JPH055078B2 - - Google Patents
Info
- Publication number
- JPH055078B2 JPH055078B2 JP22106384A JP22106384A JPH055078B2 JP H055078 B2 JPH055078 B2 JP H055078B2 JP 22106384 A JP22106384 A JP 22106384A JP 22106384 A JP22106384 A JP 22106384A JP H055078 B2 JPH055078 B2 JP H055078B2
- Authority
- JP
- Japan
- Prior art keywords
- glass
- waste liquid
- reaction
- crushed
- radioactive 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.)
- Expired - Lifetime
Links
- 239000011521 glass Substances 0.000 claims description 55
- 238000000034 method Methods 0.000 claims description 28
- 239000007788 liquid Substances 0.000 claims description 23
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 21
- 239000002901 radioactive waste Substances 0.000 claims description 19
- 239000002994 raw material Substances 0.000 claims description 12
- 238000002156 mixing Methods 0.000 claims description 4
- 239000003513 alkali Substances 0.000 claims description 2
- 238000010438 heat treatment Methods 0.000 claims description 2
- 239000000155 melt Substances 0.000 claims description 2
- 239000000126 substance Substances 0.000 claims 2
- 235000019353 potassium silicate Nutrition 0.000 claims 1
- 238000003672 processing method Methods 0.000 claims 1
- 239000006060 molten glass Substances 0.000 description 13
- 238000001027 hydrothermal synthesis Methods 0.000 description 12
- 238000002844 melting Methods 0.000 description 12
- 230000008018 melting Effects 0.000 description 12
- 239000000463 material Substances 0.000 description 7
- 238000007711 solidification Methods 0.000 description 6
- 230000008023 solidification Effects 0.000 description 6
- 239000005388 borosilicate glass Substances 0.000 description 5
- 230000035484 reaction time Effects 0.000 description 5
- 238000003825 pressing Methods 0.000 description 4
- 238000012958 reprocessing Methods 0.000 description 4
- 239000002699 waste material Substances 0.000 description 4
- HEMHJVSKTPXQMS-UHFFFAOYSA-M Sodium hydroxide Chemical compound [OH-].[Na+] HEMHJVSKTPXQMS-UHFFFAOYSA-M 0.000 description 3
- 238000010586 diagram Methods 0.000 description 3
- 239000007787 solid Substances 0.000 description 3
- 239000002915 spent fuel radioactive waste Substances 0.000 description 3
- 230000006835 compression Effects 0.000 description 2
- 238000007906 compression Methods 0.000 description 2
- 239000006063 cullet Substances 0.000 description 2
- 238000012545 processing Methods 0.000 description 2
- 238000011160 research Methods 0.000 description 2
- 239000005368 silicate glass Substances 0.000 description 2
- 229910001220 stainless steel Inorganic materials 0.000 description 2
- 239000010935 stainless steel Substances 0.000 description 2
- 238000004017 vitrification Methods 0.000 description 2
- 229910019142 PO4 Inorganic materials 0.000 description 1
- 229910004298 SiO 2 Inorganic materials 0.000 description 1
- CDBYLPFSWZWCQE-UHFFFAOYSA-L Sodium Carbonate Chemical compound [Na+].[Na+].[O-]C([O-])=O CDBYLPFSWZWCQE-UHFFFAOYSA-L 0.000 description 1
- 229910003514 Sr(OH) Inorganic materials 0.000 description 1
- 239000000654 additive Substances 0.000 description 1
- 230000008602 contraction Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000010828 elution Methods 0.000 description 1
- 230000008020 evaporation Effects 0.000 description 1
