するための手段】上記の課題を解決するた
めになされた本発明は、放射性廃棄物の焼却や溶融によ
り発生するRuO4を含有する放射性廃ガスを、シリカと酸
化鉄とを主成分とする吸着剤と接触させてRuO4を吸着除
去したうえ、カルシウムを主成分とする吸収剤と接触さ
せてHCl やSOX を吸収除去することを特徴とするもので
ある。なお、RuO4の吸着およびHCl やSOX の吸収を150
〜350 ℃の温度域で行わせることが好ましい。SUMMARY OF THE INVENTION The present invention has been made to solve the above-mentioned problems. The present invention mainly uses silica and iron oxide to convert radioactive waste gas containing RuO 4 generated by incineration or melting of radioactive waste. after having adsorbed remove RuO 4 in contact with the adsorbent as a component, and is characterized in that calcium absorption remove HCl and SO X in contact with the absorbent mainly composed of. The absorption of RuO 4 and the absorption of HCl and SO X were
It is preferable to carry out in a temperature range of -350 ° C.
【0008】[0008]
【発明の実施の形態】以下に図1を参照しつつ、本発明
の好ましい実施の形態を説明する。図1のフローシート
に示すように、本発明においても放射性廃棄物の焼却炉
や溶融炉から発生するRuO4を含有する放射性廃ガスを、
まず700 〜800 ℃の温度域で一次濾過及び二次濾過して
ダストを除去したうえ、水噴霧を行ってガス温度を150
〜350 ℃の温度域まで下げる。後記するように、この温
度域は200 〜250 ℃程度とすることがより好ましい。こ
の水噴霧によって廃ガスの温度は降下するものの、水分
は7〜8%の乾燥した状態を維持する。DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS A preferred embodiment of the present invention will be described below with reference to FIG. As shown in the flow sheet of FIG. 1, in the present invention, radioactive waste gas containing RuO 4 generated from an incinerator or melting furnace for radioactive waste is also used.
First, dust is removed by primary filtration and secondary filtration in the temperature range of 700 to 800 ° C, and water is sprayed to reduce the gas temperature to 150 ° C.
Lower to the temperature range of ~ 350 ° C. As will be described later, this temperature range is more preferably set to about 200 to 250 ° C. Although the temperature of the waste gas is lowered by this water spray, the water maintains a dry state of 7 to 8%.
【0009】次に、この廃ガスをシリカと酸化鉄とを主
成分とする吸着剤と接触させてRuO4を吸着除去する。こ
の吸着剤はシリカゲルの表面に酸化鉄を担持させた「鉄
担持シリカゲル」であり、例えば粒径が75〜3000μm で
酸化鉄の含量が1.6 重量%のものを用いることができ
る。Next, this waste gas is brought into contact with an adsorbent mainly composed of silica and iron oxide to adsorb and remove RuO 4 . The adsorbent is "iron-supported silica gel" in which iron oxide is supported on the surface of silica gel. For example, a silica particle having a particle size of 75 to 3000 μm and an iron oxide content of 1.6% by weight can be used.
【0010】図2はこの吸着剤によるRuO4の吸着除去効
果をDF(廃ガス中のRuO4の入口濃度/出口濃度)で表
して縦軸に取り、横軸に反応温度を取ったグラフであ
る。また比較のために、シリカゲルのみの場合も示して
ある。図2のグラフに示されるように、鉄担持シリカゲ
ル(グラフ中では鉄シリカと表示)は150 ℃以上でDF
が103 を越える優れた結果を示す。しかしそれ以上は温
度を上げてもDFはあまり向上しないため、機器の耐熱
性を考慮すると150 〜350 ℃の温度域、より好ましくは
200 〜250 ℃の温度域が好ましい。FIG. 2 is a graph in which the effect of adsorption and removal of RuO 4 by this adsorbent is represented by DF (inlet concentration / outlet concentration of RuO 4 in waste gas) on the vertical axis and the reaction temperature on the horizontal axis. is there. For comparison, the case of silica gel alone is also shown. As shown in the graph of FIG. 2, the iron-supported silica gel (denoted as iron silica in the graph) has a DF above 150 ° C.
There show excellent results exceeding 10 3. However, if the temperature is raised beyond that, the DF does not improve much. Therefore, considering the heat resistance of the equipment, the temperature range is 150 to 350 ° C, more preferably
A temperature range of 200-250 ° C is preferred.
【0011】また図3は廃ガス中の水分(体積%)がD
Fに及ぼす影響を示したグラフである。温度を200 ℃と
した鉄担持シリカゲルを用いた場合には、水分が5〜10
%の範囲内でDFは優れた値を示すことが分かる。FIG. 3 shows that the moisture (volume%) in the waste gas is D
6 is a graph showing the effect on F. When iron-supported silica gel at a temperature of 200 ° C. is used, the moisture content is 5 to 10
It can be seen that DF shows an excellent value within the range of%.
