JPH0320719B2 - - Google Patents
Info
- Publication number
- JPH0320719B2 JPH0320719B2 JP14754584A JP14754584A JPH0320719B2 JP H0320719 B2 JPH0320719 B2 JP H0320719B2 JP 14754584 A JP14754584 A JP 14754584A JP 14754584 A JP14754584 A JP 14754584A JP H0320719 B2 JPH0320719 B2 JP H0320719B2
- Authority
- JP
- Japan
- Prior art keywords
- melting
- aluminum
- slag
- slag agent
- decontamination
- 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
- 239000002893 slag Substances 0.000 claims description 59
- 238000002844 melting Methods 0.000 claims description 39
- 230000008018 melting Effects 0.000 claims description 39
- 239000003795 chemical substances by application Substances 0.000 claims description 34
- 229910052782 aluminium Inorganic materials 0.000 claims description 31
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 claims description 31
- 229910052751 metal Inorganic materials 0.000 claims description 20
- 239000002184 metal Substances 0.000 claims description 20
- 239000000463 material Substances 0.000 claims description 14
- 238000000034 method Methods 0.000 claims description 12
- AZDRQVAHHNSJOQ-UHFFFAOYSA-N alumane Chemical class [AlH3] AZDRQVAHHNSJOQ-UHFFFAOYSA-N 0.000 claims description 8
- 239000000203 mixture Substances 0.000 claims description 8
- WCUXLLCKKVVCTQ-UHFFFAOYSA-M Potassium chloride Chemical compound [Cl-].[K+] WCUXLLCKKVVCTQ-UHFFFAOYSA-M 0.000 claims description 5
- 150000001875 compounds Chemical class 0.000 claims description 4
- 239000000941 radioactive substance Substances 0.000 claims description 4
- WDIHJSXYQDMJHN-UHFFFAOYSA-L barium chloride Chemical compound [Cl-].[Cl-].[Ba+2] WDIHJSXYQDMJHN-UHFFFAOYSA-L 0.000 claims description 2
- 229910001626 barium chloride Inorganic materials 0.000 claims description 2
- 239000001103 potassium chloride Substances 0.000 claims description 2
- 235000011164 potassium chloride Nutrition 0.000 claims description 2
- 150000003839 salts Chemical class 0.000 claims description 2
- 229910001504 inorganic chloride Inorganic materials 0.000 claims 3
- 229910000838 Al alloy Inorganic materials 0.000 claims 1
- 229910001506 inorganic fluoride Inorganic materials 0.000 claims 1
- 238000005202 decontamination Methods 0.000 description 33
- 230000003588 decontaminative effect Effects 0.000 description 30
- 229910052770 Uranium Inorganic materials 0.000 description 18
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 18
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical compound [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 description 12
- 238000006243 chemical reaction Methods 0.000 description 12
- 150000003671 uranium compounds Chemical class 0.000 description 9
- 230000000694 effects Effects 0.000 description 7
- KRHYYFGTRYWZRS-UHFFFAOYSA-M Fluoride anion Chemical compound [F-] KRHYYFGTRYWZRS-UHFFFAOYSA-M 0.000 description 6
- 229910052742 iron Inorganic materials 0.000 description 6
- 150000002739 metals Chemical class 0.000 description 6
- 239000000126 substance Substances 0.000 description 6
- VEXZGXHMUGYJMC-UHFFFAOYSA-M Chloride anion Chemical compound [Cl-] VEXZGXHMUGYJMC-UHFFFAOYSA-M 0.000 description 5
- 150000002222 fluorine compounds Chemical class 0.000 description 5
- 238000010438 heat treatment Methods 0.000 description 5
- 150000001805 chlorine compounds Chemical class 0.000 description 4
- WZECUPJJEIXUKY-UHFFFAOYSA-N [O-2].[O-2].[O-2].[U+6] Chemical group [O-2].[O-2].[O-2].[U+6] WZECUPJJEIXUKY-UHFFFAOYSA-N 0.000 description 3
