EP0774155A1 - Method of reprocessing metal parts contaminated with uranium - Google Patents

Method of reprocessing metal parts contaminated with uranium

Info

Publication number
EP0774155A1
EP0774155A1 EP95925717A EP95925717A EP0774155A1 EP 0774155 A1 EP0774155 A1 EP 0774155A1 EP 95925717 A EP95925717 A EP 95925717A EP 95925717 A EP95925717 A EP 95925717A EP 0774155 A1 EP0774155 A1 EP 0774155A1
Authority
EP
European Patent Office
Prior art keywords
uranium
glass
slag
metal parts
melt
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.)
Granted
Application number
EP95925717A
Other languages
German (de)
French (fr)
Other versions
EP0774155B1 (en
Inventor
Ernst Haas
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Siemens AG
Original Assignee
Siemens AG
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Filing date
Publication date
Application filed by Siemens AG filed Critical Siemens AG
Publication of EP0774155A1 publication Critical patent/EP0774155A1/en
Application granted granted Critical
Publication of EP0774155B1 publication Critical patent/EP0774155B1/en
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

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Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28—Treating solids
    • G21F9/30—Processing
    • G21F9/301—Processing by fixation in stable solid media
    • G21F9/302—Processing by fixation in stable solid media in an inorganic matrix
    • G21F9/305—Glass or glass like matrix
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28—Treating solids
    • G21F9/30—Processing
    • G21F9/308—Processing by melting the waste

Definitions

  • the invention relates to a method for recycling metal parts which are radioactively contaminated by uranium, whereby the metal parts are melted so that a melt and a slag form, and wherein the metal parts and / or the melt and / or the not yet solidified slag is mixed with U 235 depleted uranium.
  • the slag has to be classified as radioactive waste containing nuclear fuel, which requires special safety precautions in handling and disposal. If the contamination has been caused by uranium nuclear fuel, which contains 3.1% U 235, for example, melt decontamination can only be used to a limited extent if more than approximately 3 grams of U 235 are to be expected in 100 kg of slag. Because the uranium passes into the slag during the smelting process and is concentrated there, this limit value is usually exceeded unless additional measures are taken. Exceeding the limit could be avoided by adding another non-uranium slag to the slag containing uranium. The uranium concentration could be reduced to the necessary extent with a sufficiently large amount of uranium-free slag. However, the amount of slag required would be so large that the total amount of slag would be increased uneconomically. Significantly more slag would have to be used than before.
  • a method has also been proposed which provides for renaturation of the uranium which causes the contamination. It is important that the isotope composition of the uranium that is to be incorporated into the slag or is already incorporated is changed such that it corresponds to the isotope composition of natural uranium. This means that the proportion of U 235 in uranium must not exceed approximately 0.7%. Uranium, which is equivalent to natural uranium in its isotope composition, need not be subjected to the safety regulations that apply to uranium nuclear fuel.
  • the invention had for its object to provide a method for recycling metal parts which are radioactively contaminated by uranium, with which a reliable and complete renaturation of the uranium is possible, so that the slag formed can then be handled and disposed of in a simple manner .
  • the object is achieved according to the invention in that the uranium depleted of U 235 is admixed in the form of uranium glass.
  • Uranium can be mixed homogeneously with the uranium that caused the contamination during the melt decontamination process.
  • the same advantage is achieved if the uranium glass, which contains the uranium depleted of U 235, the still untreated, metallic scrap, and / or the melt and / or the still liquid slag, if this has already been separated from the rest of the melt, admixed.
  • the homogeneous mixing and incorporation of the uranium from the uranium glass has the advantage that the isotope composition of the uranium in the slag is also homogeneous. There cannot be any individual zones in the slag that have an excessively high U 235 concentration. Consequently, since its uranium content corresponds to the natural uranium with regard to the isotope composition, the entire slag need not be treated as waste containing nuclear fuel. The slag can advantageously be handled and disposed of in a simple manner.
  • the uranium depleted on U 235 is mixed in, for example, in the form of uranium glass powder, uranium glass beads, uranium glass rods and / or pieces of uranium glass. Such parts made of uranium glass can be produced using known methods and can be prepared.
  • uranium glass is a glass which is thin at the melting temperature of the metal of the metal parts. This has the advantage that an improved slag liquefaction is achieved solely through the glass, regardless of its uranium content. This then leads to an even better homogeneous distribution of the uranium added.
  • uranium glass of the type alkali oxide / SiO 2 / U O 2 is added.
  • Such a glass can contain 50% uranium.
  • the alkali oxide can e.g. Be Na2 ⁇ .
  • uranium glass whose uranium has a U 235 isotope content of less than 0.7%, e.g. approx. 0.2%, has been added. A sufficient amount of U 235 isotope is then obtained in the slag, which is advantageously so small that the slag can be disposed of without problems. If e.g. the U 235 isotope content of the uranium that caused the contamination should be 3.1%. With uranium glass, the U 235 isotope content of which is 0.2%, a U 235 isotope content of less than 0 is achieved in the slag Is 7%.
  • uranium glass which contains less than 50% uranium
  • the uranium glass contains less than 40%, for example between 5% and 15%, of uranium.
  • the density of a uranium glass is lower if the uranium content in the glass is smaller. If the uranium content in the uranium glass is significantly less than 50%, a uranium-containing slag is formed, the density of which is significantly lower than the density of the iron-containing melt. As a result, the slag floats on the melt and can then be separated from the melt particularly easily, for example skimmed off.
  • the density of uranium glass with one For example, uranium content of 10% is 3.5 g / cm. With a uranium content of 50%, the density of the uranium glass is 7.7 g / cm- - The density of iron is approx. 7.8 g / ⁇ rtv- *.
  • the depleted uranium is admixed in the form of uranium glass.
  • This uranium glass contains, for example, 10% uranium, the U 235 isotope content of which is 0.2%. Then advantageously only 6.2 kg of glass are required to reduce the U 235 isotope content of 55.4 kg of slag to such an extent that the slag is easy to handle and can be stored and disposed of with simple means.
  • the advantage is achieved in particular that the slag which arises during melt decontamination and contains uranium is easy to dispose of. The burden on staff and dust filters with uranium dust is largely avoided.

