JPH04240B2 - - Google Patents
Info
- Publication number
- JPH04240B2 JPH04240B2 JP10190284A JP10190284A JPH04240B2 JP H04240 B2 JPH04240 B2 JP H04240B2 JP 10190284 A JP10190284 A JP 10190284A JP 10190284 A JP10190284 A JP 10190284A JP H04240 B2 JPH04240 B2 JP H04240B2
- Authority
- JP
- Japan
- Prior art keywords
- cartridge
- waste liquid
- radioactive waste
- glass fibers
- glass
- 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
Links
- 239000003365 glass fiber Substances 0.000 claims description 36
- 239000007788 liquid Substances 0.000 claims description 30
- 239000002901 radioactive waste Substances 0.000 claims description 25
- 238000010438 heat treatment Methods 0.000 claims description 14
- 238000004519 manufacturing process Methods 0.000 claims description 8
- 239000000835 fiber Substances 0.000 claims description 6
- 238000000034 method Methods 0.000 claims description 5
- 239000011230 binding agent Substances 0.000 description 13
- 239000011521 glass Substances 0.000 description 12
- 238000002844 melting Methods 0.000 description 7
- 230000008018 melting Effects 0.000 description 7
- 239000000428 dust Substances 0.000 description 6
- 239000000203 mixture Substances 0.000 description 6
- 238000005516 engineering process Methods 0.000 description 4
- 239000012857 radioactive material Substances 0.000 description 3
- 239000002994 raw material Substances 0.000 description 3
- 239000002699 waste material Substances 0.000 description 3
- 239000000463 material Substances 0.000 description 2
- 239000002002 slurry Substances 0.000 description 2
- 229910018072 Al 2 O 3 Inorganic materials 0.000 description 1
- 241001391944 Commicarpus scandens Species 0.000 description 1
- 241000196324 Embryophyta Species 0.000 description 1
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 description 1
- 229910004298 SiO 2 Inorganic materials 0.000 description 1
- 229910000831 Steel Inorganic materials 0.000 description 1
- 229910052770 Uranium Inorganic materials 0.000 description 1
- 238000010521 absorption reaction Methods 0.000 description 1
- 239000011449 brick Substances 0.000 description 1
- 239000006227 byproduct Substances 0.000 description 1
- 238000004140 cleaning Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000004880 explosion Methods 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 239000002927 high level radioactive waste Substances 0.000 description 1
- 238000010309 melting process Methods 0.000 description 1
- 239000006060 molten glass Substances 0.000 description 1
- 229910017604 nitric acid Inorganic materials 0.000 description 1
- 239000012254 powdered material Substances 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 239000000047 product Substances 0.000 description 1
- 238000012958 reprocessing Methods 0.000 description 1
- 238000005096 rolling process Methods 0.000 description 1
- 239000005394 sealing glass Substances 0.000 description 1
- 238000007493 shaping process Methods 0.000 description 1
- 230000035939 shock Effects 0.000 description 1
- 239000002915 spent fuel radioactive waste Substances 0.000 description 1
- 238000009987 spinning Methods 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- 239000010959 steel Substances 0.000 description 1
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
Landscapes
- Photographic Developing Apparatuses (AREA)
- Glass Compositions (AREA)
Description
【発明の詳細な説明】
本発明は、放射性廃液を廃棄処分するに際し、
放射性廃液を含浸させて加熱溶融し、ガラス固化
させるのに使用される放射性廃液処理用カートリ
ツジおよびその製造法に関する。[Detailed Description of the Invention] The present invention provides the following features when disposing of radioactive waste liquid:
The present invention relates to a cartridge for treating radioactive waste liquid used for impregnating radioactive waste liquid, heating and melting it, and vitrifying it, and a method for manufacturing the same.
