JPH03162699A - Method for dewatering and drying radioactive solid waste - Google Patents
Method for dewatering and drying radioactive solid wasteInfo
- Publication number
- JPH03162699A JPH03162699A JP30350989A JP30350989A JPH03162699A JP H03162699 A JPH03162699 A JP H03162699A JP 30350989 A JP30350989 A JP 30350989A JP 30350989 A JP30350989 A JP 30350989A JP H03162699 A JPH03162699 A JP H03162699A
- Authority
- JP
- Japan
- Prior art keywords
- container
- solid
- storage container
- water
- drying
- 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
- 238000001035 drying Methods 0.000 title claims abstract description 33
- 238000000034 method Methods 0.000 title claims description 7
- 230000002285 radioactive effect Effects 0.000 title claims description 6
- 239000002910 solid waste Substances 0.000 title claims description 4
- 238000003860 storage Methods 0.000 claims abstract description 42
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 31
- 239000007788 liquid Substances 0.000 claims abstract description 24
- 239000011261 inert gas Substances 0.000 claims abstract description 17
- 239000000463 material Substances 0.000 claims abstract description 15
- 238000007872 degassing Methods 0.000 claims abstract description 8
- 239000002901 radioactive waste Substances 0.000 claims description 29
- 238000000926 separation method Methods 0.000 claims description 9
- 239000002245 particle Substances 0.000 claims description 6
- 238000001914 filtration Methods 0.000 claims 2
- 238000010438 heat treatment Methods 0.000 claims 1
- 238000005253 cladding Methods 0.000 abstract description 25
- 239000007789 gas Substances 0.000 abstract description 19
- 239000000843 powder Substances 0.000 abstract description 9
- 239000000446 fuel Substances 0.000 abstract description 6
- 238000005520 cutting process Methods 0.000 abstract description 5
- 239000011248 coating agent Substances 0.000 abstract 2
- 238000000576 coating method Methods 0.000 abstract 2
- 239000011148 porous material Substances 0.000 abstract 2
- 238000011282 treatment Methods 0.000 description 9
- 238000010586 diagram Methods 0.000 description 7
- 238000007664 blowing Methods 0.000 description 5
- 229910001093 Zr alloy Inorganic materials 0.000 description 4
- 230000018044 dehydration Effects 0.000 description 3
- 238000006297 dehydration reaction Methods 0.000 description 3
- 230000000694 effects Effects 0.000 description 3
- 229910052751 metal Inorganic materials 0.000 description 3
- 239000002184 metal Substances 0.000 description 3
- 230000006641 stabilisation Effects 0.000 description 3
- 238000011105 stabilization Methods 0.000 description 3
- 239000000126 substance Substances 0.000 description 3
- YZCKVEUIGOORGS-NJFSPNSNSA-N Tritium Chemical compound [3H] YZCKVEUIGOORGS-NJFSPNSNSA-N 0.000 description 2
- 230000006835 compression Effects 0.000 description 2
- 238000007906 compression Methods 0.000 description 2
- 238000011038 discontinuous diafiltration by volume reduction Methods 0.000 description 2
- 238000004880 explosion Methods 0.000 description 2
- 238000012805 post-processing Methods 0.000 description 2
- 230000002195 synergetic effect Effects 0.000 description 2
- 229910052722 tritium Inorganic materials 0.000 description 2
- 239000002699 waste material Substances 0.000 description 2
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 1
- 241001113556 Elodea Species 0.000 description 1
- 229910052770 Uranium Inorganic materials 0.000 description 1
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 1
- 229910052799 carbon Inorganic materials 0.000 description 1
- 239000000919 ceramic Substances 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 239000000428 dust Substances 0.000 description 1
- 239000003344 environmental pollutant Substances 0.000 description 1
- 239000004744 fabric Substances 0.000 description 1
- 239000000835 fiber Substances 0.000 description 1
- 239000008187 granular material Substances 0.000 description 1
- 230000005484 gravity Effects 0.000 description 1