- 239000000356 contaminant Substances 0.000 description 3
- 238000011109 contamination Methods 0.000 description 3
- 150000004820 halides Chemical class 0.000 description 3
- 239000011261 inert gas Substances 0.000 description 3
- 229910052809 inorganic oxide Inorganic materials 0.000 description 3
- 238000010309 melting process Methods 0.000 description 3
- XKRFYHLGVUSROY-UHFFFAOYSA-N Argon Chemical compound [Ar] XKRFYHLGVUSROY-UHFFFAOYSA-N 0.000 description 2
- ODINCKMPIJJUCX-UHFFFAOYSA-N Calcium oxide Chemical compound [Ca]=O ODINCKMPIJJUCX-UHFFFAOYSA-N 0.000 description 2
- FAPWRFPIFSIZLT-UHFFFAOYSA-M Sodium chloride Chemical compound [Na+].[Cl-] FAPWRFPIFSIZLT-UHFFFAOYSA-M 0.000 description 2
- 229910045601 alloy Inorganic materials 0.000 description 2
- 239000000956 alloy Substances 0.000 description 2
- 239000000292 calcium oxide Substances 0.000 description 2
- 235000012255 calcium oxide Nutrition 0.000 description 2
- 239000007789 gas Substances 0.000 description 2
- 229910000765 intermetallic Inorganic materials 0.000 description 2
- 150000002500 ions Chemical class 0.000 description 2
- 239000007769 metal material Substances 0.000 description 2
- 239000003758 nuclear fuel Substances 0.000 description 2
- 230000002285 radioactive effect Effects 0.000 description 2
- 239000012857 radioactive material Substances 0.000 description 2
- 238000006722 reduction reaction Methods 0.000 description 2
- 229910000439 uranium oxide Inorganic materials 0.000 description 2
- 229910004261 CaF 2 Inorganic materials 0.000 description 1
- 229910000640 Fe alloy Inorganic materials 0.000 description 1
- PXGOKWXKJXAPGV-UHFFFAOYSA-N Fluorine Chemical compound FF PXGOKWXKJXAPGV-UHFFFAOYSA-N 0.000 description 1
- BPQQTUXANYXVAA-UHFFFAOYSA-N Orthosilicate Chemical compound [O-][Si]([O-])([O-])[O-] BPQQTUXANYXVAA-UHFFFAOYSA-N 0.000 description 1
- 229910004298 SiO 2 Inorganic materials 0.000 description 1
- 229910000831 Steel Inorganic materials 0.000 description 1
- 229910052786 argon Inorganic materials 0.000 description 1
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 1
- WUKWITHWXAAZEY-UHFFFAOYSA-L calcium difluoride Chemical compound [F-].[F-].[Ca+2] WUKWITHWXAAZEY-UHFFFAOYSA-L 0.000 description 1
- 229910001634 calcium fluoride Inorganic materials 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000004090 dissolution Methods 0.000 description 1
- 238000000605 extraction Methods 0.000 description 1
- 239000011737 fluorine Substances 0.000 description 1
- 229910052731 fluorine Inorganic materials 0.000 description 1
- 230000005484 gravity Effects 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 230000007246 mechanism Effects 0.000 description 1
- 238000010128 melt processing Methods 0.000 description 1
- 230000005012 migration Effects 0.000 description 1
- 238000013508 migration Methods 0.000 description 1
- 239000011812 mixed powder Substances 0.000 description 1
- 238000005457 optimization Methods 0.000 description 1
- 239000001301 oxygen Substances 0.000 description 1
- 229910052760 oxygen Inorganic materials 0.000 description 1
- 239000000843 powder Substances 0.000 description 1
- 230000008569 process Effects 0.000 description 1
- 230000002250 progressing effect Effects 0.000 description 1
- 239000002994 raw material Substances 0.000 description 1
- 230000001603 reducing effect Effects 0.000 description 1
- 238000007670 refining Methods 0.000 description 1