電子力発電において使用された使用済み燃料を
再処理工場において再処理するに際し、ウラン、
超ウラン元素および核分裂生成物を含んだ硝酸を
含む高レベル放射性廃液が副生する。そこで、か
かる放射性廃液を安全にかつ効率的に廃棄する技
術が望まれている。 When spent fuel used in electronic power generation is reprocessed at a reprocessing plant, uranium,
A high-level radioactive waste liquid containing nitric acid containing transuranic elements and fission products is produced as a by-product. Therefore, a technology for safely and efficiently disposing of such radioactive waste liquid is desired.
従来、この放射性廃液を処理するには、放射性
廃液を直接または脱硝濃縮してスラリー状とし、
ガラス原料と混合して高温のガラス溶融炉に供給
し、炉内で廃液中の液体成分を蒸発させると共に
放射性物質をガラス中に溶融させて、この溶融ガ
ラスをスチール製の容器に注入して固化する技術
が開発されてきている。 Conventionally, in order to treat this radioactive waste liquid, the radioactive waste liquid is either directly or denitrified and concentrated to form a slurry.
It is mixed with glass raw materials and supplied to a high-temperature glass melting furnace, where the liquid components in the waste liquid are evaporated and the radioactive materials are melted into the glass.The molten glass is poured into a steel container and solidified. Technology has been developed to do so.
しかしながら、かかる従来技術においては、ガ
ラス原料としてビーズ状あるいは粉末状のものが
使用されていたので、ガラス溶融炉内で廃液が激
しく沸騰する際、多量の放射性物質を含む粉塵が
発生し、排ガスに同伴して流出する。このため、
排ガス処理系に相当厳重な粉塵処理設備が必要で
あつた。また、粉塵によつて配管が閉塞される可
能性があつた。さらに、炉内のレンガが熱衝撃に
よつて割れて１部脱落したりする危険性があつ
た。 However, in such conventional technology, bead-shaped or powdered materials are used as glass raw materials, so when the waste liquid boils violently in the glass melting furnace, a large amount of dust containing radioactive materials is generated, and the exhaust gas is It accompanies it and flows out. For this reason,
The exhaust gas treatment system required extremely strict dust treatment equipment. In addition, there was a possibility that the pipes would be blocked by dust. Furthermore, there was a risk that the bricks inside the furnace would crack due to thermal shock and some of them would fall off.
そこで、近年、ガラス原料としてガラス繊維を
用いることが試みられている。ガラス繊維を用い
た場合には、廃液がガラス繊維間の隙間に含浸さ
れ、溶融中に発生する粉塵はガラス繊維のフイル
ター効果によつて捕捉され、飛散することが防止
される利点がある。 Therefore, in recent years, attempts have been made to use glass fiber as a glass raw material. When glass fibers are used, there is an advantage that the waste liquid is impregnated into the gaps between the glass fibers, and the dust generated during melting is captured by the filter effect of the glass fibers and prevented from scattering.
本発明者らは、この技術を実施化するため鋭意
研究した結果、使用するガラス繊維として幾つか
の特性が要求されることが分つた。 As a result of intensive research to put this technology into practice, the present inventors found that the glass fiber used must have several characteristics.
まず、ガラス繊維は、ハンドリングを良好とす
るために所定形状に成形されたカートリツジとし
て提供されることが好ましい。 First, the glass fiber is preferably provided as a cartridge shaped into a predetermined shape for easy handling.
