JPS6025496A - How to dispose of radioactive waste - Google Patents
How to dispose of radioactive wasteInfo
- Publication number
- JPS6025496A JPS6025496A JP13397383A JP13397383A JPS6025496A JP S6025496 A JPS6025496 A JP S6025496A JP 13397383 A JP13397383 A JP 13397383A JP 13397383 A JP13397383 A JP 13397383A JP S6025496 A JPS6025496 A JP S6025496A
- Authority
- JP
- Japan
- Prior art keywords
- radioactive waste
- glass
- radioactive
- chamber
- waste
- 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
- 239000002901 radioactive waste Substances 0.000 title claims description 21
- 230000008018 melting Effects 0.000 claims description 26
- 238000002844 melting Methods 0.000 claims description 26
- 239000011521 glass Substances 0.000 claims description 16
- 239000006060 molten glass Substances 0.000 claims description 12
- 238000000034 method Methods 0.000 claims description 10
- 239000000941 radioactive substance Substances 0.000 claims description 3
- 239000000463 material Substances 0.000 description 5
- 239000002699 waste material Substances 0.000 description 5
- 238000001035 drying Methods 0.000 description 4
- 239000007789 gas Substances 0.000 description 4
- 239000000203 mixture Substances 0.000 description 4
- 150000003839 salts Chemical class 0.000 description 4
- 239000007788 liquid Substances 0.000 description 3
- 238000011282 treatment Methods 0.000 description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 3
- VYPSYNLAJGMNEJ-UHFFFAOYSA-N Silicium dioxide Chemical compound O=[Si]=O VYPSYNLAJGMNEJ-UHFFFAOYSA-N 0.000 description 2
- 238000006243 chemical reaction Methods 0.000 description 2
- 238000005352 clarification Methods 0.000 description 2
- 238000002485 combustion reaction Methods 0.000 description 2
- 238000007796 conventional method Methods 0.000 description 2
- 238000010438 heat treatment Methods 0.000 description 2
- 239000004615 ingredient Substances 0.000 description 2
- 230000007774 longterm Effects 0.000 description 2
- 239000012857 radioactive material Substances 0.000 description 2
- 239000010802 sludge Substances 0.000 description 2
- 239000002910 solid waste Substances 0.000 description 2
- 241001585714 Nola Species 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
- 241000750631 Takifugu chinensis Species 0.000 description 1
- 229910045601 alloy Inorganic materials 0.000 description 1
- 239000000956 alloy Substances 0.000 description 1
- 239000004568 cement Substances 0.000 description 1
- 229910001567 cementite Inorganic materials 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 239000004927 clay Substances 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- -1 ditumene Substances 0.000 description 1
- 230000020169 heat generation Effects 0.000 description 1
- 229910001026 inconel Inorganic materials 0.000 description 1
- KSOKAHYVTMZFBJ-UHFFFAOYSA-N iron;methane Chemical compound C.[Fe].[Fe].[Fe] KSOKAHYVTMZFBJ-UHFFFAOYSA-N 0.000 description 1
- 238000004898 kneading Methods 0.000 description 1
- 239000010808 liquid waste Substances 0.000 description 1
- 238000003672 processing method Methods 0.000 description 1
- 239000011347 resin Substances 0.000 description 1
- 229920005989 resin Polymers 0.000 description 1
- 239000000377 silicon dioxide Substances 0.000 description 1
- 229910052938 sodium sulfate Inorganic materials 0.000 description 1
- 229910052979 sodium sulfide Inorganic materials 0.000 description 1
- GRVFOGOEDUUMBP-UHFFFAOYSA-N sodium sulfide (anhydrous) Chemical compound [Na+].[Na+].[S-2] GRVFOGOEDUUMBP-UHFFFAOYSA-N 0.000 description 1
- 235000011152 sodium sulphate Nutrition 0.000 description 1
- 238000007711 solidification Methods 0.000 description 1
- 230000008023 solidification Effects 0.000 description 1
- 238000003756 stirring Methods 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
Landscapes
- Processing Of Solid Wastes (AREA)
- Fertilizers (AREA)
- Treatment Of Sludge (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】
木光り］は原子力発電所（ＢＷＲ）等から発生する放射
性廃棄物の処理方法に関する。DETAILED DESCRIPTION OF THE INVENTION [Kimikari] relates to a method for treating radioactive waste generated from nuclear power plants (BWR) and the like.