- 239000011780 sodium chloride Substances 0.000 description 1
- 239000010959 steel Substances 0.000 description 1
- 230000002277 temperature effect Effects 0.000 description 1
- -1 uranium contaminated aluminum Chemical class 0.000 description 1
- 229910002007 uranyl nitrate Inorganic materials 0.000 description 1
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- Cleaning By Liquid Or Steam (AREA)
Description
〔発明の利用分野〕
本発明は、放射能汚染アルミニウムの溶融除染
方法に係り、特に原子力施設のうち特に核燃料物
質を取扱う施設で発生する核燃料物質を始めとす
る放射性物質で汚染されたアルミニウムの溶融除
染法に関する。
〔発明の背景〕
放射能汚染金属の溶融除染法は、放射能で汚染
された金属と共に無機酸化物を主体とするスラグ
剤を添加し、加熱溶融して放射性物質を選択的に
スラグ中に抽出包含させ金属から分離回収する方
法である。この方法の具体例を第1図に従つて説
明する。また放射性物質としてウランで汚染され
て金属をルツボ1に納め、さらに無機酸化物(ケ
イ酸SiO2,カルシアCaOなど)とさらにフツ化
物(フツ化カルシウムCaF2など)の混合粉末又
は粉子からなるスラグ剤を、処理金属量に対して
約10wt%を添加する。このルツボを外気と遮断
した密閉型電気炉2に納め、炉内を約0.1Torr真
空排気したのち、真空状態または不活性ガスボン
ベ5よりアルゴンなどの不活性ガスを導入して一
定圧力に調整したのち加熱昇温する。なお、真空
条件で加熱処理するときは常時、また一定圧力下
で処理するときは適時、排ガス処理対策のため設
けたケミカルトラツプ3又はフイルターを介して
排気する。
加熱溶融はヒーター6とプログラム機構付きの
電流制御装置7によつて、一定速度で昇温し、一
定時間溶融する。溶融過程においてルツボ内では
比重差によつて上層部には溶融スラグ8が、下層
部には溶融金属9となつて分離し、この過程でス
ラグ中にウラン化合物が取り込まれる
このような操作工程で放射能汚染金属の溶融除
染は行われれるが、ここで除染に最も関与してい
る因子はスラグ剤種類および加熱条件と考えられ
る。従来、鉄および鉄合金を主体として金属の溶
融処理に関しては、鉄鋼製精錬用のスラグ剤を用
いることによつて比較的高い除染効率が得られる
ことが確認されており、例えばSiO2−CaO−
Al2O3系スラグ剤において組成比を最適化したス
ラグ剤を用いれば、汚染前の金属材中のウラン濃
度近くまで除染できる。しかしながら、汚染材が
アルミニウムまたはその合金(以下アルミと略
記)の場合、このような鉄材除染用スラグ剤を適
用することは困難である。その理由として以下の
ことが考えられる。
鉄材除染用スラグ剤の融点は1200℃以上であ
り、アルミの融点(約660℃)に比してはるかに
高いため、溶融スラグとアルミの溶融処理操作温
度は1200℃以上で行う必要がり、このような高温
下ではスラグ中ウラン化合物のアルミへの再溶解
反応が進み易くなる。すなわち、冶金物理化学の
考え方では一般的に溶融スラグ−金属(M)間で
次のような反応平衡が成り立つているものとして
評価される。
UX+MU+MX ……(1)
ここで、U;ウラン
U;酸素あるいはフツ素
(1)式の平衡定数Kが1以上では反応は右に進み元
素ウランが生成する。この場合ウランは溶融金属
と金属間化合物を生成して溶け込むので除染は不
可能になる。今、鉄とアルミの場合について(1)の
反応式における平衡定数を計算すると表1に示す
ごとくなる。表から明らかなように、鉄の場合は
平衡定数は十分小さく、ウラン酸化物形態が安定
であることがわかる。一方、アルミの場合は平衡
定数が1前後であり、(1)の反応が支配定である場
合にはウラン酸化物はアルミによつて還元を受け
易く除染がきわめて難しいことを示している。
[Field of Application of the Invention] The present invention relates to a method for melting and decontaminating radioactively contaminated aluminum, particularly for decontaminating aluminum contaminated with radioactive materials such as nuclear fuel materials generated in nuclear facilities, especially facilities that handle nuclear fuel materials. Regarding melt decontamination method. [Background of the Invention] The melting decontamination method for radioactively contaminated metals involves adding a slag agent mainly composed of inorganic oxides to radioactively contaminated metals, and heating and melting the mixture to selectively release radioactive materials into the slag. This is a method of separating and recovering metals by extraction and inclusion. A specific example of this method will be explained with reference to FIG. In addition, the metal contaminated with uranium as a radioactive substance is placed in the crucible 1, and is further made of a mixed powder or powder of inorganic oxides (silicate SiO 2 , calcia CaO, etc.) and fluorides (calcium fluoride CaF 2 etc.). Approximately 10 wt% of the slag agent is added to the amount of metal to be treated. This crucible is placed in a closed electric furnace 2 that is isolated from the outside air, and the inside of the furnace is evacuated to approximately 0.1 Torr.Then, the pressure is adjusted to a constant level by vacuum or by introducing an inert gas such as argon from an inert gas cylinder 5. Heat to raise temperature. Incidentally, whenever