【0012】更に図4は、廃ガス中のHCl 濃度がRuO4の
吸着除去効果に与える影響を示したグラフである。この
グラフに示されるように、HCl 濃度が0%の場合と1%
の場合とを比較すると、鉄担持シリカゲルを用いた場
合、廃ガス中にHClが含有されている場合の方がDFが
高くなる。このため、本発明では廃ガス中から先にRuO4
を吸着させ、後でHCl やSOX を除去する方法を採用して
おり、これによって廃ガス中のRuO4濃度を1/1000以下と
することを可能とした。FIG. 4 is a graph showing the effect of the HCl concentration in the waste gas on the RuO 4 adsorption / removal effect. As shown in this graph, when the HCl concentration is 0% and 1%
Compared with the case of the above, when iron-supported silica gel is used, the DF is higher when the waste gas contains HCl. Therefore, in the present invention, RuO 4
Is adopted, and HCl and SO X are removed later. This makes it possible to reduce the RuO 4 concentration in the waste gas to 1/1000 or less.
【0013】上記のようにしてRuO4を除去された廃ガス
は150 〜350 ℃の温度に維持されたまま、カルシウムを
主成分とする吸収剤でHCl やSOX を吸収除去される。こ
のような吸収剤としては、例えば粘土にCa(OH)2 を混合
し、水蒸気養生した粒状またはペレット状のものがあ
る。この吸収剤との接触により廃ガス中のHCl やSOX は
ほぼ完全に除去され、さらにHEPAフィルター等によ
る濾過を行えばよい。[0013] Waste gas is removed RuO 4 in the manner described above while being maintained at a temperature of 0.99 to 350 ° C., are calcium absorption of HCl and SO X in absorbent mainly composed of removal. Examples of such an absorbent include granules or pellets obtained by mixing Ca (OH) 2 with clay and steam-curing. HCl and SO X in the waste gas are almost completely removed by the contact with the absorbent, and filtration may be performed by a HEPA filter or the like.
【0014】なおガス流量/吸着剤体積やガス流量/吸
収剤体積を意味するSV値は1000h -1〜2000h -1とし、
空塔速度は0.5m/s以下とすることが好ましい。[0014] Note that the SV to mean gas flow rate / adsorbent volume and gas flow rate / absorbent volume and 1000h -1 ~2000h -1,
The superficial velocity is preferably 0.5 m / s or less.
【0015】上記した本発明の放射性廃ガスの処理方法
によれば、全く廃液を発生させることなくRuO4を含有す
る放射性廃ガス中からRuO4、HCl 、SOX 等を除去するこ
とができる。しかも廃ガスを150 〜350 ℃の温度に維持
したままで処理ができるので、従来のように一度冷却し
た廃ガスを再加熱する必要もなく、エネルギーロスもな
い。次に本発明の実施例を示す。According to the method for treating radioactive waste gas of the present invention, RuO 4 , HCl, SO X and the like can be removed from radioactive waste gas containing RuO 4 without generating any waste liquid. Moreover, since the processing can be performed while maintaining the waste gas at a temperature of 150 to 350 ° C., there is no need to reheat the once-cooled waste gas as in the prior art, and there is no energy loss. Next, examples of the present invention will be described.
【0016】[0016]
【実施例】放射性廃棄物の焼却炉から生じたRuO4、HCl
、SOX 等を含有する700〜800 ℃の廃ガスを、120Nm3/h
の流量でセラミックフィルターに流してダストを除去
し、水噴霧により温度を200 ℃まで下げた。次にこの廃
ガスを鉄担持シリカゲルに接触させ、RuO4を吸着除去し
た。鉄担持シリカゲルは粒径が500 〜2000μm のもの0.
14m3を、直径0.5mで高さ0.7mの塔の中に充填したもの
で、SV=1500h -1である。[Example] RuO 4 and HCl generated from radioactive waste incinerator
The 700 to 800 ° C. of the waste gases containing SO X or the like, 120 Nm 3 / h
The dust was removed by flowing the mixture through a ceramic filter at a flow rate of, and the temperature was lowered to 200 ° C by spraying with water. Next, this waste gas was brought into contact with iron-carrying silica gel to adsorb and remove RuO 4 . Iron-supported silica gel with a particle size of 500 to 2000 μm
14 m 3 was packed in a tower 0.5 m in diameter and 0.7 m in height, SV = 1500 h −1 .