放射性廃棄物の処理方法として従来、セメシト固化、ピ
チューメン固化、プラスチック１Ｍ化するものがある。Conventional methods for disposing of radioactive waste include solidifying it with cementite, solidifying it with picumen, and converting it into 1M plastic.
これらの処理方法は濃縮ｔＭ’ｄを例にとれば、ｅ、’
ｌｄ１Ｍ液にセメント、じチューメン、プラスチック等
を加え、これを混練することによって、その中に放射性
廃棄物を取り込ませるというものである。しかしながら
、これらの処理方法によると減容化していない放射性廃
棄物に混合物を加えて固化するため、同化後の体積はか
なり増大することになる。また濃縮廃液の主成分である
Ｎａ２５Ｏ４（硫酸ナトリウム）は固化体の中ＱτＪ■
り込まれてもそΩ゛まま塩の形で存在するため、水に溶
出し易い等の問題があった。さらに従来方法によれば、
放射性廃棄物、例えば濃縮廃液、可燃性固体廃棄物、廃
樹脂、スラッジ等を乾燥、焼却同化処理するのにそれぞ
れ別個の装置を用いるので手間のかかる作業となってい
た。These processing methods, taking concentrated tM'd as an example, e, '
By adding cement, ditumene, plastic, etc. to the ld1M solution and kneading the mixture, radioactive waste is incorporated into the mixture. However, according to these treatment methods, a mixture is added to radioactive waste that has not been reduced in volume and solidified, resulting in a considerable increase in volume after assimilation. In addition, Na25O4 (sodium sulfate), which is the main component of the concentrated waste liquid, is present in the solidified material with QτJ■
Even if it is incorporated, it remains in the form of a salt, which poses problems such as being easily eluted into water. Furthermore, according to the conventional method,
Separate equipment is used to dry, incinerate, and assimilate radioactive waste, such as concentrated liquid waste, combustible solid waste, waste resin, and sludge, making the process time-consuming.
本発明はこのような従来の開所を解決することを目的と
し、原子力発電所等から発生する放射性廃棄物をカラス
電気溶融炉に投入し、該ｊ５ラス電気溶融炉の溶融カラ
スによって１ａ記放射性廃棄物を乾燥、焼却するととも
に該溶融ガラス中に溶融せしめ、この放射性物質を封入
した溶１ｆｉガラスを容器に流し込んで固化する構成の
放射性廃棄物の処理方法を提供することによって、その
目的を達成するものであり、これにより、固化体の体積
を減少することができるとともに固化体の中にＮａ２Ｓ
Ｏ４が塩の形で存在するのを防ぐことができ、また乾燥
、焼却同化処理を一括して行う仁とができるものである
。The purpose of the present invention is to solve the problem of conventional waste disposal, and the radioactive waste generated from nuclear power plants, etc. is charged into a Karasu electric melting furnace, and the radioactive waste described in 1a is processed by the melting glass of the J5 electric melting furnace. This objective is achieved by providing a method for disposing of radioactive waste, which comprises drying and incinerating the substance, melting it in the molten glass, and pouring the molten 1fi glass containing the radioactive substance into a container and solidifying it. As a result, the volume of the solidified body can be reduced and Na2S is added to the solidified body.
It is possible to prevent O4 from existing in the form of salt, and it is also possible to perform drying, incineration and assimilation treatments all at once.
以下本発明の方法をその一実施例を示す図面に基づいて
詳細に説明する。The method of the present invention will be explained in detail below based on the drawings showing one embodiment thereof.
図において、（１）は本発明方法に用いるガラス電気溶
融炉である。（２）はこのガラス電気溶融炉（１）の焼
却溶融室、（３）は焼却溶融室（２）ＶＣ−隣接して設
けられた清澄室で、これら焼却溶融室（２）と清澄室（
３ンは堰（４）で仕切られて低部のみを連通せしめられ
ている。（５）は焼却溶融室（２）の底壁を貫通して設
けられた一対の電極で、焼却溶融室（２）と清澄室（３
）の画室にわたってｒ朕られたガラス（６）の内部にジ
ュール熱を発生させガラス（６）を溶融する働きをなす
ものである。（７）は焼却溶融室（２）の底壁を貫通し
て焼却溶ｋｊ室底曲にその多数の開口を臨捷しめて設け
られた空気供給管で、インコネル等の耐熱耐蝕合金で製
作され、空気を焼却溶融室（２）内に供給して溶融反応
を促進する等の働きをなすものである。（８）は清澄室
（３）の天井壁を貫通して設けられた抵抗加熱線で、清
澄室（３）内のノコラス（６）に触れない程度で室内に
突出せしめられ、清澄室（３）内のガラス（６） ’ｆ
−加熱する働きをなすものである。なお図中、（９）は
焼却溶融室（２）の側壁上部に設けられた放射性廃棄物
の投入口、０１は焼却溶融室（２）の天井壁に設けられ
た排ガス出口、０υは清澄室（３）の側壁り部に設けら
れた湯口である。In the figure, (1) is a glass electric melting furnace used in the method of the present invention. (2) is the incineration melting chamber of this electric glass melting furnace (1), and (3) is the fining chamber installed adjacent to the incineration melting chamber (2) VC.
