JPH0230680B2 - HOSHASEIHAIKIBUTSUNOSHORIHOHO - Google Patents
HOSHASEIHAIKIBUTSUNOSHORIHOHOInfo
- Publication number
- JPH0230680B2 JPH0230680B2 JP8721083A JP8721083A JPH0230680B2 JP H0230680 B2 JPH0230680 B2 JP H0230680B2 JP 8721083 A JP8721083 A JP 8721083A JP 8721083 A JP8721083 A JP 8721083A JP H0230680 B2 JPH0230680 B2 JP H0230680B2
- Authority
- JP
- Japan
- Prior art keywords
- waste
- dryer
- exhaust gas
- radioactive
- dust
- 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
Links
- 239000002699 waste material Substances 0.000 claims description 29
- 239000000919 ceramic Substances 0.000 claims description 16
- 239000007788 liquid Substances 0.000 claims description 15
- 239000000428 dust Substances 0.000 claims description 14
- 239000007789 gas Substances 0.000 claims description 12
- 238000000034 method Methods 0.000 claims description 12
- 239000011347 resin Substances 0.000 claims description 11
- 229920005989 resin Polymers 0.000 claims description 11
- 238000002485 combustion reaction Methods 0.000 claims description 10
- 239000000843 powder Substances 0.000 claims description 10
- 239000002910 solid waste Substances 0.000 claims description 8
- 239000002901 radioactive waste Substances 0.000 claims description 7
- 239000012857 radioactive material Substances 0.000 claims description 6
- 239000002918 waste heat Substances 0.000 claims description 4
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 5
- 239000004568 cement Substances 0.000 description 4
- 239000002925 low-level radioactive waste Substances 0.000 description 3
- 239000000463 material Substances 0.000 description 3
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 2
- MCMNRKCIXSYSNV-UHFFFAOYSA-N Zirconium dioxide Chemical compound O=[Zr]=O MCMNRKCIXSYSNV-UHFFFAOYSA-N 0.000 description 2
- 238000009835 boiling Methods 0.000 description 2
- 239000010849 combustible waste Substances 0.000 description 2
- 238000007796 conventional method Methods 0.000 description 2
- 238000011038 discontinuous diafiltration by volume reduction Methods 0.000 description 2
- 238000010438 heat treatment Methods 0.000 description 2
- -1 nuclear power plants Substances 0.000 description 2
- 239000004033 plastic Substances 0.000 description 2
- 229920003023 plastic Polymers 0.000 description 2
- 239000010802 sludge Substances 0.000 description 2
- NWUYHJFMYQTDRP-UHFFFAOYSA-N 1,2-bis(ethenyl)benzene;1-ethenyl-2-ethylbenzene;styrene Chemical compound C=CC1=CC=CC=C1.CCC1=CC=CC=C1C=C.C=CC1=CC=CC=C1C=C NWUYHJFMYQTDRP-UHFFFAOYSA-N 0.000 description 1
- PMZURENOXWZQFD-UHFFFAOYSA-L Sodium Sulfate Chemical compound [Na+].[Na+].[O-]S([O-])(=O)=O PMZURENOXWZQFD-UHFFFAOYSA-L 0.000 description 1
- PNEYBMLMFCGWSK-UHFFFAOYSA-N aluminium oxide Inorganic materials [O-2].[O-2].[O-2].[Al+3].[Al+3] PNEYBMLMFCGWSK-UHFFFAOYSA-N 0.000 description 1
- 239000010426 asphalt Substances 0.000 description 1
- 229910021538 borax Inorganic materials 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 239000012717 electrostatic precipitator Substances 0.000 description 1
- 230000008020 evaporation Effects 0.000 description 1
- 238000001704 evaporation Methods 0.000 description 1
- 239000004744 fabric Substances 0.000 description 1
- 239000003456 ion exchange resin Substances 0.000 description 1
- 229920003303 ion-exchange polymer Polymers 0.000 description 1
- 238000004898 kneading Methods 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 230000008018 melting Effects 0.000 description 1
- 238000002844 melting Methods 0.000 description 1
- 239000000123 paper Substances 0.000 description 1
- 229910052938 sodium sulfate Inorganic materials 0.000 description 1
- 235000011152 sodium sulphate Nutrition 0.000 description 1
- 235000010339 sodium tetraborate Nutrition 0.000 description 1
- 230000008023 solidification Effects 0.000 description 1
- 238000007711 solidification Methods 0.000 description 1
- 239000007921 spray Substances 0.000 description 1
- BSVBQGMMJUBVOD-UHFFFAOYSA-N trisodium borate Chemical compound [Na+].[Na+].[Na+].[O-]B([O-])[O-] BSVBQGMMJUBVOD-UHFFFAOYSA-N 0.000 description 1
Landscapes
- Fertilizers (AREA)
- Gasification And Melting Of Waste (AREA)
Description
【発明の詳細な説明】
この発明は放射性廃棄物を処理する方法に関
し、詳しくは中・低レベル放射性廃棄物を処理す
る方法に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a method for treating radioactive waste, and more particularly to a method for treating intermediate to low level radioactive waste.