heat treatment is carried out under vacuum conditions, and at appropriate times when heat treatment is carried out under constant pressure, the gas is evacuated through a chemical trap 3 or filter provided for exhaust gas treatment. For heating and melting, the temperature is raised at a constant rate by the heater 6 and the current control device 7 with a program mechanism, and the melting is performed for a certain period of time. During the melting process, the crucible separates into molten slag 8 in the upper layer and molten metal 9 in the lower layer due to the difference in specific gravity, and in this process, uranium compounds are incorporated into the slag. Melting decontamination of radioactively contaminated metals is performed, and the factors most involved in decontamination are thought to be the type of slag agent and heating conditions. Conventionally, it has been confirmed that relatively high decontamination efficiency can be obtained by using a slag agent for steel refining in the melting treatment of metals, mainly iron and iron alloys. −
By using an Al 2 O3-based slag agent with an optimized composition ratio, it is possible to decontaminate metal materials to a level close to the uranium concentration before contamination. However, when the contaminated material is aluminum or its alloy (hereinafter abbreviated as aluminum), it is difficult to apply such a slag agent for decontaminating iron materials. Possible reasons for this are as follows. The melting point of the slag agent for decontaminating iron materials is 1200℃ or higher, which is much higher than the melting point of aluminum (approximately 660℃), so the melting process temperature for molten slag and aluminum must be performed at 1200℃ or higher. Under such high temperatures, the redissolution reaction of the uranium compounds in the slag into aluminum tends to proceed. That is, in the concept of metallurgical physical chemistry, it is generally evaluated that the following reaction equilibrium is established between molten slag and metal (M). UX+MU+MX...(1) Here, U: Uranium U: Oxygen or Fluorine If the equilibrium constant K of equation (1) is 1 or more, the reaction proceeds to the right and elemental uranium is produced. In this case, uranium forms intermetallic compounds with the molten metal and dissolves, making decontamination impossible. Now, if we calculate the equilibrium constant in the reaction equation (1) for iron and aluminum, it will be as shown in Table 1. As is clear from the table, in the case of iron, the equilibrium constant is sufficiently small, indicating that the uranium oxide form is stable. On the other hand, in the case of aluminum, the equilibrium constant is around 1, which indicates that if reaction (1) is the dominant constant, uranium oxide is easily reduced by aluminum and decontamination is extremely difficult.
本発明は放射能汚染物質の化合物に対する還元
作用が高いため除染が困難とされているアルミ材
を対象として、添加するスラグ剤の放射能汚染物
質に対する除染効果をさらに1桁以上引き上げる
のに最適な除染法を提供することにある。
〔発明の概要〕
ウランなどの放射性物質で汚染した金属のうち
活性が高いアルミやその合金を溶融除染するため
The present invention targets aluminum materials, which are difficult to decontaminate due to their high reducing effect on compounds of radioactive contaminants. Our goal is to provide the optimal decontamination method. [Summary of the invention] For melting and decontaminating aluminum and its alloys, which are highly active among metals contaminated with radioactive substances such as uranium.