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Inorganic Chemistry (AREA)
  • Processing Of Solid Wastes (AREA)
  • Manufacture And Refinement Of Metals (AREA)
  • Glass Compositions (AREA)

Abstract

The invention concerns a method of reprocessing metal parts contaminated with uranium. The metal parts are smelted to form a melt and slag and U235-depleted uranium is mixed with the metal parts, the melt and/or the slag. It is envisaged that the U235-depleted uranium should be added in the form of uranium glass.

Description

Beschreibungdescription
Verfahren zur Verwertung von Metallteilen, die durch Uran ra¬ dioaktiv kontaminiert sindProcess for recycling metal parts that are radioactive contaminated by uranium
Die Erfindung betrifft ein Verfahren zur Verwertung von Me¬ tallteilen, die durch Uran radioaktiv kontaminiert sind, wo¬ bei die Metallteile aufgeschmolzen werden, so daß sich eine Schmelze und eine Schlacke bilden, und wobei den Metallteilen und/oder der Schmelze und/oder der noch nicht erstarrten Schlacke an U 235 verarmtes Uran beigemischt wird.The invention relates to a method for recycling metal parts which are radioactively contaminated by uranium, whereby the metal parts are melted so that a melt and a slag form, and wherein the metal parts and / or the melt and / or the not yet solidified slag is mixed with U 235 depleted uranium.
Beim Abbau und auch beim Betrieb kerntechnischer Anlagen fällt in großem Umfang kontaminierter metallischer Schrott an, der beseitigt oder verwertet werden muß. Es ist üblich, diesen Schrott der sogenannten Schmelzdekontamination zu un¬ terziehen. Dabei wird das Metall aufgeschmolzen. Einige die Kontamination verursachenden radioaktiven Stoffe, die sich vor dem Aufschmelzen auf der Oberfläche der Metallteile be- funden haben, werden während des Schmelzdekontaminationspro¬ zesses in die sich bildende Schlacke eingebunden. Die sich außerdem bildende Schmelze, deren Volumen deutlich größer ist als das Volumen der Schlacke, bleibt weitgehend frei von ra¬ dioaktiven Stoffen.During the dismantling and also in the operation of nuclear plants, there is a large amount of contaminated metallic scrap which must be disposed of or recycled. It is customary to subject this scrap to so-called melt decontamination. The metal is melted. Some of the radioactive substances causing the contamination, which were on the surface of the metal parts prior to melting, are incorporated into the slag which forms during the melt decontamination process. The melt which also forms, the volume of which is significantly greater than the volume of the slag, remains largely free of radioactive substances.
Die Schlacke muß in der Regel als radioaktiver, kernbrenn- stoffhaltiger Abfall eingestuft werden, was besondere Sicher¬ heitsvorkehrungen bei der Handhabung und bei der Entsorgung erfordert. Sofern die Kontamination durch Uran-Kernbrennstoff hervorgerufen worden ist, der beispielsweise 3,1 % U 235 ent¬ hält, kann eine Schmelzdekontamination nur eingeschränkt an¬ gewandt werden, falls in 100 kg Schlacke mehr als ungefähr 3 Gramm U 235 zu erwarten sind. Weil beim Schmelzprozeß das Uran in die Schlacke übergeht und dort aufkonzentriert wird, wird dieser Grenzwert in der Regel überschritten, sofern keine zusätzlichen Maßnahmen ergriffen werden. Ein Überschreiten des Grenzwertes könnte vermieden werden, indem der Schlacke, die Uran enthält, eine andere Schlacke, die kein Uran enthält, beigemischt wird. Mit einer ausrei¬ chend großen Menge uranfreier Schlacke könnte die Urankonzen- tration im notwendigen Ausmaß verkleinert werden. Die notwen¬ dige Schlackenmenge wäre aber so groß, daß die Gesamt- schlackenmenge unwirtschaftlich erhöht