原子力発電所等の放射性物質取扱施設において
は、中・低レベルの放射性廃棄物、すなわち廃樹
脂（使用済イオン交換樹脂）、フイルタ−スラツ
ジ、活性炭、濃縮廃液、および布、紙、プラスチ
ツクス等からなる可燃性雑固体廃棄物等が多量に
発生する。これらの廃棄物のうち廃樹脂、濃縮廃
液、可燃性雑固体廃棄物が特に発生量が多く、た
とえば110万KW級の沸謄水型原子力発電所にお
いては廃樹脂が約150m3／年、濃縮廃液が約160
m3／年、可燃性雑固体廃棄物が約400m3／年の発
生量があり、その発生比率（容積比）は約１：
１：2.5である。そしてこれらの廃棄物のうち濃
縮廃液および廃樹脂は従来そのままセメント練り
混ぜて固化させていたので、固化体はきわめてか
さばるものであり、さらにその固化体および可燃
性雑固体廃棄物を収納した大量のドラム缶の貯蔵
のため広大なスペースを必要とし好ましくなかつ
た。そこで濃縮廃液を蒸気を利用した外熱式乾燥
機で蒸発乾燥させることも試みられているが、水
蒸気発生用の熱源を必要とするうえ、蒸気を凝縮
させ、その凝縮水を処理、処分する必要があり煩
雑であるという欠点を有するものであつた。 In facilities that handle radioactive materials such as nuclear power plants, medium to low level radioactive waste, such as waste resin (used ion exchange resin), filter sludge, activated carbon, concentrated waste liquid, cloth, paper, plastics, etc. A large amount of combustible miscellaneous solid waste will be generated. Among these wastes, waste resin, concentrated waste liquid, and combustible miscellaneous solid waste are generated in particularly large amounts.For example, in a 1.1 million KW class boiling water nuclear power plant, waste resin is concentrated at approximately 150 m 3 /year. Approximately 160 waste liquid
m 3 /year, and approximately 400m 3 /year of combustible miscellaneous solid waste is generated, and the generation ratio (volume ratio) is approximately 1:
The ratio is 1:2.5. Among these wastes, concentrated waste liquid and waste resin were conventionally mixed with cement and solidified, so the solidified material was extremely bulky, and furthermore, the solidified material and combustible miscellaneous solid waste were stored in large quantities. This is not desirable as it requires a large space to store the drums. Therefore, attempts have been made to evaporate the concentrated waste liquid using an external heat dryer that uses steam, but this requires a heat source to generate steam, and it is also necessary to condense the steam and treat and dispose of the condensed water. This method had the disadvantage of being complicated and complicated.
この発明は上記従来の欠点を解消するもので大
巾な減容化が達成でき、しかも消費エネルギが少
なくて済む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 present invention aims to solve the above-mentioned conventional drawbacks and to provide a method for disposing of radioactive waste that can achieve a large volume reduction and consume less energy.
しかしてこの発明は、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、廃樹脂を焼却
炉で焼却して焼却灰とするとともに上記焼却炉の
燃焼排ガスを除塵機で除塵し、一方上記放射性物
質取扱施設において発生する濃縮廃液を上記燃焼
排ガスの廃熱を熱源とする乾燥機で乾燥して粉体
とするとともに上記乾燥機の排ガスを除塵機で除
塵し、上記焼却灰と上記粉体と上記各除塵機で捕
集した粉じんとを固化処理することを特徴とする
放射性廃棄物の処理方法である。 However, in this invention, combustible miscellaneous solid waste and waste resin generated in a radioactive material handling facility are incinerated in an incinerator to produce incineration ash, and the combustion exhaust gas from the incinerator is removed by a dust remover, while the radioactive materials are Concentrated waste liquid generated in material handling facilities is dried in a dryer that uses the waste heat of the combustion exhaust gas as a heat source to turn it into powder, and the exhaust gas from the dryer is removed with a dust remover, and the incinerated ash and the powder are removed. This is a radioactive waste disposal method characterized by solidifying the dust collected by each of the above dust removers.