- 238000001704 evaporation Methods 0.000 description 1
- 238000000605 extraction Methods 0.000 description 1
- 238000005259 measurement Methods 0.000 description 1
- 229910021645 metal ion Inorganic materials 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 230000001590 oxidative effect Effects 0.000 description 1
- 239000002245 particle Substances 0.000 description 1
- 239000010452 phosphate Substances 0.000 description 1
- NBIIXXVUZAFLBC-UHFFFAOYSA-K phosphate Chemical compound [O-]P([O-])([O-])=O NBIIXXVUZAFLBC-UHFFFAOYSA-K 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 239000000941 radioactive substance Substances 0.000 description 1
- 230000000717 retained effect Effects 0.000 description 1
- 230000035939 shock Effects 0.000 description 1
- RMAQACBXLXPBSY-UHFFFAOYSA-N silicic acid Chemical compound O[Si](O)(O)O RMAQACBXLXPBSY-UHFFFAOYSA-N 0.000 description 1
- 235000012239 silicon dioxide Nutrition 0.000 description 1
- 239000005361 soda-lime glass Substances 0.000 description 1
- HUAUNKAZQWMVFY-UHFFFAOYSA-M sodium;oxocalcium;hydroxide Chemical compound [OH-].[Na+].[Ca]=O HUAUNKAZQWMVFY-UHFFFAOYSA-M 0.000 description 1
- 238000003860 storage Methods 0.000 description 1
- 238000012360 testing method Methods 0.000 description 1
Landscapes
- Processing Of Solid Wastes (AREA)
- Fertilizers (AREA)
Description
［産業上の利用分野］
本発明は、使用済核燃料の再処理工場等から排
出される放射性廃液を固形化処理するようにした
放射性廃液の処理方法に関するものである。
［従来の技術］
使用済核燃料の再処理工場等から排出される放
射性廃液とりわけ高レベルの放射能を帯びた廃液
は、従来、廃液のまま貯蔵されていた。また、近
年、保管をより容易なものとするためにガラス固
化体とし、キヤニスタと称されるステンレス等か
らなる耐久性を有する容器に充填して保存するガ
ラス固化法が開発されている。
従来行なわれているガラス固化法について、第
２図を参照しながら説明すると、
ａ まず放射性廃液１にガラス原料（例えばガラ
スカレツト等）を混ぜ、
ｂ これをガラス溶解炉３中にて溶融させた後、
ｃ その底部の抜出ノズル４からキヤニスタ５に
流し出す。
図中６はガラス流を示す。また７は、溶解炉３
中で発生する蒸気を、処理設備に送給する配管を
示す。
［発明が解決しようとする問題点］
上記従来のプロセスにおいては、
イ 高温の溶融ガラスがキヤニスタの内面に直に
接触する。
ロ この接触は酸化雰囲気（空気雰囲気）で行な
われる。
ハ 溶融ガラスが急冷されて破砕物状となるの
で、固化ガラスの比表面積が大きくなる。
等の改善課題がある。また、
ニ 充填するキヤニスタを交換する場合等には、
ガラス流６を断続させねばならず、従つてノズ
ル４を通過する溶融ガラスが間欠的となる。そ
のため、ノズル４に温度の昇降による膨張、収
縮が負荷され、ノズル４の寿命が短くなる。
等の問題もあつた。
［問題点を解決するための手段］
上記問題点を解決するために、本発明はガラス
溶融炉中の溶融ガラスを水中に流し出して破砕物
状となし、これを水熱条件下で固めて躯体化する
ようにしたものであり、
放射性廃液にガラス原料を混ぜた後加熱して該
ガラス原料を溶融させ、この溶融物を水中に流し
出して破砕物状の固化ガラスとなし、次いでこの
破砕物状のガラスを、反応容器中で、水の存在下
で圧力70Kg／cm2以上、温度150℃以上の加熱加圧
状態に保持して躯体化させた後、キヤニスタ中に
保存することを特徴とする放射性廃液の処理方
法、
を要旨とするものである。
以下本発明について更に詳細に説明する。
第１図は本発明の好ましい一態様を示す系統図
である。
本発明方法では、
放射性廃液１にガラス原料２を混じ、
ガラス溶融炉３にて溶融する。放射性廃液１
中の放射性物質の大部分は、溶融ガラス中に取
り込まれ、一部は水蒸気と共に配管７より揮散
するが、配管７の下流側に設置されている捕集
手段（図示せず）により捕集される。
ガラス溶融炉３中の溶融ガラスは、水８中に
流し出され、これにより固化すると共に、急冷
されるので細かな破砕物状ガラス９となる。
この破砕物状ガラス９は乾燥器１０で乾燥し
た後、又は水切装置１１で所要量の付着水を水
切した例、
水熱条件下にて躯体化し、キヤニスタ５中に
保存する。
上記一連のプロセスについて次に詳細に説明す
る。
プロセスについて；
本発明では、処理対象となる放射性廃液は、特
に限定されるものではなく、使用済核燃料の再処
理設備から排出される廃液の他、原子力発電所、
研究施設等から排出される液等、各種の放射性廃
液に適用し得る。
ガラス原料としては、珪酸（SiO2）を含むも
のが用いられ、例えば、ホウ珪酸ガラス、ソーダ
ホウ珪酸ガラス等の他、ソーダ石灰質ホウ珪酸ガ
ラス、ソーダ石灰ガラス、高鉛珪酸塩ガラス、含
リン酸塩珪酸質ガラス等も用い得る。
ガラス原料と放射性廃液との混合割合は、放射
性廃液中の固形分１重量部に対しガラス原料３重
量部以上、とりわけ３〜10重量部程度とするのが
好ましい。
プロセスについて；
ガラス原料を溶融する温度は、そのガラス原料
が十分な流動性を帯びる温度であれば良く、特に
高温にする必要はない。
このガラス溶融炉３及び前記乾燥器１０から生
じる蒸気は、配管７で抜き出され捕集・処理設備
に送給される。
プロセスについて；
水８中に流し出された溶融ガラスは冷却されて
固化すると共に、急冷されるので破砕物状とな
る。この破砕物状ガラスはバケツトコンベア、ネ
ツトコンベア等の適宜の手段により搬出され、次
プロスセスに送られる。
なお、溶融ガラスの保有熱により水８が加熱さ
れ蒸発するので、蒸発量に応じて水を補給するの
が好ましい。
プロセスについて；
このプロセスでは、次の水熱固化プロセスにて
必要とする量以上の水を破砕物状ガラスから取り
除く。この手段としては、図示の乾燥器１０、水