- 239000003456 ion exchange resin Substances 0.000 description 1
- 229920003303 ion-exchange polymer Polymers 0.000 description 1
- 239000011344 liquid material Substances 0.000 description 1
- 238000002844 melting Methods 0.000 description 1
- 230000008018 melting Effects 0.000 description 1
- 239000004745 nonwoven fabric Substances 0.000 description 1
- 229910052760 oxygen Inorganic materials 0.000 description 1
- 239000001301 oxygen Substances 0.000 description 1
- 231100000719 pollutant Toxicity 0.000 description 1
- 238000002360 preparation method Methods 0.000 description 1
- 238000012545 processing Methods 0.000 description 1
- 239000004576 sand Substances 0.000 description 1
- 239000002689 soil Substances 0.000 description 1
- 239000011343 solid material Substances 0.000 description 1
- 230000000087 stabilizing effect Effects 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 230000001954 sterilising effect Effects 0.000 description 1
- 238000004659 sterilization and disinfection Methods 0.000 description 1
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 1
- -1 wire mesh Substances 0.000 description 1
Landscapes
- Manufacture And Refinement Of Metals (AREA)
Abstract
Description
【発明の詳細な説明】
［産業上の利用分野］
本発明は、放射性固体廃棄物（以下、放射性廃棄物とい
う）の脱水及び乾燥方法に関するものである．
〔従来の技術〕
周知のように、切断処理された使用済みの燃料制御棒、
切断処理された使用済みのウラン、燃料被覆管、イオン
交換樹脂等の放射性固体物質や放射性汚染物質等の放射
性廃棄物は、そのまま水と共にステンレス材等からなる
容器に収納されると共に、貯蔵プール内に入れるか、或
いは貯蔵室において水中保管されている．
〔発明が解決しようとするｔｌ題〕
上記放射性廃棄物の保管方法は、保管スペース上の観点
からすれば、これらに滅容及び安定化等の処理を施すこ
とが、保管スペースの有効活用及び有害物質の安定化を
図る上において好ましい。DETAILED DESCRIPTION OF THE INVENTION [Field of Industrial Application] The present invention relates to a method for dehydrating and drying radioactive solid waste (hereinafter referred to as radioactive waste). [Prior Art] As is well known, used fuel control rods that have been cut,
Radioactive waste such as radioactive solid materials and radioactive pollutants such as used cut uranium, fuel cladding tubes, and ion exchange resins are stored as is in containers made of stainless steel or other materials along with water, and are stored in storage pools. or stored underwater in a storage room. [Problem to be solved by the invention] From the viewpoint of storage space, the method for storing radioactive waste mentioned above requires that the waste be subjected to treatments such as sterilization and stabilization to ensure effective use of storage space and prevent harmful This is preferable in terms of stabilizing the substance.
上記したような減容及び安定化の手段としては、例えば
溶融処理、熱間静水圧加圧処理、圧縮処理、焼却処理等
がある．
ところで、放射性廃棄物をそのまま減容及び安定化等の
処理を行うと、処理中に水蒸気爆発が発生したり、水草
気やガスの発生に伴う内圧の上昇により同化不能になっ
たり、燃焼し難いという問題が生しるので、処理前にこ
れらを乾燥する必要がある。Means for volume reduction and stabilization as described above include, for example, melting treatment, hot isostatic pressure treatment, compression treatment, and incineration treatment. By the way, if radioactive waste is treated as it is, such as volume reduction and stabilization, a steam explosion may occur during the treatment, or it may become impossible to assimilate due to the rise in internal pressure due to the generation of waterweed or gas, or it may be difficult to burn. Therefore, it is necessary to dry them before processing.
そして、放射性廃棄物を乾燥させる前に、この放射性廃
棄物から容易に分離する水を予め除去することが、後処
理の乾燥の容易化にとって極めて効果的である。Before drying the radioactive waste, it is extremely effective to remove water that is easily separated from the radioactive waste in order to facilitate drying in post-processing.
ところが、実際には後処理、処分に対する考慮が一切払
われておらず、従って放射性廃棄物の乾燥は行われてい
ないのが実状である。However, in reality, no consideration is given to post-processing or disposal, and therefore radioactive waste is not dried.
しかしながら、放射性廃棄物の貯蔵量が増大するにつれ
、放射性廃棄物の貯蔵は早晩問題として取上げられるよ
うになるものと容易に予測される。However, as the amount of radioactive waste stored increases, it is easy to predict that the storage of radioactive waste will sooner or later become a problem.
従って、本発明は含水を容易に除去し、乾燥し得る放射
性廃棄物の乾燥方法の提供を目的とする。Therefore, an object of the present invention is to provide a method for drying radioactive waste that can easily remove moisture and dry the waste.