以下図面によつてこの発明をさらに詳細に説明
する。 The present invention will be explained in more detail below with reference to the drawings.
先ず原子力発電所等の放射性物質取扱施設から
発生する中・低レベルの放射性廃棄物のうち、可
燃性廃棄物である廃樹脂およびフイルタスラツジ
は脱水機１により脱水後それぞれ定量フイーダ２
を介して熱風炉形の焼却炉３に投入して焼却し、
同じく可燃性廃棄物である廃油および可燃性雑固
体廃棄物は好ましくは空気予熱器を有する焼却炉
４で焼却する。なお図中鎖線で示すように焼却炉
４の燃焼排ガスの一部を焼却炉３の加熱源として
利用してもよい。両焼却炉３，４の燃焼排ガスは
一方にのみ開口した多孔質セラミツク製フイルタ
エレメント５をろ過体としてそなえた一次セラミ
ツクフイルタ６および二次セラミツクフイルタ７
により除塵し、高性能（HEPA）フイルタ８に
よつて除塵後ブロワ９によつて煙突へ圧送し大気
中へ放出する。１０は燃焼排ガスの有する約800
℃にも及ぶ廃熱を利用して常温空気を加熱してボ
ール型熱風乾燥機２０（後述）に供給するための
熱交換器である。なお一次セラミツクフイルタ６
においては、送入される燃焼排ガス中の未然分ダ
ストの燃焼効率を向上させるために補助バーナ１
１を設けるとよい。 First, among medium and low-level radioactive waste generated from facilities handling radioactive materials such as nuclear power plants, waste resin and filter sludge, which are combustible wastes, are dehydrated by a dehydrator 1 and then transferred to a quantitative feeder 2.
and incinerate it by putting it into a hot-air furnace type incinerator 3 through
Waste oil and combustible miscellaneous solid waste, which are also combustible wastes, are preferably incinerated in an incinerator 4 having an air preheater. Note that a part of the combustion exhaust gas from the incinerator 4 may be used as a heating source for the incinerator 3, as shown by the chain line in the figure. The combustion exhaust gas from both incinerators 3 and 4 is passed through a primary ceramic filter 6 and a secondary ceramic filter 7 each having a porous ceramic filter element 5 that is open only on one side as a filter body.
After the dust is removed by a high-performance (HEPA) filter 8, it is forced into a chimney by a blower 9 and released into the atmosphere. 10 is the approximately 800 that combustion exhaust gas has
This is a heat exchanger for heating room temperature air using waste heat reaching temperatures as high as 0.degree. C. and supplying the heated air to a ball-type hot air dryer 20 (described later). Furthermore, primary ceramic filter 6
In order to improve the combustion efficiency of unresolved dust in the incoming combustion exhaust gas, the auxiliary burner 1 is installed.
It is recommended to set 1.
また濃縮廃液はボール型熱風乾燥機２０内に供
給して乾燥させる。ボール型熱風乾燥機２０は穴
あき板状の底板２１を有する胴部内に好ましくは
アルミナ、ジルコニアなどのセラミツク質ボール
２２を充填し、このセラミツク質ボール２２を回
転軸に固着した羽根２３により撹拌する型式のも
のである。底板２１の下部にはブロワ２４によつ
て圧送され熱交換器１０の通過により300〜400℃
程度に加熱された熱風（空気）が供給され、セラ
ミツク質ボール２２の充填層上に滴下された濃縮
廃液はボール表面に沿つて流れ落ちる間に上記熱
風によつて乾燥され、フレーク状の粉体となつて
下方へ落下し本体下部から取出される。この粉体
は沸謄水型原子力発電所の場合は硫酸ソーダ、加
圧水型原子力発電所の場合はホウ酸ソーダなどを
主成分とするものである。ボール型熱風乾燥機２
０の排気口から排出される排ガス中には濃縮廃液
の乾燥粉体の一部が同伴するので、前記と同様な
フイルタエレメントを用いた一次セラミツクフイ
ルタ２５および二次セラミツクフイルタ２６によ
り除塵し、前記焼却炉の燃焼排ガスと同様に高性
能フイルタ８により除塵後大気中へ放出させる。 Further, the concentrated waste liquid is supplied into the ball-type hot air dryer 20 and dried. The ball type hot air dryer 20 has a body having a perforated bottom plate 21 and is filled with ceramic balls 22, preferably made of alumina, zirconia, etc., and the ceramic balls 22 are agitated by a blade 23 fixed to a rotating shaft. It is of the model type. A temperature of 300 to 400°C is supplied to the lower part of the bottom plate 21 by a blower 24 and passed through a heat exchanger 10.