切装置１１のいずれか一方又は双方を用いるのが
好適であるが、その他の手段によつても良い。
プロセスについて；
プロセスから送給される破砕物状ガラスに、
必要に応じて水を加えた後、反応用応力容器に入
れ、水熱条件となるよう加熱して破砕物状ガラス
を躯体化せしめる。
本発明の方法においては、水熱反応を行なわせ
るには、筒状の反応容器の一端又は両端に圧縮ピ
ストンを嵌装させて筒体中央に反応充填室を形成
した装置を用いるのが便利である。即ち、水を添
加した破砕物状ガラスをこの反応充填室内に充填
し、圧縮ピストンで充填物を圧縮しながら加熱し
て水熱反応を行なわせるのである。
この反応容器としてキヤニスタを用いれば、水
熱反応終了後に取り出して、キヤニスタに充填す
る手間が省ける。
なおこの水熱反応を行なわせるに際し、破砕物
状ガラスにアルカリ例えばNaOH、KOH、Ca
（OH）2、Sr（OH）2等を混ぜても良い。このよう
にすれば、破砕物状ガラスを固化させる水熱反応
を促進させることができる。
本発明方法においては、破砕物状ガラスを反応
容器に充填するに際して、破砕物状ガラスを２又
はそれ以上に区分けし、一区分け量を反応容器に
充填する毎にプレス（以下、仮プレスということ
がある。）するのようにするのが好ましい。この
ように仮プレスすれば、反応容器内に充填された
一区分け量の破砕物状ガラスが直ちに圧縮されて
その体積が小さくなるので、反応容器内に多量の
破砕物状ガラスを充填することが可能となり、反
応容器の小容量化も可能となる。この仮プレス圧
は、固化反応時の圧力よりも小さくて良く、例え
ば固化反応時の圧力の1/10程度で良い。なお、区
分けした破砕物状ガラスを全て反応容器内に充填
した後のプレスは、このような軽度の仮プレスを
行なうことなく、固化反応時の圧力でプレスし、
反応を開始すれば足りる。
而して、本発明の方法においては、水熱反応を
行なつているときに、破砕物状ガラスが加熱加圧
状態にあれば良く、所定の反応圧力への昇圧と、
所定の反応温度への昇温は、これらのいずれかを
先行させても良く、これらを同時に行なつても良
い。
本発明において、水熱反応の圧力は70Kg／cm2以
上である。圧力の上限は、実用的には500Kg／cm2
程度である。なお圧力は、当然ながらその反応温
度における水の蒸気圧よりも高い圧力とし、水熱
状態になるようにする。
水熱反応の温度は、150℃よりも低いと、固化
反応が進行せず、極めて強度の低い固化体しか得
られない。特に好ましい温度は200〜350℃以上で
ある。
水熱反応時間は、５分から２時間程度で十分で
ある。水熱反応の圧力、温度が低い場合にはこの
反応時間は長目になり、逆に圧力、温度を高くす
れば反応時間は短くて足りる。なお本発明者等の
研究によれば、上記圧力及び温度の範囲におい
て、なるべく低い圧力及び温度の条件下に長い時
間保持する方が、得られる固化体の強度が高いこ
とが認められた。
第１図のプロセスは本発明方法の一例を示すも
のであるから、本発明方法はこの第１図のプロセ
スに限定されるものではない。
［作用］
放射性廃液中の固形分はガラスに封じ込められ
る。このガラスは、一旦溶融したものを水中に流
し出して破砕物状ガラスとされ、その後水熱反応
によつて躯体化されたものである。、従つて、比
較的温度の低いガラスがキヤニスタに接触する。
キヤニスタに充填されたガラス躯体は、割れ等が
殆どなく、比表面積が小さい。
また、ガラス溶融炉から溶融ガラスを連続的に
流し出すことができるので溶融ガラス流し出し用
のノズル４への熱衝撃が極めて小さくなる。更
に、ノズル４の如き格別の流し出し手段を設ける
必要も無く、溶融炉３から溶融ガラスをオーバー
フローさせて水８中に流し出す様にすることもで
きる。このようにすれば、溶融炉３の構成も簡易
なもので足りる。
［実施例］
以下に本発明を実施例を挙げて更に具体的に説
明するが、本発明はその要旨を超えない限り以下
の実施例に限定されるものではない。
実施例 １
平均粒径40mmのホウ珪酸ガラス（組成は表−
１）のカレツト14.4Kgに核燃料再処理工場の廃液
60を混合した後、1100℃に加熱してホウ珪酸ガ
ラスを溶融させ、次いで水中に流し出して表−１
に示す放射性ガラス固体化を得た。これを120メ
ツシユ（0.125mm）以下に粉砕し、固化試験をし
た結果を第３図および第４図に示す。
第３図は、ガラス固化体20Kgに対し２の水を
添加し、十分に混合した後、このうちの約４Kgを
内径120cmの加圧反応容器に充填し、圧力300Kg／
cm2において10分間の反応をさせた場合の反応温度
を圧縮強度の関係を示す。
第４図は、同じ手順で、反応温度を270℃とし
た場合の反応時間と圧縮強度の関係を示す。
なお、表−２は得られた躯体の分析値である。
[Industrial Application Field] The present invention relates to a method for treating radioactive waste liquid, which solidifies radioactive waste liquid discharged from a spent nuclear fuel reprocessing plant or the like. [Prior Art] Radioactive waste liquid discharged from spent nuclear fuel reprocessing plants, etc., particularly waste liquid with high levels of radioactivity, has conventionally been stored as waste liquid. In addition, in recent years, in order to make storage easier, a vitrification method has been developed in which the vitrified material is stored in a durable container made of stainless steel or the like called a canister. The conventional vitrification method will be explained with reference to Fig. 2: a. First, a glass raw material (e.g. glass cullet) is mixed with radioactive waste liquid 1, b. This is melted in a glass melting furnace 3, and then , c is poured out from the extraction nozzle 4 at the bottom into the canister 5. 6 in the figure indicates a glass flow. Also, 7 is the melting furnace 3