本発明は上記した問題の解決を同るためになされたもの
であって、従って本発明に係る放射性廃棄物の脱水及び
乾燥方法の要旨は、底部に多数の微小孔を有する収容容
器に放射性廃棄物を投入し、該収容容器をホンパー状の
固液分離器に載置すると共に、該収容容器の微小孔から
滴下する微小物を含む水を前記固液分離器の内側に設け
た固液分離材により濾過して脱水する。The present invention has been made to solve the above-mentioned problems. Therefore, the gist of the method for dehydrating and drying radioactive waste according to the present invention is to dispose of radioactive waste in a storage container having a large number of micropores at the bottom. A solid-liquid separator in which a substance is input, the storage container is placed on a romper-like solid-liquid separator, and water containing minute objects drips from the micropores of the storage container provided inside the solid-liquid separator. Filter and dehydrate through material.
脱水後さらに、前記収容容器を密閉可能な乾燥容器内に
収容して脱ガスを行い、次いで加熱した不活性ガスを供
給すると共に、ヒータにより加熱して乾燥することを特
徴とする．
〔作用］
本発明によれば、収容容器に投入された放射性廃棄物に
付着しかつこれに含まれている水のうち、この放射性廃
棄物から分離した水は放射性廃棄物中の微小な放射性廃
棄物粒と共にこの収容容器の底部の多数の微小孔を通っ
て滴下するが、これらはホッパー状の固液分離器の固液
分離材によりＭ過され、微小な放射性廃棄物粒と水とに
分離される。After dehydration, the storage container is further housed in a sealable drying container to degas it, and then a heated inert gas is supplied and the container is heated and dried by a heater. [Operation] According to the present invention, among the water attached to and contained in the radioactive waste put into the storage container, the water separated from the radioactive waste is separated from the minute radioactive waste in the radioactive waste. The particles drop through the many micro holes at the bottom of this storage container, but these are passed through the solid-liquid separation material of the hopper-shaped solid-liquid separator and separated into minute radioactive waste particles and water. be done.
そして、この収容容器が乾燥器内に収容されると、脱ガ
スに次いで加熱した不活性ガスが供給されるが、このガ
スは上記微小孔を通って流入して個々の放射性廃棄物の
間を通り抜ける一方、収容容器の外側からヒータの熱が
加えられる。When this storage container is placed in a dryer, heated inert gas is supplied after degassing, but this gas flows through the micropores and passes between the individual pieces of radioactive waste. While passing through, heat from a heater is applied from outside the container.
本発明の実施例を、第１図乃至第５図とを参照しながら
以下に説明する。Embodiments of the present invention will be described below with reference to FIGS. 1 to 5.
策土１施員
この第１実施例を、脱水状態を示す模式的断面構成説明
図の第１図と、乾燥状態を示す模式的断面構成説明図の
第２図と、第２図の主要部拡大図の第３図とに基づいて
説明する。Soil preparation 1 This first example is shown in Figure 1, a schematic cross-sectional diagram showing a dewatered state, Figure 2, a schematic cross-sectional diagram showing a dry state, and the main parts of Figure 2. This will be explained based on FIG. 3, which is an enlarged view.
即ち、第１図乃至第３図に示す符号（５）は、円筒体（
５１）の下端より若干上方位置に、多数の微小孔（ロ）
を有するパンチドメタルになる底板（５２）を有する収
容容器であり、この収容容器（５）内には自体が放射能
汚染され、放射能汚染水が付着すると共に、放射能汚染
水を含んだ燃料被覆管、燃料制御棒やこれらのの切断粉
等からなる放射性廃棄物（以下、被覆管等という）（ホ
）が投入されている。That is, the symbol (5) shown in FIGS. 1 to 3 indicates the cylindrical body (
51) A number of micro holes (b) are located slightly above the lower end.
This container has a bottom plate (52) made of punched metal with Radioactive waste (hereinafter referred to as cladding, etc.) consisting of fuel cladding tubes, fuel control rods, and their cut powder (e) is being input.
そして、この収容容器（５）は内側に突出縁（６３）を
有する円胴体（６１〉と、この円胴体（６１）の下側の
漏斗状体（６２）とからなる、固液分離器としてのホッ
パー（６）の前記突出縁（６３）の上面に載置されてい
る。This storage container (5) is composed of a cylindrical body (61) having a protruding edge (63) on the inside, and a funnel-shaped body (62) on the lower side of this cylindrical body (61), and serves as a solid-liquid separator. is placed on the upper surface of the protruding edge (63) of the hopper (6).