würde. Es müßte deut¬ lich mehr Schlacke als zuvor verwertet werden.As a rule, the slag has to be classified as radioactive waste containing nuclear fuel, which requires special safety precautions in handling and disposal. If the contamination has been caused by uranium nuclear fuel, which contains 3.1% U 235, for example, melt decontamination can only be used to a limited extent if more than approximately 3 grams of U 235 are to be expected in 100 kg of slag. Because the uranium passes into the slag during the smelting process and is concentrated there, this limit value is usually exceeded unless additional measures are taken. Exceeding the limit could be avoided by adding another non-uranium slag to the slag containing uranium. The uranium concentration could be reduced to the necessary extent with a sufficiently large amount of uranium-free slag. However, the amount of slag required would be so large that the total amount of slag would be increased uneconomically. Significantly more slag would have to be used than before.
Es ist auch schon ein Verfahren vorgeschlagen worden, das ei¬ ne Renaturierung des Urans, das die Kontamination verursacht, vorsieht. Es kommt dabei darauf an, daß die Isotopenzusammen¬ setzung des Urans, das in die Schlacke eingebunden werden soll oder bereits eingebunden ist, derart verändert wird, daß sie der Isotopenzusammensetzung des natürlichen Urans ent¬ spricht. Das bedeutet, daß der Anteil des U 235 im Uran nicht größer als ungefähr 0,7 % sein darf. Uran, das in seiner Iso¬ topenzusammensetzung dem natürlichen Uran gleichkommt, braucht nicht den Sicherheitsbestimmungen unterworfen zu wer- den, die für Uran-Kernbrennstoff gelten.A method has also been proposed which provides for renaturation of the uranium which causes the contamination. It is important that the isotope composition of the uranium that is to be incorporated into the slag or is already incorporated is changed such that it corresponds to the isotope composition of natural uranium. This means that the proportion of U 235 in uranium must not exceed approximately 0.7%. Uranium, which is equivalent to natural uranium in its isotope composition, need not be subjected to the safety regulations that apply to uranium nuclear fuel.
Es ist bereits bekannt, daß zur Verringerung des Isotopenan¬ teils des U 235 den Metallteilen, der Schmelze und/oder der noch nicht erstarrten Schlacke an U 235 verarmtes Uran beige- mischt wird. Dadurch erhält man, wenn das Verfahren durchge¬ führt ist, eine Schlacke, in die Uran eingebunden ist, dessen U 235-Isotopenanteil dem U 235-Isotopenanteil von natürlichem Uran entspricht oder diesen sogar unterschreitet.It is already known that in order to reduce the isotope content of the U 235, uranium depleted in U 235 is admixed with the metal parts, the melt and / or the not yet solidified slag. When the process is carried out, this gives a slag into which uranium is incorporated, the U 235 isotope portion of which corresponds to or even falls below the U 235 isotope portion of natural uranium.
Bisher war es üblich, das an U 235 verarmte Uran in der Form von UO2 oder U3O8 beizumischen. Diese Oxide liegen als Pulver vor. Ein solches Pulver wird erfahrungsgemäß nicht gleichmäßig in der Schmelze oder in der Schlacke verteilt. Folglich kann es dazu kommen, daß eine Schlackenprobe nicht den gewünschten niedrigen U 235-Isotopenanteil hat. Beim Zu¬ mischen dieses Pulvers gelangt Staub in die Umgebungsluft. Der Staub muß dann zum Schutz des Personals durch Filter ent¬ fernt werden.Until now, it was common to mix the uranium depleted in U 235 in the form of UO2 or U3O8. These oxides are in powder form. Experience has shown that such a powder is not evenly distributed in the melt or in the slag. As a result, a slag sample may not have the desired low U 235 isotope content. When this powder is mixed, dust gets into the ambient air. The dust must then be removed by filters to protect the personnel.