The third tunnel is separated by a weir (4), allowing only the lower part to communicate. (5) is a pair of electrodes installed through the bottom wall of the incineration melting chamber (2) and the fining chamber (3).
) The function is to generate Joule heat inside the glass (6) that has been scratched across the compartments of the glass (6) to melt the glass (6). (7) is an air supply pipe that penetrates the bottom wall of the incineration melting chamber (2) and has a large number of openings in the bottom curve of the incineration melting chamber, and is made of a heat-resistant and corrosion-resistant alloy such as Inconel. The function is to supply air into the incineration melting chamber (2) to promote the melting reaction. (8) is a resistance heating wire installed through the ceiling wall of the fining chamber (3), and is made to protrude into the chamber without touching the nochorus (6) in the fining chamber (3). ) in the glass (6) 'f
-It functions to heat. In the figure, (9) is the radioactive waste inlet installed on the upper side wall of the incineration melting chamber (2), 01 is the exhaust gas outlet installed on the ceiling wall of the incineration melting chamber (2), and 0υ is the clarification chamber. (3) is a sprue provided on the side wall.
このような構成のガラス電気溶融炉（１）を用いて、次
に放射性廃棄物の処理方法を順を追って説明する。Next, a method for disposing of radioactive waste will be explained step by step using the glass electric melting furnace (1) having such a configuration.
まず、あらかじめガスなどの直火、または電熱により８
００℃前後にハラスを加熱した後、電極（５）に交流を
与える。そうすると、電４ｉ＆ （５）問に電流が流れ
、カラス（６）内部にジュール熱が発生する。この発熱
により、その後連続的にガラス（６）は溶融せしめられ
る。このときガラス（６）の溶融温度は１２００〜１５
００℃程度である。First, heat the heat over an open flame such as gas or electric heat.
After heating the Harasu to around 00°C, alternating current is applied to the electrode (5). Then, a current flows between the electrodes 4i and (5), and Joule heat is generated inside the crow (6). Due to this heat generation, the glass (6) is then continuously melted. At this time, the melting temperature of glass (6) is 1200 to 15
It is about 00℃.
次に、放射性廃棄物（例えば濃縮廃液、スラッジ）を投
入口（９）から焼却溶融室（２）内に投入する。Next, radioactive waste (for example, concentrated waste liquid, sludge) is introduced into the incineration melting chamber (2) through the input port (9).
このとき、濃縮廃液を大敏に投入する場合は、ガラス（
６）の成分調整のため粘土等の５ｘＯｚ （酸化ケイ巣
）成分を加える。また、加燃性固体廃棄物を大量に投入
する場合は、力、ラス（６）の成分調整のためＪ５ラス
ガレットを加える。At this time, if you want to pour in the concentrated waste liquid, use a glass (
Add 5xOz (silica oxide) ingredients such as clay to adjust the ingredients in step 6). In addition, when a large amount of combustible solid waste is to be input, J5 lath galette is added to adjust the composition of the lath (6).
投入された放射性廃棄物は、焼却溶融室（２）内におい
て溶融ガラス（６）により加熱乾燥せしめられ、空気供
給管（７）から供給される空気によって燃焼せしめられ
る。これにより、放射性廃棄物は減容されることになる
。なお、供給された空気は溶融ガラス（６）を攪拌して
溶融反応を促進（特に灰とよく混合）するだけでなく、
溶融ガラス（６）により予熱されて良好な乾燥、燃焼用
空気と々る。燃焼等により発生したＳｏ２．ＣＯ２等の
排ガスは排ガス出口ｕＱから排出し、ｖ１゛刀ス処理設
備にて処理する。The injected radioactive waste is heated and dried by molten glass (6) in the incineration melting chamber (2), and is combusted by air supplied from the air supply pipe (7). This will reduce the volume of radioactive waste. In addition, the supplied air not only stirs the molten glass (6) and promotes the melting reaction (particularly mixes well with the ash), but also
It is preheated by the molten glass (6) to provide good drying and combustion air. So2 generated by combustion etc. Exhaust gases such as CO2 are discharged from the exhaust gas outlet uQ and processed in the v1 treatment facility.