さらに、漏斗状体（６２）の上面であるテーパ面上は、
着脱自在な後述する材質になる固液分離材（ｆ）によっ
て覆われている．
なお、漏斗状体（６２）の中央において下方に・突出し
てなるものはビレン管（６４）であり、このドレン管（
６４）の下端は、図示省略しているが、管路を介して集
水槽に連通されてなる構或になっている。Furthermore, on the tapered surface which is the upper surface of the funnel-shaped body (62),
It is covered with a removable solid-liquid separation material (f), which will be described later. In addition, what protrudes downward at the center of the funnel-shaped body (62) is a drain pipe (64), and this drain pipe (
Although not shown, the lower end of 64) is connected to a water collection tank via a conduit.
従って、収容容器（５）に投入された被覆管等（４）に
付着し、或いは含まれている水のうち、この被覆管等（
ロ）から重力の作用によって分離した水は、被覆管等（
ロ）の微小な切断粉等と共に、この収容容器（５）の底
仮（５２）の多数の微小孔（ロ）を通ってホソパ（２）
内に滴下する．
次いで、滴下した水と被覆管等（４）の切断粉等とは固
液分離材（ｆ）によって濾過されると共に、水のみがド
レン管（６４）から上記集水槽に流れ込む。Therefore, of the water attached to or contained in the cladding tube, etc. (4) put into the storage container (5), this cladding tube, etc. (4)
The water separated by the action of gravity from the cladding pipe (b)
Together with the minute cutting powder etc. of (b), it passes through the numerous micro holes (b) in the bottom (52) of this storage container (5) to the hosopa (2).
drip inside. Next, the dropped water and cut powder from the cladding tube (4) are filtered by the solid-liquid separator (f), and only water flows into the water collection tank from the drain pipe (64).
次いで、所定時間が経過して被覆管等（ロ）から水が分
離しなくなると、収容容器（５）だけが、例えばクレー
ン等により吊持されて、第２図に示すような構成になる
乾燥容器（１）内に収容される。Next, when a predetermined period of time has passed and the water no longer separates from the cladding tube, etc. (b), only the storage container (5) is suspended, for example, by a crane, and the drying process takes place as shown in Figure 2. It is housed in a container (1).
この乾燥容器（１）の詳細は、閉蓋時に密Ｉ：１機能を
有する開閉自在な天！（１１）が上部に設けられ、内壁
に沿うヒータ（１２）が内設され、底部に前記収容容器
（５）が載置される支持台（１４）が配設されると共に
、底部付近の外側にはドレン管（ｌ３）を設けてなる構
或になっている。The details of this drying container (1) are that it has a lid that can be opened and closed with a tight I:1 function when closed! (11) is provided at the top, a heater (12) is provided inside along the inner wall, a support base (14) on which the storage container (5) is placed is provided at the bottom, and an outside near the bottom is provided. A drain pipe (l3) is provided at the drain pipe (l3).
一方、この乾燥容器（１）の上部外側には、この容器（
１）側から除湿器（２ｌ）と、ダストフィルタ（２２）
と、真空ポンプ（２３）とを配管を介して接続してなる
脱ガス装置（２）を設ける他、乾燥容器（１）の下部付
近の側面に不活性ガスを導入するガス導入部（３）を連
通させた。このガス導入部（３）は乾燥容器（１）側か
らコントロールバルブ（３３）と、ガスヒータ（３ｌ）
と、ガスボンベ等の不活性ガス供給源（３２）とを配管
を介して接続してなる構戊になっている．従って、上記
収容容器（５）が乾燥容器（１）内に収容され、天Ｍ（
１１）が閉しられて密封されると、脱ガス装置（２）の
真空ポンプ（２３）の稼働によりこの乾燥容器（１）内
の脱ガスが行われ、これに伴って水分の茎発が促進され
る。次いで、ガス導入部（３）のコントロールバルプ（
３３）が間弁され、不活性ガス供給＆（３２）からガス
ヒータ（３１）を介して加熱した不活性ガスが乾燥容器
（】）内に吹込まれると共に、ヒータ（ｌ２）にｉｌ１
電される。On the other hand, on the outside of the upper part of this drying container (1), this container (
1) Dehumidifier (2L) and dust filter (22) from the side
In addition to providing a degassing device (2) which is connected to a vacuum pump (23) and a vacuum pump (23) via piping, a gas introduction section (3) for introducing an inert gas into the side surface near the bottom of the drying container (1) is provided. communicated. This gas introduction part (3) is connected to the control valve (33) and gas heater (3l) from the drying container (1) side.
