JPH0449679B2 - - Google Patents
Info
- Publication number
- JPH0449679B2 JPH0449679B2 JP58150855A JP15085583A JPH0449679B2 JP H0449679 B2 JPH0449679 B2 JP H0449679B2 JP 58150855 A JP58150855 A JP 58150855A JP 15085583 A JP15085583 A JP 15085583A JP H0449679 B2 JPH0449679 B2 JP H0449679B2
- Authority
- JP
- Japan
- Prior art keywords
- radioactive waste
- consumable electrode
- rod
- metal
- slag
- 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
- 229910052751 metal Inorganic materials 0.000 claims description 18
- 239000002184 metal Substances 0.000 claims description 18
- 238000002844 melting Methods 0.000 claims description 15
- 230000008018 melting Effects 0.000 claims description 15
- 239000002901 radioactive waste Substances 0.000 claims description 14
- 239000002893 slag Substances 0.000 claims description 12
- 238000000034 method Methods 0.000 claims description 11
- 239000002699 waste material Substances 0.000 description 6
- 230000008569 process Effects 0.000 description 5
- 230000000694 effects Effects 0.000 description 4
- 238000003860 storage Methods 0.000 description 4
- 229910052770 Uranium Inorganic materials 0.000 description 3
- 238000005202 decontamination Methods 0.000 description 3
- 230000003588 decontaminative effect Effects 0.000 description 3
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 3
- 238000003466 welding Methods 0.000 description 3
- 229910052778 Plutonium Inorganic materials 0.000 description 2
- 229910000831 Steel Inorganic materials 0.000 description 2
- 230000008901 benefit Effects 0.000 description 2
- 230000008878 coupling Effects 0.000 description 2
- 238000010168 coupling process Methods 0.000 description 2
- 238000005859 coupling reaction Methods 0.000 description 2
- 239000010730 cutting oil Substances 0.000 description 2
- 238000013467 fragmentation Methods 0.000 description 2
- 238000006062 fragmentation reaction Methods 0.000 description 2
- 230000007246 mechanism Effects 0.000 description 2
- 239000007769 metal material Substances 0.000 description 2
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 description 2
- 239000010959 steel Substances 0.000 description 2
- RYGMFSIKBFXOCR-UHFFFAOYSA-N Copper Chemical compound [Cu] RYGMFSIKBFXOCR-UHFFFAOYSA-N 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 229910052802 copper Inorganic materials 0.000 description 1
- 239000010949 copper Substances 0.000 description 1
- 238000005520 cutting process Methods 0.000 description 1
- 230000006866 deterioration Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000011038 discontinuous diafiltration by volume reduction Methods 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 238000010406 interfacial reaction Methods 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 239000000155 melt Substances 0.000 description 1
- 238000010309 melting process Methods 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 238000007781 pre-processing Methods 0.000 description 1
- 239000012857 radioactive material Substances 0.000 description 1
- 239000011819 refractory material Substances 0.000 description 1
- 230000004044 response Effects 0.000 description 1
- 238000007493 shaping process Methods 0.000 description 1
- 238000010008 shearing Methods 0.000 description 1
- 238000007711 solidification Methods 0.000 description 1
- 230000008023 solidification Effects 0.000 description 1
Landscapes
- Processing Of Solid Wastes (AREA)
Description
【発明の詳細な説明】
この発明は原子力施設で発生する金属放射性廃
棄物のうち、とくに長尺形状を有する廃棄物を処
理する方法に関するものである。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a method for treating metal radioactive waste generated at nuclear facilities, particularly waste having an elongated shape.
原子力産業、とくに核燃料サイクル全般に係わ
る事業所において用いられるプラント機器類は、
主として金属材料で構成されているのが現状であ
り、これらの保守、解体からは大量の金属放射性
廃棄物が発生する。現在のところ、これらの廃棄
物は適当な寸法に細片化した後にドラム缶等の容
器に封入され、貯蔵されている。しかしながら、
種々雑多の形状の廃棄物が発生する場合は、貯蔵
空間が有効に利用できないために上記方法は効率
的ではない。とくにパイプ類や塔槽類の場合は著
しく貯蔵効率は低い。 Plant equipment used in the nuclear power industry, especially in offices related to the nuclear fuel cycle in general, are
Currently, they are mainly composed of metal materials, and their maintenance and dismantling generate large amounts of metal radioactive waste. At present, these wastes are shredded into pieces of appropriate size, sealed in containers such as drums, and stored. however,
If waste is generated in a variety of miscellaneous shapes, the above method is not efficient as the storage space cannot be utilized effectively. In particular, the storage efficiency of pipes and tanks is extremely low.