【表】
に好適なスラグ剤の種類および溶融条件として必
要な点は以下にあると考えられる。既に述べたよ
うに、アルミとウラン酸化物とは反応して還元さ
れたウラン元素を生成し易く、こうして生じたウ
ラン元素はアルミと金属間化合物を生成して金属
中に溶け込む。こうなると除染が不可能になる。
一方、温度が高くない溶融過程における、初期段
階では、ウラン化合物のスラグ中への移行反応が
進行していると考えられる。従つて一旦スラグ中
へ取り込んだウラン化合物は、安定なスラグ剤と
の複合体として存在できればアルミによる還元反
応を受けることなくスラグ中に包含されうるもの
と考える。そこでアルミ溶融除染の条件をまとめ
る。(1)スラグ剤はウラン化合物の取り込み反応を
したのち、安定な化学形態でウラン化合物と複合
体を形成し、アルミによるウラン化合物の還元反
応を抑える。(2)スラグ剤中へウラン化合物の取り
込み反応が終了した後は、金属中へのウランの再
溶解反応が考えられるので溶融温度度と時間の最
適化をへはかる。(3)スラグ剤の種類を選定する上
で、ウラン化合物の捕集反応を促進するために必
要な捕集用スラグイオンの生成量が最大となる最
適条件を選ぶ。(4)スラグの融点や粘性、化学的安
定性が適正なこと、などである。
現在までのところ、アルミ溶融除染用スラグ剤
および溶融条件に関する知見は得られていないの
で、実験結果をもとに発明に至つた最適なスラグ
剤選定根拠を説明する。表2に実験結果を示。表
2より、酸化物系は総じて融点が高いためアルミ
用スラグ剤としては適当でなく、除染効果も低
い。フツ化物系スラグの場合、酸化物系よりも除
染効果は高いがまだ不十分である。すなわち、除
染の目標レベルが原材アルミ中のウラン濃度
1ppmであるのに対しては、はるかに高いレベル
を示している。しかし、フツ化物の場合、実用的
なフツ化物の種類とその組合わせを勘案すると
100種類以上のスラグ剤が存在することになり、
フツ化物とそれらの組成比の最適化をはかれば溶
融除染に有効な可能性は残されている。次に、塩
化物系を検索した結果さらに除染効果の高いこと
がわかつた。しかし、塩化物のほとんどが塩
(NaCl)で代表されるように潮解性を有してお
り、たとえ溶融除染が完了しても、インゴツトを
取り出した時付着していたスラグが潮解してイン
ゴツト表面を濡らす。このような再汚染を生じる
と溶融除染のメリツトを失う。かつ液体状の汚染
物を取扱うことになり保管上も問題となる。塩化
物の中では比較的潮解性が少なく安定な化合物と
して塩化カリウム(KCl)と塩化バリウム
(BaCl2)があげられる。これらの塩化物を用い
ることにより潮解性の問題は回避できるがまた除
染効果は十分でない。
そこで発明されたものが塩化物とフツ化物の混
合系スラグ剤である。これを用いることにより、
化学的安定性の問題と除染効率向上の問題をさら
に一歩前進させることができる。しかしながら、
なおかつ除染の目標レベルより1桁高い。この問
題の改善例は後述するが、これまでの実施例にお
いて、塩化物、フツ化物などのハロゲン化物系が
アルミの溶融除染に有効であつた理由を除染原理
に基づいて説明する。
ハロゲン化物系のスラグ剤が有効である理由と
して次のことがあげられる。まず、アルミの融点
に近い低融点スラグが得られるので、アルミの溶
融とほぼ同時に溶融スラグ−金属間の除染反応を
進行させうる。また、ハロゲン化物はイオン化傾
向が強くウラン捕集イオンの生成量が多く、粘性
が無機酸化物に比して1桁ないし2桁小さいため
スラグ−金属間の反応は短時間で完了すると考え
られる。次に塩化物やフツ化物系スラグ剤におい
て、除染に最適なスラグ組成に関して述べる。The types of slag agents suitable for [Table] and the necessary points for melting conditions are considered to be as follows. As already mentioned, aluminum and uranium oxide tend to react to generate reduced uranium element, and the uranium element thus generated forms an intermetallic compound with aluminum and dissolves into the metal. If this happens, decontamination will be impossible.