【0017】鉄担持シリカゲルの充填塔を出た廃ガスは
温度200 ℃を維持したまま、カルシウムを主成分とする
吸収剤の充填塔に導かれた。この充填塔は2基設けられ
ており、それぞれに吸収剤(直径2.3 〜3.4mm の粒、化
学組成はCaO が51重量%、SiO2が20重量%、Al2O3 が4
重量%、CaSO4 が2重量%、Fe2O3 が0.5重量%)が0.3
m3 ずつ充填されており、交互に使用された。充填塔は
直径0.5m、高さ0.7mで、SV=1500h -1である。ここで
HCl やSOX を除去された廃ガスはそのままHEPAフィ
ルターで濾過され、大気中へ放出された。この実施例に
おける廃ガス中のRuO4、HCl 、SOX の除去効果を表1に
示す。The waste gas leaving the packed column of iron-supported silica gel was led to a packed column of an absorbent containing calcium as a main component while maintaining the temperature at 200 ° C. The packed column is provided in two groups, absorbent, respectively (diameter 2.3 ~3.4Mm particle, the chemical composition CaO is 51 wt%, SiO 2 of 20 wt%, Al 2 O 3 is 4
% By weight, 2% by weight of CaSO 4 and 0.5% by weight of Fe 2 O 3 )
each m 3 is filled and used alternately. The packed tower has a diameter of 0.5 m, a height of 0.7 m and an SV = 1500 h -1 . here
The waste gas from which HCl and SO X had been removed was directly filtered through a HEPA filter and released to the atmosphere. Table 1 shows the effect of removing RuO 4 , HCl and SO X in the waste gas in this embodiment.
【0018】[0018]
【表1】 [Table 1]
【0019】[0019]
【発明の効果】以上に説明したように、本発明によれば
全く廃液を発生させることなくRuO4を含有する放射性廃
ガス中からRuO4、HCl 、SOX 等を除去することができる
ので、従来のように廃液処理に多大の設備と運転作業を
要しない利点がある。また廃ガスを150 〜350 ℃の温度
に維持したままで処理ができるので、従来のように一度
冷却した廃ガスを再加熱する必要もなく、エネルギーロ
スもない利点がある。さらにHCl を含有させた状態でRu
O4の吸着を行わせるので、一段と優れたRuO4除去効果を
得ることができる。As described above, according to the present invention, RuO 4 , HCl, SO X and the like can be removed from a radioactive waste gas containing RuO 4 without generating any waste liquid. There is an advantage that a large amount of equipment and operation work are not required for waste liquid treatment as in the related art. Further, since the processing can be performed while maintaining the waste gas at a temperature of 150 to 350 ° C., there is an advantage that there is no need to reheat the once cooled waste gas as in the conventional case, and there is no energy loss. Ru further containing HCl
Since O 4 is adsorbed, a more excellent RuO 4 removal effect can be obtained.
【図1】本発明のフローシートである。FIG. 1 is a flow sheet of the present invention.
【図2】吸着剤のDFに与える温度の影響を示すグラフ
である。FIG. 2 is a graph showing the effect of temperature on the DF of an adsorbent.
【図3】吸着剤のDFに与える水分の影響を示すグラフ
である。FIG. 3 is a graph showing the effect of moisture on the DF of an adsorbent.
【図4】吸着剤のDFに与えるHCl の影響を示すグラフ
である。FIG. 4 is a graph showing the effect of HCl on the DF of the adsorbent.
【図5】従来法のフローシートである。FIG. 5 is a flow sheet of a conventional method.
Claims (2)
るRuO4を含有する放射性廃ガスを、シリカと酸化鉄とを
主成分とする吸着剤と接触させてRuO4を吸着除去したう
え、カルシウムを主成分とする吸収剤と接触させてHCl
やSOX を吸収除去することを特徴とする放射性廃ガスの
処理方法。1. A radioactive waste gas containing RuO 4 generated by incineration or melting of radioactive waste is brought into contact with an adsorbent mainly composed of silica and iron oxide to adsorb and remove RuO 4 , HCl by contact with an absorbent containing
Method for treating a radioactive waste gases, characterized by absorbing and removing or SO X.
0 〜350 ℃の温度域で行わせる請求項1に記載の放射性
廃ガスの処理方法。2. The absorption of RuO 4 and the absorption of HCl and SO X are reduced by 15%.
The method for treating radioactive waste gas according to claim 1, wherein the method is performed in a temperature range of 0 to 350 ° C.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP3154496A JP2948754B2 (en) | 1996-02-20 | 1996-02-20 | Radioactive waste gas treatment method |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP3154496A JP2948754B2 (en) | 1996-02-20 | 1996-02-20 | Radioactive waste gas treatment method |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH09222496A JPH09222496A (en) | 1997-08-26 |
| JP2948754B2 true JP2948754B2 (en) | 1999-09-13 |
Family
ID=12334143
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP3154496A Expired - Lifetime JP2948754B2 (en) | 1996-02-20 | 1996-02-20 | Radioactive waste gas treatment method |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP2948754B2 (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP5767938B2 (en) * | 2011-10-19 | 2015-08-26 | 新日鉄住金エンジニアリング株式会社 | Volume reduction method for low-level radioactive waste |
| CN104143368B (en) * | 2014-08-12 | 2017-01-25 | 中广核工程有限公司 | Nuclear power station radioactive waste gas treatment system |
-
1996
- 1996-02-20 JP JP3154496A patent/JP2948754B2/en not_active Expired - Lifetime
Also Published As
| Publication number | Publication date |
|---|---|
| JPH09222496A (en) | 1997-08-26 |
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