and an inert gas supply source (32) such as a gas cylinder are connected via piping. Therefore, the storage container (5) is accommodated in the drying container (1), and the top M (
11) is closed and sealed, the vacuum pump (23) of the degassing device (2) operates to degas the inside of the drying container (1), and as a result, moisture is released. promoted. Next, the control valve (
33) is closed and heated inert gas is blown into the drying container (]) from the inert gas supply & (32) via the gas heater (31), and the heater (l2) is supplied with il1.
Powered up.
この不活性ガスは多数の微小孔（ｈ）を通って収容容器
（５）内に流入し、収容容器（５）内の被覆管等であっ
て、しかも切断部位が変形していても内部に流入し、ま
た被覆管等の切断粉等のような残渣であってもそれらの
間を通って流れるので、被覆管等（ロ）の乾燥が一層早
められる．
上記したように、被覆管等（ト）の乾燥に際して不活性
ガスを供給するのは、被覆管はジルコニウム合金であり
、このジルコニウム合金の切断粉になる残渣は極めて活
性が強いため、加熱状態において空気中の酸素と急激に
反応して発火、或いは爆発を生じる恐れがあるからに他
ならない．また、被覆管等（ロ）の乾燥温度を約１５０
゜Ｃに設定した。乾燥温度を約１５０゜Ｃに設定したの
は、上記ジルコニウム合金製の被覆管には揮発性物質、
例えばトリチウム等が例外なく収蔵されており、故にジ
ルコニウム合金製の被覆管が４５０゜Ｃ以上の温度にな
るとトリチウム等が放出され始めるので、この放出を抑
制するためである．このように、脱水後の被覆管等（ロ
）は、３段構えの乾燥手段の相乗作用によりより効果的
、かつ安全に乾燥されることとなる。This inert gas flows into the storage container (5) through a large number of micropores (h), and even if the cut portion is deformed, the inert gas flows into the storage container (5). Even residues such as cutting powder from the cladding tubes, etc. flow through them, so that the drying of the cladding tubes, etc. (b) is further accelerated. As mentioned above, the inert gas is supplied when drying the cladding tube (g) because the cladding tube is made of a zirconium alloy, and the residue that becomes the cutting powder of this zirconium alloy is extremely active, so when heated This is because there is a risk of ignition or explosion due to rapid reaction with oxygen in the air. In addition, the drying temperature of the cladding tube, etc. (b) was set to approximately 150°C.
It was set at °C. The drying temperature was set at approximately 150°C because the zirconium alloy cladding tube contains volatile substances,
For example, tritium and the like are stored without exception, and therefore, when the zirconium alloy cladding tube reaches a temperature of 450°C or higher, tritium and the like begin to be released, so this is to suppress this release. In this way, the cladding tube etc. (b) after dewatering can be dried more effectively and safely due to the synergistic effect of the three-stage drying means.
一方、上記固液分離材（ｆ）は加熱されないのでその材
質に対する選択肢が多く、例えば多孔性陶磁器、焼結金
属、多孔質プラスチック、繊維織物、金網、不織布等の
他、炭素、砂、金属粉等の粉粒体を用いることができる
．
ところで、経済上の観点からすれば固液分離材（ｆ）を
収容容器（５）の底板（５２）の上に直接配設すれば良
いようにも考えられるが、この収容容器（５）内への被
覆管等（４）の投入に際して、この固液分離材（ｆ）が
損傷を受ける恐れがあって好ましくない。On the other hand, since the solid-liquid separating material (f) is not heated, there are many choices for its material, such as porous ceramics, sintered metal, porous plastic, fiber fabric, wire mesh, non-woven fabric, carbon, sand, metal powder, etc. Powder and granular materials such as can be used. By the way, from an economical point of view, it may be possible to arrange the solid-liquid separation material (f) directly on the bottom plate (52) of the storage container (5). When inserting the cladding tube etc. (4) into the container, this solid-liquid separation material (f) may be damaged, which is not preferable.