次に、このカートリツジは、有機質あるいは無
機質のいずれのバインダーも用いないことが好ま
しい。有機質のバインダーを用いると、加熱溶融
工程において可燃性ガスが発生し、爆発する危険
性がある。このため、ヒートクリーニングを行な
つてバインダーを飛ばすことが考えられるが、そ
の場合には手間やコストがかかる。一方、無機質
のバインダーを用いた場合には、加熱溶融におい
てガラス成分にバインダーの成分が混入し、全体
としてガラス成分が変化してしまうので、バイン
ダーの成分が加わつた状態で全体の組成が目標値
に達するように各成分を調整する必要がある。し
かし、ガラス繊維にバインダーを付与する場合、
バインダーの添加量の調整は実際にはなかなか難
しく、また、バインダーの混合が不均一になりや
すいので、組成が一定しない不都合がある。さら
に、加熱した際にバインダー中には揮発しやすい
成分と揮発しにくい成分とがあるのでこれによつ
ても組成が変化する。結局、無機質のバインダー
を用いた場合には、最終的なガラス成分の組成の
調整が難しくなる欠点がある。 Next, the cartridge preferably does not use any organic or inorganic binder. If an organic binder is used, flammable gas will be generated during the heating and melting process, and there is a risk of explosion. For this reason, it is conceivable to perform heat cleaning to remove the binder, but in that case it is time consuming and costly. On the other hand, when an inorganic binder is used, the binder component mixes with the glass component during heating and melting, changing the overall glass component. It is necessary to adjust each component to reach the following. However, when adding a binder to glass fibers,
It is actually quite difficult to adjust the amount of binder added, and the mixture of binders tends to be non-uniform, so there is a problem that the composition is not constant. Furthermore, since there are components in the binder that easily volatilize and components that do not volatilize easily when heated, the composition also changes due to these components. After all, when an inorganic binder is used, there is a drawback that it becomes difficult to adjust the composition of the final glass component.
さらに、カートリツジは良好な保水性と、ある
程度の強度が必要とされる。保水性が良いことに
よつて、放射性廃液をできるだけ多く吸収させる
ことができ、ある程度の強度を有することによつ
て、例えばカートリツジの供給装置から遠く離れ
た放射性廃液を含浸させる装置等にカートリツジ
を投入しても破損を防止できる。 Furthermore, the cartridge must have good water retention and a certain degree of strength. Due to its good water retention, it is possible to absorb as much radioactive waste liquid as possible, and because it has a certain degree of strength, it is possible, for example, to insert the cartridge into a radioactive waste liquid impregnating device far away from the cartridge supply device. damage can be prevented.
したがつて、本発明の目的は、ガラス繊維をバ
インダーを用いることなく所定形状に成形し、良
好な保水性および所定の強度が得られるようにし
た放射性廃液処理用カートリツジおよびその製造
法を提供することにある。 Therefore, an object of the present invention is to provide a cartridge for radioactive waste liquid treatment in which glass fibers are molded into a predetermined shape without using a binder to provide good water retention and a predetermined strength, and a method for manufacturing the same. There is a particular thing.
すなわち、本発明の第１の発明は、ガラス繊維
が部分的に加熱融着されブロツク状に成形された
放射性廃液処理用カートリツジである。 That is, the first aspect of the present invention is a cartridge for treating radioactive waste liquid, which is formed into a block shape by partially heat-sealing glass fibers.
また、本発明の第２の発明は、ガラス繊維を型
中に充填し、これを加熱処理して部分的に融着さ
せ、ブロツク状に成形する放射性廃液処理用カー
トリツジの製造法である。 A second aspect of the present invention is a method for manufacturing a cartridge for treating radioactive waste liquid, which involves filling a mold with glass fibers, heating them to partially fuse them, and forming them into a block shape.
したがつて、カートリツジは有機質および無機
質のバインダーを含有せず、加熱溶融時に可燃性
ガスが発生したり、ガラス成分が変化したりする
ことがない。そして、ガラス繊維を部分的に融着
して整形したことにより、良好な保水性および所
定の強度が得られる。 Therefore, the cartridge does not contain organic or inorganic binders, and no flammable gas is generated or the glass components change during heating and melting. By partially fusing and shaping the glass fibers, good water retention and a predetermined strength can be obtained.
以下、本発明の実施例を図面を参照して説明す
る。 Embodiments of the present invention will be described below with reference to the drawings.