On the other hand, in the early stage of the melting process when the temperature is not high, it is thought that the migration reaction of uranium compounds into the slag is progressing. Therefore, it is considered that the uranium compound once incorporated into the slag can be included in the slag without undergoing a reduction reaction with aluminum if it exists as a stable complex with a slag agent. Therefore, we will summarize the conditions for aluminum melting decontamination. (1) After the slag agent takes in the uranium compound and undergoes a reaction, it forms a complex with the uranium compound in a stable chemical form, thereby suppressing the reduction reaction of the uranium compound by aluminum. (2) After the reaction of incorporating uranium compounds into the slag agent is completed, a re-dissolution reaction of uranium into the metal can be considered, so the melting temperature and time should be optimized. (3) When selecting the type of slag agent, choose the optimal conditions that will maximize the amount of collection slag ions needed to promote the collection reaction of uranium compounds. (4) The melting point, viscosity, and chemical stability of the slag must be appropriate. Up to now, no knowledge has been obtained regarding the slag agent for aluminum melting and decontamination and the melting conditions, so the basis for selecting the optimal slag agent that led to the invention will be explained based on experimental results. Table 2 shows the experimental results. From Table 2, oxides generally have a high melting point, so they are not suitable as slag agents for aluminum, and their decontamination effects are also low. In the case of fluoride-based slag, the decontamination effect is higher than that of oxide-based slag, but it is still insufficient. In other words, the target level for decontamination is the uranium concentration in raw aluminum.
It shows a much higher level compared to 1ppm. However, in the case of fluorides, considering the practical types of fluorides and their combinations,
There are over 100 types of slag agents,
If fluorides and their composition ratios are optimized, there remains the possibility that they will be effective in melt decontamination. Next, we searched for chloride-based products and found that they were even more effective in decontamination. However, most chlorides are deliquescent, as represented by salt (NaCl), and even if melting and decontamination is completed, the slag that adhered to the ingot will deliquesce when the ingot is removed. Wet the surface. If such recontamination occurs, the benefits of melt decontamination are lost. In addition, liquid contaminants are handled, which poses a storage problem. Among chlorides, potassium chloride (KCl) and barium chloride (BaCl 2 ) are stable compounds with relatively little deliquescent property. Although the deliquescent problem can be avoided by using these chlorides, the decontamination effect is not sufficient. Therefore, a mixed slag agent containing chloride and fluoride was invented. By using this,
It is possible to take the issue of chemical stability and decontamination efficiency a step further. however,
Moreover, it is one order of magnitude higher than the target level for decontamination. Examples of improvements to this problem will be described later, but the reason why halides such as chlorides and fluorides were effective in melting and decontaminating aluminum in the previous examples will be explained based on the principle of decontamination. The reasons why halide-based slag agents are effective are as follows. First, since a low melting point slag close to the melting point of aluminum is obtained, the decontamination reaction between the molten slag and the metal can proceed almost simultaneously with the melting of the aluminum. Further, since halides have a strong ionization tendency, produce a large amount of uranium-trapping ions, and have a viscosity one to two orders of magnitude lower than that of inorganic oxides, it is thought that the reaction between slag and metal is completed in a short time. Next, we will discuss the optimal slag composition for decontamination among chloride and fluoride-based slag agents.