Der Erfindung lag die Aufgabe zugrunde, ein Verfahren zur Verwertung von Metallteilen, die durch Uran radioaktiv kontaminiert sind, anzugeben, mit dem eine zuverlässige und vollständige Renaturierung des Urans möglich ist, so daß dann die gebildete Schlacke in einfacher Weise zu handhaben und zu entsorgen ist.The invention had for its object to provide a method for recycling metal parts which are radioactively contaminated by uranium, with which a reliable and complete renaturation of the uranium is possible, so that the slag formed can then be handled and disposed of in a simple manner .
Die Aufgabe wird gemäß der Erfindung dadurch gelöst, daß das an U 235 verarmte Uran in der Form von Uranglas beigemischt wird.The object is achieved according to the invention in that the uranium depleted of U 235 is admixed in the form of uranium glass.
Damit wird der Vorteil erzielt, daß das an U 235 verarmteThis has the advantage that the depleted of U 235
Uran während des Schmelzdekontaminationsprozesses homogen mit dem Uran, das die Kontamination verursacht hat, vermischt werden kann. Man erzielt den gleichen Vorteil, wenn man das Uranglas, das das an U 235 verarmte Uran enthält, dem noch unbehandelten, metallischen Schrott, und/oder der Schmelze und/oder der noch flüssigen Schlacke, wenn diese bereits von der übrigen Schmelze abgetrennt ist, beimischt.Uranium can be mixed homogeneously with the uranium that caused the contamination during the melt decontamination process. The same advantage is achieved if the uranium glass, which contains the uranium depleted of U 235, the still untreated, metallic scrap, and / or the melt and / or the still liquid slag, if this has already been separated from the rest of the melt, admixed.
Durch die homogene Vermischung und Einbindung des Urans aus dem Uranglas wird der Vorteil erzielt, daß die Isotopenzusam¬ mensetzung des Urans in der Schlacke ebenfalls homogen ist. Es kann keine einzelnen Zonen in der Schlacke geben, die eine zu hohe U 235-Konzentration haben. Folglich braucht die ge¬ samte Schlacke, da ihr Urananteil hinsichtlich der Isotopen- Zusammensetzung dem natürlichen Uran entspricht, nicht als kernbrennstoffhaltiger Abfall behandelt zu werden. Man kann vorteilhafterweise die Schlacke in einfacher Weise handhaben und entsorgen.The homogeneous mixing and incorporation of the uranium from the uranium glass has the advantage that the isotope composition of the uranium in the slag is also homogeneous. There cannot be any individual zones in the slag that have an excessively high U 235 concentration. Consequently, since its uranium content corresponds to the natural uranium with regard to the isotope composition, the entire slag need not be treated as waste containing nuclear fuel. The slag can advantageously be handled and disposed of in a simple manner.
Das an U 235 verarmte Uran wird beispielsweise in der Form von Uranglasgrieß, Uranglasperlen, Uranglasstäben und/oder Uranglasstücken beigemischt. Derartige Teile aus Uranglas sind mit bekannten Verfahren herstellbar und können bevorra¬ tet werden.The uranium depleted on U 235 is mixed in, for example, in the form of uranium glass powder, uranium glass beads, uranium glass rods and / or pieces of uranium glass. Such parts made of uranium glass can be produced using known methods and can be prepared.