星主夫韮員
この第２実施例を、脱水状態を示す模式的断面構成説明
図の第４図に基づき、第１実施例と相違する点について
だけ以下に説明する。This second embodiment will be described below with reference to FIG. 4, which is a schematic cross-sectional diagram illustrating the dehydration state, and only the differences from the first embodiment will be explained below.
即ち、突出縁（６３）を有する円胴体（６１）と、この
円胴体（６ｌ）の下側の漏斗状体（６２）とからなるホ
ッパ−（６）の前記突出縁（６３）の上面に、底部に固
液分鋪材（ｆ）を備えてなるホルダ（７）の上部に設け
た鍔部（７１）を載せ、この鍔部（７１）の上に被覆管
等（ロ）が投入されてなる収容容器（５）を載置する構
威とした．従って、被覆管等（４）に付着し、或いは含
まれている水のうち、この被覆管等（４）から分離した
水は、切断粉等の微小な被覆管等（ロ）と共に収容容器
（５）の多数の微小孔（ロ）を通ってホルダ（７）内に
滴下すると共に、このホルダ（７）の底部の固液分離材
（ｆ）により濾過されるので、この実施例の作用と効果
とは前記第１実施例と略同効である。That is, on the upper surface of the projecting edge (63) of a hopper (6) consisting of a circular body (61) having a projecting edge (63) and a funnel-shaped body (62) on the lower side of this circular body (6l), A holder (7) comprising a solid-liquid material (f) at the bottom is placed on the holder (7), and a flange (71) is placed on top of the flange (71), and the cladding tube, etc. (b) is placed on top of the holder (7). The structure was designed to hold a storage container (5) consisting of Therefore, of the water attached to or contained in the cladding tube, etc. (4), the water separated from the cladding tube, etc. (4) is stored in the storage container (2) together with minute cladding tubes, etc. (b) such as cutting powder. 5) into the holder (7) through the large number of micropores (b), and is filtered by the solid-liquid separation material (f) at the bottom of the holder (7). The effect is approximately the same as that of the first embodiment.
星主夫嵐明
この第３実施例を、乾燥状態を示す主要部模式的断面構
成説明図の第５図に基づいて説明する。This third embodiment will be explained based on FIG. 5, which is a schematic sectional view of the main part showing the dry state.
なお、この実施例にあっては収容容器（５）と乾燥容器
（１）の構成が若干相違するだけだから、それらの相違
点だけの説明に止める。In this embodiment, since the configurations of the storage container (5) and the drying container (1) are only slightly different, the explanation will be limited to only those differences.
即ち、収容容器（５）の底板（５２）の中心に、上端が
閉蓋され、この底板（５２）の下面より下方に突出する
下端が開口すると共に、内部から外方、つまり収容容器
（５）の内側に連通ずる複数の微小孔（ロ）を有するガ
ス吹込筒（５３）を設けた。That is, the upper end is closed at the center of the bottom plate (52) of the storage container (5), and the lower end protruding downward from the bottom surface of the bottom plate (52) is opened, and the storage container (5) is opened from the inside to the outside. ) A gas blowing cylinder (53) having a plurality of microholes (b) communicating with the inside of the cylinder was provided.
一方、乾燥容器（１）には、下部付近の側面に設けた不
活性ガスを導入するガス導入部（３）を分岐させ、この
乾燥容器（１）の下部中心からも連通させると共に、こ
の乾燥容器（１）のＭ．板から上方に突出し、かつ上面
に収容容器（５）のガス吹込筒（５３）の下端が押圧サ
れるガスシール（４ｌ）を支持するシールハウジング（
４２）を上部付近に有するガス吹込口（４）を設けてな
る構成とした。On the other hand, the drying container (1) has a branched gas introduction part (3) for introducing an inert gas, which is provided on the side near the lower part, and communicates with the center of the lower part of the drying container (1). Container (1) M. A seal housing (4l) that protrudes upward from the plate and supports a gas seal (4l) on the upper surface of which the lower end of the gas blowing tube (53) of the storage container (5) is pressed.
42) is provided with a gas inlet (4) near the top.