This shows the piping that delivers the steam generated inside to the processing equipment. [Problems to be Solved by the Invention] In the above conventional process, (a) the high temperature molten glass comes into direct contact with the inner surface of the canister; (b) This contact is carried out in an oxidizing atmosphere (air atmosphere). C. Since the molten glass is rapidly cooled and becomes crushed, the specific surface area of the solidified glass increases. There are other issues to improve. In addition, when replacing the canister to be filled,
The glass stream 6 must be interrupted, so that the molten glass passing through the nozzle 4 is intermittent. Therefore, the nozzle 4 is subjected to expansion and contraction due to temperature rise and fall, and the life of the nozzle 4 is shortened. There were also other problems. [Means for Solving the Problems] In order to solve the above problems, the present invention pours out the molten glass in the glass melting furnace into water to form a crushed material, and solidifies this under hydrothermal conditions. It is designed to be made into a frame, and after mixing the glass raw material with the radioactive waste liquid, it is heated to melt the glass raw material, and this melt is poured into water to form solidified glass in the form of crushed material. It is characterized by the fact that physical glass is heated and pressurized in the presence of water at a pressure of 70 kg/cm 2 or more and a temperature of 150°C or more to form a skeleton, and then stored in a canister. The gist of this paper is a method for treating radioactive waste liquid. The present invention will be explained in more detail below. FIG. 1 is a system diagram showing a preferred embodiment of the present invention. In the method of the present invention, a glass raw material 2 is mixed with a radioactive waste liquid 1 and melted in a glass melting furnace 3. Radioactive waste liquid 1
Most of the radioactive substances inside are taken into the molten glass, and some of them are volatilized from the pipe 7 along with water vapor, but they are collected by a collection means (not shown) installed downstream of the pipe 7. Ru. The molten glass in the glass melting furnace 3 is poured into water 8, where it solidifies and is rapidly cooled to become fine crushed glass 9. After this crushed glass 9 is dried in a dryer 10, or after removing a required amount of adhering water with a drainer 11, it is formed into a skeleton under hydrothermal conditions and stored in a canister 5. The above series of processes will now be described in detail. Regarding the process: In the present invention, the radioactive waste liquid to be treated is not particularly limited, and in addition to waste liquid discharged from spent nuclear fuel reprocessing equipment, nuclear power plants,
It can be applied to various radioactive waste liquids, such as liquids discharged from research facilities. As glass raw materials, those containing silicic acid (SiO 2 ) are used, such as borosilicate glass, soda borosilicate glass, soda lime borosilicate glass, soda lime glass, high lead silicate glass, phosphate-containing glass, etc. Silicate glass or the like may also be used. The mixing ratio of the glass raw material and the radioactive waste liquid is preferably 3 parts by weight or more, particularly about 3 to 10 parts by weight, of the glass raw material per 1 part by weight of the solid content in the