このような現状に対して、金属放射性廃棄物は
溶融処理を施し、その金属材料の持つ真密度まで
減容し、貯蔵効率を高める方法が有効である。こ
のため、従来は金属放射性廃棄物をエレクトロス
ラグ溶融炉を用いて溶融処理することが提案され
ているが、従来の処理方法では非消耗電極の間に
被処理物を投入するため、予め被処理物を切削、
剪断等の方法により細片化する必要があり、この
ため上記処理に伴い切削油や切屑等の二次廃棄物
が発生するとともに前処理工程が非常に複雑であ
るという欠点があつた。 In response to this current situation, it is effective to melt metal radioactive waste to reduce its volume to the true density of the metal material and increase storage efficiency. For this reason, it has been proposed to melt metal radioactive waste using an electroslag melting furnace. cutting things,
It is necessary to break it into pieces by a method such as shearing, which has the disadvantage that secondary wastes such as cutting oil and chips are generated along with the above treatment, and the pretreatment process is extremely complicated.
この発明は、このような従来の欠点を解消する
ためになされたものであり、前処理が簡単で充分
な減容を行なうことができる処理方法を提供する
ものである。 The present invention was made in order to eliminate such conventional drawbacks, and provides a treatment method that allows for simple pretreatment and sufficient volume reduction.
この発明は、複数本の長尺金属放射性廃棄物を
それぞれ圧縮して断面積密度を高めるとともに束
ねることにより所定の密度の棒状体にし、その上
端部には給電装置に対する接続手段を取付けると
ともに下端部には端板を取付けることにより消耗
電極を構成し、これをエレクトロスラグ溶融炉で
溶融し、スラグと金属とを固化体として取り出す
ようにしたものである。なお、ここにいう束ねる
とは、ワイヤにより束ねる場合のみならず、溶接
結合により一体化する場合も含む概念である。 This invention involves compressing a plurality of long pieces of metal radioactive waste to increase the cross-sectional area density and bundling them into a rod-shaped body with a predetermined density.A connection means to a power supply device is attached to the upper end of the rod-shaped body, and a connecting means to a power supply device is attached to the lower end of the rod-shaped body. A consumable electrode is constructed by attaching an end plate to the electrode, which is melted in an electroslag melting furnace, and the slag and metal are taken out as a solidified body. Note that the term "bundling" here includes not only the case of bundling with wires but also the case of integrating by welding.
以下、この発明の実施例を図面によつて説明す
る。第１図において、現場で発生した長尺金属放
射性廃棄物１は処理施設に運ばれ１、有効断面積
等を指標とする棒状成形の必要性の有無の判別を
行なう２。目安としては、有効断面積が溶融炉の
炉床面積の20％程度以上であれば安定して操業で
きると考えられる。成形が必要な場合は長尺金属
放射性廃棄物１をローラ１１またはプレス１２に
より所定の密度に圧縮した棒状体２にする３。そ
してこれを結束機３により適宜の本数ワイヤで束
ね、または溶接機４により溶接結合して所定太さ
の棒状体５にする４。これによつて断面積密度を
高め、スラグ浴を保持するための必要電流を流せ
るようにする。また、この棒状体の大きさを調整
することにより溶融処理した固化体の大きさを調
整することができ、通常のドラム缶に封入するの
に適したものとすることもできる。ついで溶接機
３０により、この棒状体５の両端に端板７および
８を取付ける５。この取付けは、第２図に示すよ
うに、上側端板７には中心に吊下げ用軸部７１を
設けるとともに穴７０を形成したものを用いて穴
７１部で棒状体５の端部と溶接し、下側端板８に
は平板を用いてその穴８０部で棒状体５の端部と
溶接する。軸部７１の端部には結合機構（図示せ
ず）を設け、この結合機構付き軸部により消耗電
極６の吊下げ用兼給電用ワイヤまたは棒を形成さ
せる。端板８の下面は平坦に形成して溶融開始時
にスムーズにアークが発生するようにしている。
これによつてエレクトロスラグ溶融炉用の消耗電
極６が形成される。 Embodiments of the present invention will be described below with reference to the drawings. In FIG. 1, long metal radioactive waste 1 generated at the site is transported to a processing facility 1, where it is determined whether it is necessary to form it into a rod shape using the effective cross-sectional area, etc. 2. As a guideline, stable operation is considered to be possible if the effective cross-sectional area is approximately 20% or more of the hearth area of the melting furnace. If shaping is required, the long metal radioactive waste 1 is compressed into a rod-shaped body 2 to a predetermined density using rollers 11 or a press 12 3. Then, this is bundled with an appropriate number of wires using a binding machine 3, or welded together using a welding machine 4 to form a rod-shaped body 5 of a predetermined thickness. This increases the cross-sectional area density and allows the necessary current to flow to maintain the slag bath. Moreover, by adjusting the size of this rod-shaped body, the size of the melt-treated solidified body can be adjusted, and it can also be made suitable for being sealed in a normal drum can. Next, end plates 7 and 8 are attached to both ends of this rod-shaped body 5 using a welding machine 30. For this installation, as shown in FIG. 2, the upper end plate 7 is provided with a hanging shaft 71 in the center and a hole 70 is formed, and the end of the rod-shaped body 5 is welded at the hole 71. A flat plate is used as the lower end plate 8, and 80 holes thereof are welded to the end of the rod-shaped body 5. A coupling mechanism (not shown) is provided at the end of the shaft portion 71, and the shaft portion with the coupling mechanism forms a wire or rod for suspending and feeding the consumable electrode 6. The lower surface of the end plate 8 is formed flat so that an arc is smoothly generated when melting starts.