従って、脱水された被覆管等（ロ）が収容されている収
容容器（５）内には、この収容容器（５）の底板（５２
）の複数の微小孔■を通って不活性ガスが流入し、また
ガス吹込口（４）からガスシール（４１）により個別に
ガス吹込筒（５３）に流入する不活性ガスがそのガス吹
込筒（５３）の複数の微小孔（ロ）を通って流入するの
で、この実施例の作用と効果とは第ｌ実施例と略同効で
ある．
但し、この図から良く理解されるように、不活性ガスが
流入する面積を広くし得るので、第１実施例に比較して
乾燥能力がより優れている．また、この実施例になる構
成の収容容器（５）を、第１実施例になる乾燥容器（１
）に適用することも可能であって、しかも第１実施例よ
りも優れた乾燥能力を期待することができる．
なお、上記実施例は本発明の具体例にすぎず、従って上
記実施例によって本発明の技術的思想の範囲が限定され
るものではない．
［発明の効果］
以上詳述したように、本発明に係る放射性廃棄物の乾燥
方法によれば、収容容器に投入された放射性廃棄物に付
着しかつこれに含まれている水のうち、この放射性廃棄
物から分離した水は放射性廃棄物中の微小な放射性廃棄
物粒と共にこの収容容器の底部の多数の微小孔を通って
滴下するが、これらはホッパー状の固液分離器の固液分
離材により濾過され、微小な放射性廃棄物粒と水とに分
離されるので、放射性廃棄物に付着している水が容易に
脱水され、次いでこの収容容器は乾燥容器に収容された
後、脱ガス、加熱された不活性ガスの供給と、ヒータと
の相乗作用により能率的に、しかも安全に乾燥させるこ
とが可能になり、貯蔵のための滅容及び安定化処理とし
ての溶融処理、熱間静水圧加圧処理、圧縮処理、焼却処
理等を安全、かつ確実に行い得る。Therefore, inside the storage container (5) in which the dehydrated cladding tube, etc. (b) is stored, there is a bottom plate (52) of the storage container (5).
), the inert gas flows in through the plurality of micro holes (■), and the inert gas flows into the gas blowing tube (53) individually from the gas blowing port (4) through the gas seal (41). Since the water flows through the plurality of micro holes (b) in (53), the operation and effect of this embodiment are almost the same as those of the first embodiment. However, as can be clearly understood from this figure, since the area into which the inert gas flows can be increased, the drying ability is superior to that of the first embodiment. In addition, the storage container (5) having the configuration of this embodiment was replaced with the drying container (1) of the first embodiment.
), and can be expected to have a better drying ability than the first embodiment. It should be noted that the above embodiments are merely specific examples of the present invention, and therefore the scope of the technical idea of the present invention is not limited by the above embodiments. [Effects of the Invention] As detailed above, according to the method for drying radioactive waste according to the present invention, among the water attached to and contained in the radioactive waste put into the storage container, this The water separated from the radioactive waste drips through the many micropores at the bottom of this storage container together with the tiny radioactive waste particles in the radioactive waste, but these are separated by the solid-liquid separation in the hopper-shaped solid-liquid separator. The water is filtered through the material and separated into minute radioactive waste particles and water, so the water adhering to the radioactive waste is easily dehydrated, and the container is then placed in a drying container and then degassed. The synergistic effect between the supply of heated inert gas and the heater makes it possible to dry efficiently and safely. Water pressure treatment, compression treatment, incineration treatment, etc. can be performed safely and reliably.
従って、放射性廃棄物の貯蔵量の増大につれて問題にな
るものと想定される、放射性廃棄物の貯蔵スペースの確
保という問題解決に対して極めて多大な効果を奏する．Therefore, it is extremely effective in solving the problem of securing storage space for radioactive waste, which is expected to become a problem as the amount of radioactive waste stored increases.