radioactive waste liquid. Regarding the process: The temperature at which the glass raw material is melted may be a temperature at which the glass raw material has sufficient fluidity, and does not need to be particularly high. Steam generated from the glass melting furnace 3 and the dryer 10 is extracted through a pipe 7 and sent to collection and processing equipment. Regarding the process: The molten glass poured into water 8 is cooled and solidified, and is rapidly cooled to become a crushed material. This crushed glass is carried out by an appropriate means such as a bucket conveyor or a net conveyor, and sent to the next process. In addition, since the water 8 is heated and evaporated by the heat retained in the molten glass, it is preferable to replenish water according to the amount of evaporation. About the process: In this process, more water is removed from the crushed glass than is required in the subsequent hydrothermal solidification process. As this means, it is preferable to use either or both of the illustrated dryer 10 and draining device 11, but other means may also be used. About the process: The crushed glass fed from the process
After adding water as necessary, the glass is placed in a reaction stress container and heated under hydrothermal conditions to form the crushed glass into a skeleton. In the method of the present invention, in order to carry out the hydrothermal reaction, it is convenient to use an apparatus in which a compression piston is fitted to one or both ends of a cylindrical reaction vessel and a reaction filling chamber is formed in the center of the cylindrical vessel. be. That is, crushed glass to which water has been added is filled into this reaction filling chamber, and the filled material is compressed and heated by a compression piston to cause a hydrothermal reaction. If a canister is used as the reaction vessel, the effort of taking out the reaction vessel and filling it into the canister after the completion of the hydrothermal reaction can be saved. In addition, when carrying out this hydrothermal reaction, an alkali such as NaOH, KOH, Ca, etc. is added to the crushed glass.
(OH) 2 , Sr(OH) 2 , etc. may be mixed. In this way, the hydrothermal reaction that solidifies the crushed glass can be promoted. In the method of the present invention, when filling a reaction vessel with crushed glass, the crushed glass is divided into two or more parts, and each time one division is filled into the reaction vessel, a press (hereinafter referred to as "temporary press") is applied. ) is preferable. By temporarily pressing in this way, the amount of crushed glass filled in the reaction container is immediately compressed and its volume becomes smaller, so it is possible to fill a large amount of crushed glass into the reaction container. This makes it possible to reduce the capacity of the reaction vessel. This temporary pressing pressure may be lower than the pressure during the solidification reaction, and may be, for example, about 1/10 of the pressure during the solidification reaction. In addition, after filling all of the divided crushed glass into the reaction container, pressing was carried out using the pressure used during the solidification reaction without performing such a light temporary pressing.