This forms a consumable electrode 6 for an electroslag melting furnace.
エレクトロスラグ溶融炉は６に示されるように
水冷炉体９と底板８１とを有し、底板８１は台車
８２により昇降可能に保持され、炉体９は冷却手
段９３により冷却されるように構成されている。
炉体９として銅製のものを用いると、耐火物を用
いる場合と比較して使用による劣化によつて二次
廃棄物が発生することがないという利点がある。
この炉体９中に上記消耗電極６の先端部を臨ま
せ、電源制御手段９４により底板８１と消耗電極
６との間に通電する。炉体９の上部にはカバー９
１が取付けられて負圧管理され、溶融時に発生す
るガスは排ガス系で適宜処理されて放射性物質は
外部に飛散しないように回収される。なお、上記
２における判別で、直接溶融可能とされた長尺金
属放射性廃棄物１は６でそのまま消耗電極として
用いる。 As shown in 6, the electroslag melting furnace has a water-cooled furnace body 9 and a bottom plate 81, the bottom plate 81 is held movably up and down by a trolley 82, and the furnace body 9 is configured to be cooled by a cooling means 93. ing.
When the furnace body 9 is made of copper, there is an advantage that secondary waste is not generated due to deterioration due to use, compared to the case where a refractory material is used.
The tip of the consumable electrode 6 is placed in the furnace body 9, and power is applied between the bottom plate 81 and the consumable electrode 6 by the power supply control means 94. A cover 9 is installed on the top of the furnace body 9.
1 is installed and negative pressure is controlled, and the gas generated during melting is appropriately treated in the exhaust gas system and the radioactive materials are recovered so as not to scatter to the outside. The long metal radioactive waste 1 determined to be directly meltable in the determination in step 2 above is used as a consumable electrode in step 6.
溶融炉内での溶融は、消耗電極６の先端部がス
ラグ６２中に位置して溶滴がスラグ６２中を下降
して溶鋼６１が形成され、その下側が順次凝固し
て固化体６０が形成される。この溶融では金属放
射性廃棄物が小さな溶滴となつてスラグ６２中を
通過し、反応に関与する金属質量に対しその表面
積が大きく、スラグ浴との界面反応が生じやすい
ために除染効果が大きい。とくに、汚染元素がウ
ランまたはプルトニウム等のTRU（超ウラン元
素）の場合はウラン、プルトニウム等のウラン元
素がスラグ６２中に移行して金属塊は除染される
ことになるので、大きな除染効果が期待できる。
消耗電極６を全部溶融させた後冷却させと、固化
体６０とその上の固化したスラグ６３とが生成す
る。これを底板８１を下降させることにより溶融
炉から取出し、スラグ６３は破砕機６４で破砕し
て溶融炉の溶融処理に再利用する７。一定回数利
用後のスラグは適宜の容器中に貯蔵して処分す
る。また、固化体６０はドラム缶等の収納容器６
９に収納して所定の場所に移す８。 During melting in the melting furnace, the tip of the consumable electrode 6 is located in the slag 62 and the droplets descend in the slag 62 to form molten steel 61, and the lower side of the molten steel is sequentially solidified to form a solidified body 60. be done. In this melting, the metal radioactive waste becomes small droplets and passes through the slag 62, and its surface area is large relative to the mass of metal involved in the reaction, making it easy to cause an interfacial reaction with the slag bath, resulting in a large decontamination effect. . In particular, if the contaminating element is TRU (transuranic elements) such as uranium or plutonium, the uranium elements such as uranium and plutonium will migrate into the slag 62 and the metal lump will be decontaminated, resulting in a large decontamination effect. can be expected.