第ｌ図乃至第３図は本発明になる第１実施例を示し、第
１図は脱水状態を示す模式的断面構戒説明図、第２図は
乾燥状態を示す模式的断面構成説明図、第３図は第２図
の主要部拡大図、第４図は本発明になる第２実施例の脱
水状態を示す模式的断面構戒説明図、第５図は本発明に
なる第３実施例の乾燥状態を示す主要部模式的断面構成
説明図である。
（１）・・・乾燥容器、（２）−・・脱ガス装置、（３
）・・・ガス導入部、（４）・・・ガス吹込口、（５）
・・・収容容器、（５２）・・・底板、（５３）−・・
ガス吹込筒、（６）−・・ホッパー、（７）・・・ホル
ダ、（ｆ）−・・固液分離材、（ロ）・・・微小孔、（
ト）・・・被覆管等。1 to 3 show a first embodiment of the present invention, FIG. 1 is a schematic cross-sectional configuration explanatory diagram showing a dehydrated state, FIG. 2 is a schematic cross-sectional configuration explanatory diagram showing a dry state, FIG. 3 is an enlarged view of the main part of FIG. 2, FIG. 4 is a schematic cross-sectional diagram showing the dehydration state of the second embodiment of the present invention, and FIG. 5 is a third embodiment of the present invention. FIG. 2 is a schematic cross-sectional configuration explanatory diagram of main parts showing a dry state. (1)...Drying container, (2)--Degassing device, (3
)...Gas inlet, (4)...Gas inlet, (5)
... Storage container, (52) ... Bottom plate, (53) ...
Gas blowing tube, (6) -- hopper, (7) -- holder, (f) -- solid-liquid separation material, (b) -- micropore, (
g)...cladding tube, etc.
Claims (2)
体廃棄物を投入し、該収容容器をホッパー状の固液分離
器に載置すると共に、該収容容器の微小孔から滴下する
微小物を含む水を前記固液分離器の内側に設けた固液分
離材により濾過することを特徴とする放射性固体廃棄物
の脱水方法。(1) Radioactive solid waste is placed in a storage container that has a large number of micropores at the bottom, and the container is placed on a hopper-like solid-liquid separator, and minute particles are dropped from the micropores of the storage container. A method for dewatering radioactive solid waste, comprising filtering water containing the solid-liquid separator using a solid-liquid separation material provided inside the solid-liquid separator.
体廃棄物を投入し、該収容容器をホッパー状の固液分離
器に載置すると共に、該収容容器の微小孔から滴下する
微小物を含む水を前記固液分離器の内側に設けた固液分
離材により濾過した後、該収容容器を密閉可能な乾燥容
器内に収容して脱ガスを行い、次いで加熱した不活性ガ
スを供給すると共に、ヒータにより加熱することを特徴
とする放射性固体廃棄物の乾燥方法。(2) Radioactive waste is put into a storage container with many micro holes at the bottom, and the storage container is placed on a hopper-like solid-liquid separator, and minute particles are dropped from the micro holes of the storage container. After filtering the water containing water through a solid-liquid separation material provided inside the solid-liquid separator, the storage container is placed in a sealable drying container to perform degassing, and then heated inert gas is supplied. and heating with a heater.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP30350989A JPH03162699A (en) | 1989-11-21 | 1989-11-21 | Method for dewatering and drying radioactive solid waste |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP30350989A JPH03162699A (en) | 1989-11-21 | 1989-11-21 | Method for dewatering and drying radioactive solid waste |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH03162699A true JPH03162699A (en) | 1991-07-12 |
Family
ID=17921832
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP30350989A Pending JPH03162699A (en) | 1989-11-21 | 1989-11-21 | Method for dewatering and drying radioactive solid waste |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH03162699A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2014202703A (en) * | 2013-04-09 | 2014-10-27 | 株式会社東芝 | Drying container for radioactive waste |
| CN105280262A (en) * | 2015-09-17 | 2016-01-27 | 中广核工程有限公司 | Nuclear power plant waste package dehydration device and method |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5516282A (en) * | 1978-07-21 | 1980-02-04 | Nippon Atomic Ind Group Co | Dehydrating and drying device |
| JPS6050499A (en) * | 1983-08-31 | 1985-03-20 | 日本碍子株式会社 | Method and device for treating radioactive waste |
-
1989
- 1989-11-21 JP JP30350989A patent/JPH03162699A/en active Pending
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5516282A (en) * | 1978-07-21 | 1980-02-04 | Nippon Atomic Ind Group Co | Dehydrating and drying device |
| JPS6050499A (en) * | 1983-08-31 | 1985-03-20 | 日本碍子株式会社 | Method and device for treating radioactive waste |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2014202703A (en) * | 2013-04-09 | 2014-10-27 | 株式会社東芝 | Drying container for radioactive waste |
| CN105280262A (en) * | 2015-09-17 | 2016-01-27 | 中广核工程有限公司 | Nuclear power plant waste package dehydration device and method |
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