本発明において使用されるガラス繊維は、短繊
維、長繊維のいずれでもよいが、本発明の場合は
特に短繊維が適している。ガラス繊維の組成とし
ては、例えばSiO260.2wt％、B2O319.0wt％、
Li2O4.0wt％、BaO4.0wt％、CaO4.0wt％、
ZnO4.0wt％、Al2O34.8wt％のものが放射性物質
をガラス固化するのに特に適している。ガラス繊
維の平均径としては、８〜15μが好ましい。平均
径が8μ未満の場合には良好な吸水性が得られな
くなる。また、平均径が15μを超えると、紡糸工
程における生産性が悪くなり、かつ、ガラス繊維
相互の融着箇所が少なくなつて形状が崩れやすく
なる。 The glass fibers used in the present invention may be either short fibers or long fibers, but short fibers are particularly suitable for the present invention. The composition of the glass fiber is, for example, SiO 2 60.2wt%, B 2 O 3 19.0wt%,
Li 2 O4.0wt%, BaO4.0wt%, CaO4.0wt%,
ZnO 4.0wt% and Al 2 O 3 4.8wt% are particularly suitable for vitrifying radioactive materials. The average diameter of the glass fibers is preferably 8 to 15μ. If the average diameter is less than 8μ, good water absorption cannot be obtained. Furthermore, if the average diameter exceeds 15μ, the productivity in the spinning process will be poor, and the number of points where the glass fibers will be fused to each other will be reduced, making the shape likely to collapse.
本発明においては、第１図に示すように、まず
このガラス繊維１をシート状に形成する。そして
このシートをある一定の形状に切断し、所定の重
量にあう長さとする。次に第２図に示すように、
このシートを圧延しながら所定の径になるように
巻き上げる。さらに、第３図に示すように、例え
ば２つ割りのステンレス製の型２に巻き上げたシ
ートを充填する。このとき、ガラス繊維１の密度
は、170〜230Kg／m3となるように調整することが
好ましい。密度が170Kg／m3未満の場合には充分
な圧縮強度が得られず、かつ、保水された放射性
廃液に対するガラス重量を適性に保つたとき、体
積が大きくなりすぎて大型の加熱溶融炉が必要と
なる。密度が230Kg／m3を超えると、全体として
割れやすくなり、落下強度が充分に得られず、か
つ、相対的にガラス繊維の間隙が小さくなるので
保水率が低下する。なお、ガラス繊維１をシート
状にすることなく、そのまま圧縮して第３図に示
す型２に充填するようにしてもよい。 In the present invention, as shown in FIG. 1, the glass fiber 1 is first formed into a sheet shape. This sheet is then cut into a certain shape to a length that matches a predetermined weight. Next, as shown in Figure 2,
While rolling this sheet, it is rolled up to a predetermined diameter. Furthermore, as shown in FIG. 3, the rolled up sheet is filled into a mold 2 made of stainless steel, which is divided into two parts, for example. At this time, the density of the glass fiber 1 is preferably adjusted to 170 to 230 Kg/m 3 . If the density is less than 170Kg/m 3 , sufficient compressive strength cannot be obtained, and when the weight of the glass is maintained at an appropriate level for the water-retained radioactive waste liquid, the volume becomes too large, requiring a large heating and melting furnace. becomes. When the density exceeds 230 Kg/m 3 , the entire material becomes easy to break, insufficient drop strength is not obtained, and the gaps between the glass fibers become relatively small, resulting in a decrease in water retention. Note that the glass fiber 1 may be compressed as it is and filled into the mold 2 shown in FIG. 3 without being made into a sheet.
このようにガラス繊維１を型２に充填した後、
710±15℃にて35±５分間加熱処理し、ガラス繊
維１を部分的に融着させる。加熱温度が695℃よ
りも低く、あるいは加熱時間が30分よりも短い場
合には、ガラス繊維１の融着が充分になされず、
成形性が悪くなる。また、加熱温度が725℃より
も高く、あるいは加熱時間が40分よりも長い場合
には、ガラス繊維１が溶融して収縮し、保水性が
悪くなり、割れやすくなる。 After filling the mold 2 with glass fiber 1 in this way,
Heat treatment is performed at 710±15° C. for 35±5 minutes to partially fuse the glass fibers 1. If the heating temperature is lower than 695°C or the heating time is shorter than 30 minutes, the glass fibers 1 will not be sufficiently fused,
Formability deteriorates. Furthermore, if the heating temperature is higher than 725° C. or the heating time is longer than 40 minutes, the glass fibers 1 will melt and shrink, resulting in poor water retention and becoming more likely to break.