このように乾燥、燃焼せしめられた放射性廃棄物の乾燥
塩および焼却灰は、溶融ガラス（６）に充分ｍ ＋Ａｌ
ｌする。そうするとこの放射性物質を封入した溶融ガラ
ス（６） Ｖｉ堰（４）を潜って清廉室（３）に流入す
ることになる。The dry salt and incineration ash of the radioactive waste dried and burned in this way are sufficient for the molten glass (6).
I do it. Then, the molten glass (6) containing this radioactive material will flow through the Vi weir (4) and into the purity chamber (3).
次に清澄室（３）において、放射性物質を封入した溶融
カラス（６）を均質にするとともに、残存気泡の除去を
行う。そして清澄した溶融ガラス（６）を湯口９］）よ
り準備した容器に流し込んで冷却し、刀ラス固化体とす
る。得られたガラス固化体は耐水溶性、耐熱性、耐火性
に優れ、長期保管において安定しているという特徴があ
る。Next, in the clarification chamber (3), the molten glass (6) containing the radioactive substance is made homogeneous and any remaining air bubbles are removed. The clarified molten glass (6) is then poured into a prepared container through a sprue 9 and cooled to form a solidified glass. The obtained vitrified material has excellent water solubility, heat resistance, and fire resistance, and is stable during long-term storage.
以り本発明の方法によれば、放射性廃棄物を乾燥、焼却
して減容化した後に溶融ガラス中に溶融せしめるので、
固化体の体積を減少することができるとともに固化体の
中にＮａＢ５Ｏ４が塩の形で存在するのを防ぐことがで
きる。また７３ラス′市気溶融炉を用いるので、乾燥、
焼却、固化処理を一括して行うことができ、放射性物質
を飛散させるような虞れも少ない。さらに得られた固化
体はノｊラス固化体であるので、耐水溶性、耐熱性、耐
火性に優れるとともに長期保管において安定であり、放
射性廃棄物の固化体として最適である。Therefore, according to the method of the present invention, radioactive waste is dried and incinerated to reduce its volume and then melted into molten glass.
The volume of the solidified body can be reduced and the presence of NaB5O4 in the form of salt in the solidified body can be prevented. In addition, since we use a 73 ras 'commercial air melting furnace, drying,
Incineration and solidification can be performed all at once, and there is little risk of scattering radioactive materials. Furthermore, since the obtained solidified material is a nolas solidified material, it has excellent water solubility, heat resistance, and fire resistance, and is stable during long-term storage, making it optimal as a solidified material for radioactive waste.
図面は本発明方法に用いるカラス電気溶融炉の−例を示
す縦断面図である。
（１）・・・ｊｆｆラス電気溶融炉、（６）・・・１３
ラス（溶融ガラス）
代理人 祿 木 義 弘The drawing is a longitudinal sectional view showing an example of a glass electric melting furnace used in the method of the present invention. (1)...jff lath electric melting furnace, (6)...13
Las (molten glass) Agent Yoshihiro Kiyoshi
Claims (1)
ス電気溶融炉に投入し、該ガラス′１は気溶融炉の溶融
カラスによって前記放射性廃棄物を乾燥、焼却するとと
もに該溶融ガラス中に溶融せしめ、この放射性物質を封
入した溶融ガラスを容器に流し込んで固化することを特
徴とする放射性廃棄物の処理方法。(2) Radioactive waste generated from nuclear power plants, cities, etc. is put into an electric glass melting furnace, and the radioactive waste is dried and incinerated by the melting glass of the gas melting furnace, and the radioactive waste is melted into the molten glass. A method for disposing of radioactive waste characterized by pouring molten glass containing radioactive substances into a container and solidifying it.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP13397383A JPS6025496A (en) | 1983-07-21 | 1983-07-21 | How to dispose of radioactive waste |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP13397383A JPS6025496A (en) | 1983-07-21 | 1983-07-21 | How to dispose of radioactive waste |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS6025496A true JPS6025496A (en) | 1985-02-08 |
Family
ID=15117398
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP13397383A Pending JPS6025496A (en) | 1983-07-21 | 1983-07-21 | How to dispose of radioactive waste |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6025496A (en) |
-
1983
- 1983-07-21 JP JP13397383A patent/JPS6025496A/en active Pending
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