It is enough to start the reaction. Therefore, in the method of the present invention, it is sufficient that the crushed glass is in a heated and pressurized state during the hydrothermal reaction, and the pressure is increased to a predetermined reaction pressure,
The temperature may be raised to a predetermined reaction temperature in advance of any one of these, or may be carried out simultaneously. In the present invention, the pressure of the hydrothermal reaction is 70 Kg/cm 2 or more. The upper limit of pressure is practically 500Kg/cm 2
That's about it. Note that the pressure is naturally higher than the vapor pressure of water at the reaction temperature, so that a hydrothermal state is achieved. If the temperature of the hydrothermal reaction is lower than 150°C, the solidification reaction will not proceed and only a solidified product with extremely low strength will be obtained. A particularly preferred temperature is 200 to 350°C or higher. A hydrothermal reaction time of about 5 minutes to 2 hours is sufficient. If the pressure and temperature of the hydrothermal reaction are low, the reaction time will be long; on the other hand, if the pressure and temperature are high, the reaction time will be short. According to research conducted by the present inventors, it has been found that within the above pressure and temperature ranges, the strength of the obtained solidified product is higher when the material is maintained for a longer period of time under the lowest possible pressure and temperature conditions. Since the process shown in FIG. 1 shows an example of the method of the present invention, the method of the present invention is not limited to the process shown in FIG. [Operation] Solid content in radioactive waste liquid is sealed in glass. This glass is made by melting the glass and pouring it into water to create crushed glass, which is then formed into a frame through a hydrothermal reaction. , thus relatively cool glass contacts the canister.
The glass body filled in the canister has almost no cracks and has a small specific surface area. Further, since the molten glass can be continuously poured out from the glass melting furnace, the thermal shock to the nozzle 4 for pouring out the molten glass becomes extremely small. Furthermore, there is no need to provide a special pouring means such as the nozzle 4, and the molten glass can be allowed to overflow from the melting furnace 3 and poured into the water 8. In this way, the structure of the melting furnace 3 can be simple. [Examples] The present invention will be described in more detail below with reference to Examples, but the present invention is not limited to the following Examples unless the gist thereof is exceeded. Example 1 Borosilicate glass with an average particle size of 40 mm (composition is shown in Table-
1) The cullet 14.4Kg contains waste liquid from a nuclear fuel reprocessing plant.
60 was mixed, heated to 1100℃ to melt the borosilicate glass, and then poured into water to form Table 1.
The solidified radioactive glass shown in Fig. 1 was obtained. This was crushed to 120 meshes (0.125 mm) or less, and a solidification test was conducted. The results are shown in Figures 3 and 4. Figure 3 shows that 2 parts of water is added to 20 kg of vitrified material, and after thorough mixing, about 4 kg of this is charged into a pressurized reaction vessel with an inner diameter of 120 cm, and the pressure is 300 kg/
The relationship between the reaction temperature and the compressive strength is shown when the reaction is carried out at cm 2 for 10 minutes. Figure 4 shows the relationship between reaction time and compressive strength when the same procedure was used but the reaction temperature was 270°C. Table 2 shows the analysis values of the obtained skeleton.
【表】【table】
【表】
第３図及び第４図より、本発明法によれば、極
めて強度の高い躯体とし得ることが明らかであ
る。特に、300Kg／cm2で加圧の場合、反応温度を
270℃以上、反応時間を10min以上とすることに
より著しく高強度になることが認められる。
また、このようにした得られた躯体をステンレ
ス製キヤニスタ中に保管したところ、経時的な変
化は全く生じなく、長時間にわたつて安定して保
存し得ることが認められた。
［効果］
以上詳述した通り、本発明においては、放射性
廃液中の固形分を含有した溶融ガラスを一旦水中
に流し出し、破砕物状ガラスとなした後、水熱反
応させて躯体とするようにしたものであり、高温
の溶融ガラスが直接にキヤニスタに接触しない。
そのためキヤニスタの長寿命化が図れる。また躯
体の比表面積が小さく、金属イオン等の溶出が僅
小である。また、躯体の体積も、小さなものとな
る。更に、加熱、加圧装置も通常のもので足り、
その他の特別の装置を用いる必要がないと共に、
添加剤も安価であるのでランニングコストも低
い。更に、ガラス溶解炉の構成も簡易なものとし
得ると共に、その寿命も長いものとなる。[Table] From FIGS. 3 and 4, it is clear that according to the method of the present invention, a frame with extremely high strength can be obtained. In particular, when pressurizing at 300Kg/ cm2 , the reaction temperature is
It is recognized that the strength can be significantly increased by setting the temperature to 270°C or higher and the reaction time to 10 minutes or more. Furthermore, when the obtained skeleton was stored in a stainless steel canister, no change occurred over time, and it was found that it could be stored stably for a long period of time. [Effect] As detailed above, in the present invention, the molten glass containing the solid content in the radioactive waste liquid is once poured into water to form crushed glass, and then subjected to a hydrothermal reaction to form a frame. The high temperature molten glass does not come into direct contact with the canister.