Hot air (air) heated to a certain degree is supplied, and the concentrated waste liquid dropped onto the packed bed of the ceramic balls 22 is dried by the hot air while flowing down along the ball surface, and becomes flaky powder. It curls downward and is taken out from the bottom of the main body. This powder is mainly composed of sodium sulfate in the case of boiling water nuclear power plants, and sodium borate in the case of pressurized water nuclear power plants. Ball type hot air dryer 2
Since a part of the dry powder of the concentrated waste liquid is included in the exhaust gas discharged from the exhaust port of No. Similar to the combustion exhaust gas of an incinerator, the dust is removed by a high-performance filter 8 and then released into the atmosphere.
一方、焼却炉３および４で得られた焼却灰、セ
ラミツクフイルタ６および７で捕集した粉じん、
ボール型熱風乾燥機２０で得られた粉体、セラミ
ツクフイルタ２５および２６で捕集した粉じん等
は、たとえばセメント、アスフアルト、プラスチ
ツクスおよびセラミツクスなどを固化剤とする方
法、あるいは溶融炉を用いる固化処理装置３０に
送り、固化処理する。 On the other hand, incineration ash obtained in incinerators 3 and 4, dust collected in ceramic filters 6 and 7,
The powder obtained by the ball-type hot air dryer 20, the dust collected by the ceramic filters 25 and 26, etc. are processed by a method using cement, asphalt, plastics, ceramics, etc. as a solidifying agent, or by a solidifying process using a melting furnace. It is sent to a device 30 and solidified.
このようにこの発明では濃縮廃液を乾燥機によ
り乾燥して粉体化後固化処理するので、従来の濃
縮廃液をそのままセメントと混練して固化させる
方法に比べて、濃縮廃液の固化処理に必要な所要
ドラム缶本数は約1/7程度に減少する。またこの
発明では廃樹脂を焼却して焼却灰とした状態で固
化処理するので、従来のそのままセメントで固化
するのに比べて廃樹脂の固化処理に必要なドラム
缶の本数は約1/70程度に減少する。 In this way, in this invention, the concentrated waste liquid is dried in a dryer and solidified after being pulverized, so compared to the conventional method of kneading the concentrated waste liquid as it is with cement and solidifying it, the process required for solidifying the concentrated waste liquid is The number of drums required will be reduced to about 1/7. In addition, in this invention, waste resin is incinerated and solidified in the form of incineration ash, so the number of drums required for solidifying waste resin is approximately 1/70th that of the conventional method of solidifying waste resin directly with cement. Decrease.
この発明方法の実施に使用する装置は前記装置
に限定されるものではなく、たとえばボール型熱
風乾燥機２０へ供給する熱風としてはブロワ９の
吐出側あるいは吸込側などからバイパスした熱風
をそのままボール型熱風乾燥機２０へ供給して用
いてもよい。また濃縮廃液の乾燥機としてボール
型熱風乾燥機２０を用いると蒸発面積が大きいの
で乾燥機が小形で済み、粉体がフレーク状で飛散
しにくいうえ、胴部内壁等への粉体の付着量が少
なく保守が容易である等、種々の長所を有するも
のであるが、噴霧型乾燥機など他の形式の乾燥機
を用いてもよい。また各セラミツクフイルタのか
わりにサイクロンや電気集じん装置を用いること
も可能である。また第１図に示す例において、焼
却炉３，４は必ずしも同時焼却操作を必要とする
ものではなく、また焼却炉は必ずしも別体で設け
る必要はない。 The apparatus used to carry out the method of this invention is not limited to the above-mentioned apparatus. For example, the hot air to be supplied to the ball-type hot air dryer 20 is the hot air bypassed from the discharge side or the suction side of the blower 9, and is directly used in the ball-type hot air dryer 20. It may also be used by being supplied to the hot air dryer 20. In addition, if the ball-type hot air dryer 20 is used as a dryer for concentrated waste liquid, the evaporation area is large, so the dryer can be small, and the powder is flaky and difficult to scatter, and the amount of powder adhering to the inner wall of the body etc. Although this type of dryer has various advantages such as low amount of water and easy maintenance, other types of dryers such as a spray type dryer may also be used. It is also possible to use a cyclone or an electrostatic precipitator instead of each ceramic filter. Furthermore, in the example shown in FIG. 1, the incinerators 3 and 4 do not necessarily require simultaneous incineration operations, and the incinerators do not necessarily need to be provided separately.