When the consumable electrode 6 is completely melted and then cooled, a solidified body 60 and solidified slag 63 thereon are generated. The slag 63 is taken out from the melting furnace by lowering the bottom plate 81, and the slag 63 is crushed by a crusher 64 and reused for the melting process in the melting furnace 7. After a certain number of uses, the slag is stored in an appropriate container and disposed of. Further, the solidified body 60 is stored in a storage container 6 such as a drum can.
9 and move it to the designated location 8.
上記処理によると、長尺金属放射性廃棄物は細
片化という手間のかかる前処理が必要ないために
前処理が簡単であり、また細片化に伴う切削油や
切屑等の二次廃棄物が発生しないという利点があ
る。また、固化処理に伴い処理物の除染効果も期
待できる。 According to the above treatment, long metal radioactive waste is easy to pre-process as it does not require the time-consuming pre-processing of fragmentation, and secondary waste such as cutting oil and chips accompanying fragmentation is eliminated. It has the advantage of not occurring. In addition, the solidification process can also be expected to have a decontaminating effect on the treated material.
以上説明したように、この発明はエレクトロス
ラグ溶融法を利用し長尺金属放射性廃棄物を消耗
電極にして処理するようにしたものであり、前処
理が簡単で除染効果も勝れたものである。 As explained above, this invention utilizes the electroslag melting method to process long metal radioactive waste by using it as a consumable electrode, and the pretreatment is simple and the decontamination effect is excellent. be.
第１図１〜８はこの発明の実施例を示す処理装
置の工程説明図、第２図はそれに用いる消耗電極
の部分切り欠き断面図である。
１……長尺金属放射性廃棄物、５……棒状体、
６……消耗電極、９……炉体、６０固化体。
1 to 8 are process explanatory diagrams of a processing apparatus showing an embodiment of the present invention, and FIG. 2 is a partially cutaway sectional view of a consumable electrode used therein. 1... Long metal radioactive waste, 5... Rod-shaped body,
6...Consumable electrode, 9...Furnace body, 60 Solidified body.
Claims (1)
縮して断面積密度を高めるとともに束ねることに
より所定の密度の棒状体にし、その上端部には給
電装置に対する接続手段を取付けるとともに下端
部には端板を取付けることにより消耗電極を構成
し、これをエレクトロスラグ溶融炉で溶融し、ス
ラグと金属とを固化体として取り出すことを特徴
とする長尺金属放射性廃棄物の処理方法。1. A plurality of long pieces of metal radioactive waste are each compressed to increase the cross-sectional area density and bundled to form a rod-shaped body with a predetermined density, and a connection means to a power supply device is attached to the upper end, and an end is attached to the lower end. A method for disposing of elongated metal radioactive waste, which comprises forming a consumable electrode by attaching a plate, melting the consumable electrode in an electroslag melting furnace, and extracting slag and metal as a solidified body.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP15085583A JPS6042699A (en) | 1983-08-17 | 1983-08-17 | Method of treating long-sized metallic radioactive waste |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP15085583A JPS6042699A (en) | 1983-08-17 | 1983-08-17 | Method of treating long-sized metallic radioactive waste |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS6042699A JPS6042699A (en) | 1985-03-06 |
| JPH0449679B2 true JPH0449679B2 (en) | 1992-08-12 |
Family
ID=15505839
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP15085583A Granted JPS6042699A (en) | 1983-08-17 | 1983-08-17 | Method of treating long-sized metallic radioactive waste |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6042699A (en) |
Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS517130A (en) * | 1974-06-17 | 1976-01-21 | Tama Fureki Sansho Kk | ENMUSHORY OKISHAKUZAI |
| JPS51105904A (en) * | 1975-02-08 | 1976-09-20 | Leybold Heraeus Verwaltung | |
| JPS5330408A (en) * | 1976-09-02 | 1978-03-22 | Sumitomo Metal Ind Ltd | Electro-slag refining process with composite electrode |
| JPS57184571A (en) * | 1981-05-11 | 1982-11-13 | Power Reactor & Nuclear Fuel Dev Corp | Melting and treating device for metallic waste |
-
1983
- 1983-08-17 JP JP15085583A patent/JPS6042699A/en active Granted
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS517130A (en) * | 1974-06-17 | 1976-01-21 | Tama Fureki Sansho Kk | ENMUSHORY OKISHAKUZAI |
| JPS51105904A (en) * | 1975-02-08 | 1976-09-20 | Leybold Heraeus Verwaltung | |
| JPS5330408A (en) * | 1976-09-02 | 1978-03-22 | Sumitomo Metal Ind Ltd | Electro-slag refining process with composite electrode |
| JPS57184571A (en) * | 1981-05-11 | 1982-11-13 | Power Reactor & Nuclear Fuel Dev Corp | Melting and treating device for metallic waste |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS6042699A (en) | 1985-03-06 |
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