第1図に示す放射能汚染アルミニウムの溶融処
理装置において先に述べた処理手順によりウラン
汚染アルミニウムの溶融処理を行つた。本実施例
ではウラン汚染濃度にして500ppm相当になるよ
うに硝酸ウラニル溶液を一定量金属棒表面に塗り
つけたのち、金属の10wt%相当のスラグ剤と共
にルツボに納め最大1000℃で加熱溶融した。溶融
時間は30分一定とし、冷却後インゴツトをルツボ
から取り出し、インゴツト中のウラン濃度を測定
した。実施例の結果を表2と第3図および第4図
に示す。表2にはアルミニウム材処理用の各種ス
ラグ剤選定試験の結果をまとめて示した。第3図
はフツ化物系スラグ剤の塩基度すなわちイオン間
引力の弱いスラグ成分とイオン間引力の強いスラ
グ成分のモル数の比を求め、そのモル比に対して
得られたインゴツト中のウラン濃度の関係を示し
ており、塩基度が0.5〜2の範囲が適することを
示す実施例である。
第4図は、表3に示したスラグ剤選定試験の結
果、除染効果が最も大きかつたフツ化物、塩化物
混合系スラグ剤のうちの代表スラグ14LiF−
76KCl−10BaCl2スラグ剤を用いた温度効果を確
認した実施例を示す。第4図は溶融処理温度に対
するアルミインゴツト中のウラン濃度の関係を示
している。本スラグ剤の融点は約700℃であり、
実施例では最低温度はスラグ剤融点より高めの
780℃で行つている。また、ウラン汚染度は
2000ppmとして行つている。この結果、インゴツ
ト中のウラン濃度は処理温度が低いほど低下し、
除染効果が高くなつていることを示している。本
方式により目標除染レベル、すなわち一般にアル
ミニウム材中のウラン濃度0.9ppmとほとんど同
一レベルまで除染することを達成できた。
〔発明の効果〕
以上述べてきたように、本発明の方法によれば
放射能汚染物質の酸化物質を還元して溶融金属中
へ取り込み易く、一般的に除染が困難とされてい
るアルミウム材を、塩化物を含み、融点は金属材
の融点より200℃以上高くならないように成分調
整されたスラグ剤剤と共に、可及的に低い温度で
溶融処理することにより、放射能汚染アルミニウ
ム材の溶融除染効率を向上させることができる。
このような最適化をはかることにより、除染後の
アルミニウム材中のウラン濃度を原材中の濃度レ
ベルまで下げることが可能になる。
In the apparatus for melting radioactively contaminated aluminum shown in FIG. 1, uranium contaminated aluminum was melted according to the procedure described above. In this example, a certain amount of uranyl nitrate solution was applied to the surface of the metal rod so that the uranium contamination concentration was 500 ppm, and then placed in a crucible together with a slag agent equivalent to 10 wt% of the metal and heated and melted at a maximum temperature of 1000°C. The melting time was kept constant for 30 minutes, and after cooling, the ingot was removed from the crucible and the uranium concentration in the ingot was measured. The results of the examples are shown in Table 2 and FIGS. 3 and 4. Table 2 summarizes the results of various slag agent selection tests for aluminum material treatment. Figure 3 shows the basicity of the fluoride slag agent, that is, the ratio of the number of moles of the slag component with weak interion attraction to the slag component with strong interion attraction, and the uranium concentration in the ingot obtained for that molar ratio. This is an example showing that a range of basicity of 0.5 to 2 is suitable. Figure 4 shows representative slag 14LiF- from the fluoride and chloride mixed slag agents that had the greatest decontamination effect as a result of the slag agent selection test shown in Table 3.
An example is shown in which the temperature effect using a 76KCl-10BaCl 2 slag agent was confirmed. FIG. 4 shows the relationship between the uranium concentration in the aluminum ingot and the melting temperature. The melting point of this slag agent is approximately 700℃,
In the example, the minimum temperature is higher than the melting point of the slag agent.
It is carried out at 780℃. In addition, the degree of uranium contamination is
It is carried out as 2000ppm. As a result, the lower the processing temperature, the lower the uranium concentration in the ingot.
This shows that the decontamination effect is increasing. Using this method, we were able to achieve the target decontamination level, which is almost the same level as the uranium concentration in aluminum materials, which is 0.9 ppm. [Effects of the Invention] As described above, according to the method of the present invention, oxidized substances of radioactive contaminants can be reduced and easily incorporated into molten metal, and aluminum materials, which are generally difficult to decontaminate, can be reduced. The radioactively contaminated aluminum material is melted by melting it at the lowest possible temperature with a slag agent that contains chloride and whose composition is adjusted so that the melting point is not more than 200℃ higher than the melting point of the metal material. Decontamination efficiency can be improved.
By performing such optimization, it becomes possible to reduce the uranium concentration in the decontaminated aluminum material to the concentration level in the raw material.