以上説明したようにこの発明によれば、可燃性
雑固体廃棄物および／または廃樹脂を焼却すると
ともに、この焼却による廃熱を利用して熱源とす
る乾燥機により濃縮廃液を乾燥し粉体化するの
で、放射性廃棄物の固化処理に際して大巾な減容
化が達成でき、消費エネルギも少なくて済み経済
的に放射性廃棄物を固化処理できる。 As explained above, according to the present invention, combustible miscellaneous solid waste and/or waste resin is incinerated, and the concentrated waste liquid is dried and powdered using a dryer that uses waste heat from the incineration as a heat source. Therefore, when solidifying radioactive waste, a large volume reduction can be achieved, and less energy is consumed, making it possible to solidify radioactive waste economically.
第１図はこの発明の方法の実施に使用する装置
の一例の機器系統図である。
３……焼却炉、４……焼却炉、６……一次セラ
ミツクフイルタ、７……二次セラミツクフイル
タ、８……高性能フイルタ、９……ブロワ、１０
……熱交換器、２０……ボール型熱風乾燥機、２
４……ブロワ、２５……一次セラミツクフイル
タ、２６……二次セラミツクフイルタ、３０……
固化処理装置。
FIG. 1 is an equipment system diagram of an example of an apparatus used to carry out the method of the present invention. 3...Incinerator, 4...Incinerator, 6...Primary ceramic filter, 7...Secondary ceramic filter, 8...High performance filter, 9...Blower, 10
... Heat exchanger, 20 ... Ball type hot air dryer, 2
4...Blower, 25...Primary ceramic filter, 26...Secondary ceramic filter, 30...
Solidification processing equipment.
Claims (1)
雑固体廃棄物、廃樹脂を焼却炉で焼却して焼却灰
とするとともに上記焼却炉の燃焼排ガスを除塵機
で除塵し、一方上記放射性物質取扱施設において
発生する濃縮廃液を上記燃焼排ガスの廃熱を熱源
とする乾燥機で乾燥して粉体とするとともに上記
乾燥機の排ガスを除塵機で除塵し、上記焼却灰と
上記粉体と上記各除塵機で捕集した粉じんとを固
化処理することを特徴とする放射性廃棄物の処理
方法。 ２ 乾燥機がボール型熱風乾燥機である特許請求
の範囲第１項記載の放射性廃棄物の処理方法。 ３ 集塵機がセラミツクフイルタである特許請求
の範囲第１項または第２項記載の放射性廃棄物の
処理方法。[Scope of Claims] 1. Combustible miscellaneous solid waste and waste resin generated in a radioactive material handling facility are incinerated in an incinerator to produce incineration ash, and the combustion exhaust gas from the incinerator is removed by a dust remover, while the above-mentioned Concentrated waste liquid generated in facilities handling radioactive materials is dried in a dryer that uses the waste heat of the combustion exhaust gas as a heat source to turn it into powder, and the exhaust gas from the dryer is removed with a dust remover to produce the incinerated ash and the powder. and the dust collected by each of the above-mentioned dust removers are solidified. 2. The radioactive waste disposal method according to claim 1, wherein the dryer is a ball-type hot air dryer. 3. The radioactive waste treatment method according to claim 1 or 2, wherein the dust collector is a ceramic filter.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP8721083A JPH0230680B2 (en) | 1983-05-18 | 1983-05-18 | HOSHASEIHAIKIBUTSUNOSHORIHOHO |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP8721083A JPH0230680B2 (en) | 1983-05-18 | 1983-05-18 | HOSHASEIHAIKIBUTSUNOSHORIHOHO |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS59212799A JPS59212799A (en) | 1984-12-01 |
| JPH0230680B2 true JPH0230680B2 (en) | 1990-07-09 |
Family
ID=13908576
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP8721083A Expired - Lifetime JPH0230680B2 (en) | 1983-05-18 | 1983-05-18 | HOSHASEIHAIKIBUTSUNOSHORIHOHO |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0230680B2 (en) |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6159299A (en) * | 1984-08-31 | 1986-03-26 | 株式会社日立製作所 | Method and device for treating radioactive waste |
| JPH077109B2 (en) * | 1986-11-08 | 1995-01-30 | 日本碍子株式会社 | How to dispose of radioactive waste |
| JP3844327B2 (en) * | 1999-07-23 | 2006-11-08 | 日本碍子株式会社 | Method and apparatus for processing radioactive graphite |
-
1983
- 1983-05-18 JP JP8721083A patent/JPH0230680B2/en not_active Expired - Lifetime
Also Published As
| Publication number | Publication date |
|---|---|
| JPS59212799A (en) | 1984-12-01 |
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