Therefore, the life of the canister can be extended. In addition, the specific surface area of the body is small, and the elution of metal ions and the like is minimal. Moreover, the volume of the frame becomes small. Furthermore, ordinary heating and pressurizing equipment is sufficient.
There is no need to use any other special equipment, and
Since additives are also inexpensive, running costs are also low. Furthermore, the structure of the glass melting furnace can be simplified and its lifespan can be extended.
第１図は本発明の実施の一手順を示す系統図、
第２図は従来例を示す系統図である。また第３図
及び第４図は実施例における測定結果を表わすグ
ラフである。
１……放射性廃液、２……ガラス原料、３……
ガラス溶融炉、８……水、９……破砕物状ガラ
ス。
FIG. 1 is a system diagram showing one procedure for implementing the present invention;
FIG. 2 is a system diagram showing a conventional example. Further, FIGS. 3 and 4 are graphs showing the measurement results in the example. 1...Radioactive waste liquid, 2...Glass raw material, 3...
Glass melting furnace, 8...water, 9...crushed glass.
Claims (1)
該ガラス原料を溶融させ、この溶融物を水中に流
し出して破砕物状の固化ガラスとなし、次いでこ
の破砕物状ガラスを、反応容器中で、水の存在下
で圧力70Kg／cm2以上、温度150℃以上の加熱加圧
状態に保持して躯体化させた後、キヤニスタ中に
保存することを特徴とする放射性廃液の処理方
法。 ２ 放射性廃液ガラスを加熱加圧状態に保持して
躯体化させる反応容器としてキヤニスタを用いる
ことを特徴とする特許請求の範囲第１項に記載の
放射性廃液の処理方法。 ３ 破砕物状ガラスにアルカリを混じて躯体化せ
しめることを特徴とする特許請求の範囲第１項又
は第２項に記載の放射性廃液の処理方法。[Scope of Claims] 1. After mixing a glass raw material with a radioactive waste liquid, heating it to melt the glass raw material, pouring out the melt into water to form a solidified glass in the form of a crushed substance, and then converting the glass in the form of a crushed substance. is heated and pressurized in the presence of water at a pressure of 70 kg/cm 2 or more and a temperature of 150°C or more to form a skeleton, and then stored in a canister. processing method. 2. The method for treating radioactive waste liquid according to claim 1, characterized in that a canister is used as a reaction vessel for holding the radioactive waste liquid glass in a heated and pressurized state to form a skeleton. 3. A method for treating radioactive waste liquid according to claim 1 or 2, characterized in that the crushed glass is mixed with an alkali to form a skeleton.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP22106384A JPS6199896A (en) | 1984-10-19 | 1984-10-19 | Method of disposing radioactive waste liquor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP22106384A JPS6199896A (en) | 1984-10-19 | 1984-10-19 | Method of disposing radioactive waste liquor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS6199896A JPS6199896A (en) | 1986-05-17 |
| JPH055078B2 true JPH055078B2 (en) | 1993-01-21 |
Family
ID=16760905
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP22106384A Granted JPS6199896A (en) | 1984-10-19 | 1984-10-19 | Method of disposing radioactive waste liquor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6199896A (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6383697A (en) * | 1986-09-29 | 1988-04-14 | 日揮株式会社 | Solidifying processing method of radioactive molten water-cooled slag |
-
1984
- 1984-10-19 JP JP22106384A patent/JPS6199896A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS6199896A (en) | 1986-05-17 |
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