この加熱処理の後、型２を放冷してガラス繊維
１を取出すことにより、第４図に示すようなカー
トリツジ３を得ることができる。この実施例の場
合、カートリツジ３は円筒形をなしているが、直
方体、球あるいはこれらに準ずる形状でもよい。
カートリツジ３の大きさは、直径70mm、高さ70mm
程度が適当である。そして、このカートリツジ３
は、保水量が2.5／Kgカートリツジ以上あり、
20ｍの高さから落下しても割れにくい落下強度を
有する。 After this heat treatment, the mold 2 is left to cool and the glass fibers 1 are taken out, thereby obtaining a cartridge 3 as shown in FIG. 4. In this embodiment, the cartridge 3 has a cylindrical shape, but it may also be a rectangular parallelepiped, a sphere, or a similar shape.
The size of cartridge 3 is 70mm in diameter and 70mm in height.
The degree is appropriate. And this cartridge 3
has a water retention capacity of 2.5/Kg or more,
It has a drop strength that makes it difficult to break even when dropped from a height of 20 meters.
このカートリツジ３に脱硝濃縮してスラリー状
とした放射性廃液を含浸させ、マイクロ波加熱炉
にて1000〜1100℃で加熱溶融した結果、粉塵の発
生は極めて少なかつた。 This cartridge 3 was impregnated with a radioactive waste liquid that had been denitrified and concentrated into a slurry form, and heated and melted in a microwave heating furnace at 1000 to 1100°C. As a result, very little dust was generated.
以上説明したように、本発明によれば、ガラス
繊維をブロツク状に成形してカートリツジにした
ので、ハンドリングが良好となる。また、バイン
ダーを用いずにガラス繊維の１部を融着して成形
したので、放射性廃液を含浸させて加熱溶融する
際に、可燃性ガス等が生じることなく、粉塵の発
生量が少なくなり、かつ、ガラス成分の組成を均
一に保つことができる。さらに、保水性が良好で
適度の強度を有するものが得られる。 As explained above, according to the present invention, since glass fiber is formed into a block shape to form a cartridge, handling is improved. In addition, since a part of the glass fiber is fused and molded without using a binder, no flammable gas is generated when impregnated with radioactive waste liquid and heated and melted, reducing the amount of dust generated. Moreover, the composition of the glass components can be kept uniform. Furthermore, a material with good water retention and appropriate strength can be obtained.
図はいずれも本発明の実施例を説明するもので
あり、第１図はガラス繊維をシート状にした状態
の斜視図、第２図はガラス繊維をまるめて所定の
径にした状態の斜視図、第３図はガラス繊維を充
填する型の斜視図、第４図は製造された放射性廃
液処理用カートリツジの斜視図である。
図中、１はガラス繊維、２は型、３は放射性廃
液処理用カートリツジである。
The figures are for explaining embodiments of the present invention. Figure 1 is a perspective view of glass fibers formed into a sheet, and Figure 2 is a perspective view of glass fibers rolled into a predetermined diameter. , FIG. 3 is a perspective view of a mold filled with glass fiber, and FIG. 4 is a perspective view of a manufactured cartridge for treating radioactive waste liquid. In the figure, 1 is glass fiber, 2 is a mold, and 3 is a cartridge for treating radioactive waste liquid.