第1図は溶融処理装置の構成概略図、第2図は
鉄材溶融除染時のスラグ塩基度と除染係数の関
係、第3図はアルミニウム溶融除染時のフツ化物
系スラグ塩基度と除染効果の関係、第4図はアル
ミニウム溶融温度と除染効果の関係を示す。
1……ルツボ、2……密閉型電気炉、3……ケ
ミカル(NaF)トラツプ、4……排気ポンプ、
5……不活性ガスボンベ、6……ヒーター、7…
…電気炉制御装置、8……溶融スラグ、9……溶
融金属。
Figure 1 is a schematic diagram of the configuration of the melt processing equipment, Figure 2 is the relationship between slag basicity and decontamination coefficient during melt decontamination of iron materials, and Figure 3 is the relationship between fluoride slag basicity and decontamination coefficient during aluminum melt decontamination. Figure 4 shows the relationship between aluminum melting temperature and decontamination effect. 1... Crucible, 2... Closed electric furnace, 3... Chemical (NaF) trap, 4... Exhaust pump,
5... Inert gas cylinder, 6... Heater, 7...
...Electric furnace control device, 8... Molten slag, 9... Molten metal.
Claims (1)
ルミ合金に無機塩類からなるスラグ剤を添加して
加熱溶融し、前記放射性物質をスラグ中に包含さ
せる放射能汚染金属の溶融処理法において、前記
スラグ剤としての無機塩化物と無機フツ化物の混
合物から成るスラグ剤を用いることを特徴とする
放射能汚染アルミニウムの溶融除染方法。 2 前記スラグ剤の融点は処理アルミニウム材の
融点よりも高くても200℃以下となるように成分
調整を施し、溶融処理はスラグ剤およびアルミニ
ウム材が溶解する低い温度において行う特許請求
の範囲第1項記載の放射能汚染アルミニウムの溶
融除染方法。 3 前記スラグ剤の組成に少なくとも2種類の無
機塩化物を含み、一方は化合物のイオン間引力が
強く、他方は弱くかつ前者に対する後者のモル比
が0.5以上あるスラグ剤を用いる特許請求の範囲
第1項または第2項記載の放射能汚染アルミニウ
ムの溶融除去方法。 4 前記無機塩化物として潮解性が少ないことを
特徴とする化合物である塩化カリウムと塩化バリ
ウムを用いる特許請求の範囲第1項または第2項
記載の放射性能汚染アルミニウムの溶融除染方
法。[Claims] 1. A method for melting radioactively contaminated metal in which a slag agent made of inorganic salts is added to aluminum or an aluminum alloy contaminated with a radioactive substance, the mixture is heated and melted, and the radioactive substance is included in the slag. A method for melting and decontaminating radioactively contaminated aluminum, characterized in that the slag agent is a mixture of an inorganic chloride and an inorganic fluoride. 2. The components of the slag agent are adjusted so that the melting point of the slag agent is at most 200°C or lower than the melting point of the treated aluminum material, and the melting treatment is carried out at a low temperature at which the slag agent and the aluminum material melt. Method for melting and decontaminating radioactively contaminated aluminum as described in Section 1. 3. The slag agent contains at least two types of inorganic chlorides in its composition, one of which has a strong ionic attraction of the compound, the other has a weak attraction, and the molar ratio of the latter to the former is 0.5 or more. The method for melting and removing radioactively contaminated aluminum according to item 1 or 2. 4. The method for melting and decontaminating radiation-contaminated aluminum according to claim 1 or 2, which uses potassium chloride and barium chloride, which are compounds characterized by low deliquescent properties, as the inorganic chlorides.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP14754584A JPS6126899A (en) | 1984-07-18 | 1984-07-18 | Method for melting and decontaminating radioactively contaminated aluminum |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP14754584A JPS6126899A (en) | 1984-07-18 | 1984-07-18 | Method for melting and decontaminating radioactively contaminated aluminum |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS6126899A JPS6126899A (en) | 1986-02-06 |
| JPH0320719B2 true JPH0320719B2 (en) | 1991-03-20 |
Family
ID=15432742
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP14754584A Granted JPS6126899A (en) | 1984-07-18 | 1984-07-18 | Method for melting and decontaminating radioactively contaminated aluminum |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6126899A (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE69739049D1 (en) | 1996-04-02 | 2008-11-27 | Chisso Corp | Liquid crystal compounds, liquid crystal-containing preparations, and liquid crystal displays prepared from these compounds |
-
1984
- 1984-07-18 JP JP14754584A patent/JPS6126899A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS6126899A (en) | 1986-02-06 |
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