Claims (1)
状に成形されたことを特徴とする放射性廃液処理
用カートリツジ。 ２ 特許請求の範囲第１項において、前記ガラス
繊維として短繊維が用いられた放射性廃液処理用
カートリツジ。 ３ 特許請求の範囲第１項または第２項におい
て、前記ガラス繊維は平均径が８〜15μである放
射性廃液処理用カートリツジ。 ４ 特許請求の範囲第１項ないし第３項におい
て、密度が170〜230Kg／m3である放射性廃液処理
用カートリツジ。 ５ ガラス繊維を型中に充填し、これを加熱処理
して部分的に融着させ、ブロツク状に成形するこ
とを特徴とする放射性廃液処理用カートリツジの
製造法。 ６ 特許請求の範囲第５項において、前記ガラス
繊維として短繊維を用いる放射性廃液処理用カー
トリツジの製造法。 ７ 特許請求の範囲第５項または第６項におい
て、前記ガラス繊維として平均径が８〜15μのも
のを用いる放射性廃液処理用カートリツジの製造
法。 ８ 特許請求の範囲第５項ないし第７項におい
て、前記ガラス繊維を型中に充填する際、密度が
170〜230Kg／m3となるように調整する放射性廃液
処理用カートリツジの製造法。 ９ 特許請求の範囲第５項ないし第８項におい
て、前記加熱処理は710±15℃にて35±５分間行
なう放射性廃液処理用カートリツジの製造法。[Scope of Claims] 1. A cartridge for treating radioactive waste liquid, characterized in that glass fibers are partially heat-fused and molded into a block shape. 2. The cartridge for radioactive waste liquid treatment according to claim 1, wherein short fibers are used as the glass fibers. 3. The cartridge for radioactive waste liquid treatment according to claim 1 or 2, wherein the glass fibers have an average diameter of 8 to 15 μm. 4. A cartridge for treating radioactive waste liquid, which has a density of 170 to 230 Kg/m 3 as set forth in Claims 1 to 3. 5. A method for manufacturing a cartridge for radioactive waste liquid treatment, which comprises filling a mold with glass fibers, heat-treating them to partially fuse them, and forming them into a block shape. 6. The method of manufacturing a cartridge for radioactive waste liquid treatment according to claim 5, using short fibers as the glass fibers. 7. The method for producing a cartridge for radioactive waste liquid treatment according to claim 5 or 6, in which the glass fibers have an average diameter of 8 to 15 μm. 8 In claims 5 to 7, when the glass fibers are filled into a mold, the density is
A method for manufacturing a cartridge for treating radioactive waste liquid that is adjusted to 170 to 230 Kg/ m3 . 9. The method for producing a cartridge for radioactive waste liquid treatment according to claims 5 to 8, wherein the heat treatment is performed at 710±15°C for 35±5 minutes.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP10190284A JPS60244899A (en) | 1984-05-21 | 1984-05-21 | Cartridge for treating radioactive waste liquor and manufacture thereof |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP10190284A JPS60244899A (en) | 1984-05-21 | 1984-05-21 | Cartridge for treating radioactive waste liquor and manufacture thereof |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS60244899A JPS60244899A (en) | 1985-12-04 |
| JPH04240B2 true JPH04240B2 (en) | 1992-01-06 |
Family
ID=14312842
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP10190284A Granted JPS60244899A (en) | 1984-05-21 | 1984-05-21 | Cartridge for treating radioactive waste liquor and manufacture thereof |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS60244899A (en) |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS62222198A (en) * | 1986-03-25 | 1987-09-30 | 動力炉・核燃料開発事業団 | Manufacture of cartridge for processing radioactive waste liquor |
| JPH0721556B2 (en) * | 1988-03-28 | 1995-03-08 | 動力炉・核燃料料開発事業団 | Method for melting and solidifying glass of radioactive waste liquid with suppressed formation of gaseous ruthenium |
| JPH0915389A (en) * | 1995-06-27 | 1997-01-17 | Japan Atom Energy Res Inst | Radioactive nuclide adsorbent and its production method and volume reduction processing method for radioactive waste |
-
1984
- 1984-05-21 JP JP10190284A patent/JPS60244899A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS60244899A (en) | 1985-12-04 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| LAPS | Cancellation because of no payment of annual fees |