Beispielsweise wird ein bei niedriger Temperatur schmelzendes Uranglaε beigemischt. Dabei kommt es darauf an, daß das Uran¬ glas ein bei der Schmelztemperatur des Metalls der Metall¬ teile dünnflüssiges Glas ist. Damit wird der Vorteil erzielt, daß allein durch das Glas, unabhängig von dessen Urananteil, eine verbesserte Schlackenverflüssigung erzielt wird. Diese führt dann zu einer noch besseren homogenen Verteilung des beigemischten Urans.For example, a glass of uranium melting at low temperature is added. It is important that the uranium glass is a glass which is thin at the melting temperature of the metal of the metal parts. This has the advantage that an improved slag liquefaction is achieved solely through the glass, regardless of its uranium content. This then leads to an even better homogeneous distribution of the uranium added.
Beispielsweise wird Uranglas des Typs Alkalioxid/Siθ2/Uθ2 beigemischt. Ein solches Glas kann 50 % Uran enthalten. Das Alkalioxid kann z.B. Na2θ sein.For example, uranium glass of the type alkali oxide / SiO 2 / U O 2 is added. Such a glass can contain 50% uranium. The alkali oxide can e.g. Be Na2θ.
Beispielsweise wird Uranglas, dessen Uran einen U 235 Iso¬ topenanteil unter 0,7 %, z.B. ca. 0,2 %, hat, beigemischt. Man erreicht dann bei ausreichender Zugabe in der Schlacke einen U 235 Isotopenanteil, der vorteilhafterweise so klein ist, daß die Schlacke problemlos entsorgt werden kann. Falls z.B. der U 235 Isotopenanteil des Urans, das die Kontamina¬ tion verursacht hat, 3,1 % betragen sollte, erreicht man mit Uranglas, dessen U 235 Isotopenanteil 0,2 % ist, in der Schlacke einen U 235-Isotopenanteil, der kleiner als 0,7 % ist.For example, uranium glass, whose uranium has a U 235 isotope content of less than 0.7%, e.g. approx. 0.2%, has been added. A sufficient amount of U 235 isotope is then obtained in the slag, which is advantageously so small that the slag can be disposed of without problems. If e.g. the U 235 isotope content of the uranium that caused the contamination should be 3.1%. With uranium glass, the U 235 isotope content of which is 0.2%, a U 235 isotope content of less than 0 is achieved in the slag Is 7%.
Beispielsweise wird Uranglas, das weniger als 50 % Uran ent¬ hält, beigemischt. Insbesondere enthält das Uranglas weniger als 40 %, z.B. zwischen 5 % und 15 %, Uran. Die Dichte eines Uranglases ist kleiner wenn der Urananteil im Glas kleiner ist. Falls der Urananteil im Uranglas deutlich kleiner als 50 % ist, wird eine uranhaltige Schlacke gebildet, deren Dichte deutlich kleiner als die Dichte der eisenhaltigen Schmelze ist. Dadurch schwimmt die Schlacke auf der Schmelze und kann dann besonders leicht von der Schmelze abgetrennt, z.B. abgeschöpft, werden. Die Dichte von Uranglas mit einem Urananteil von z.B. 10% ist 3,5 g/cm- . Bei einem Urananteil von 50 % beträgt die Dichte des Uranglases 7,7 g/cm- - Die Dichte von Eisen ist ca. 7,8 g/αrtv-* .For example, uranium glass, which contains less than 50% uranium, is added. In particular, the uranium glass contains less than 40%, for example between 5% and 15%, of uranium. The density of a uranium glass is lower if the uranium content in the glass is smaller. If the uranium content in the uranium glass is significantly less than 50%, a uranium-containing slag is formed, the density of which is significantly lower than the density of the iron-containing melt. As a result, the slag floats on the melt and can then be separated from the melt particularly easily, for example skimmed off. The density of uranium glass with one For example, uranium content of 10% is 3.5 g / cm. With a uranium content of 50%, the density of the uranium glass is 7.7 g / cm- - The density of iron is approx. 7.8 g / αrtv- *.
Im folgenden wird an einem Beispiel erläutert, wieviel Uran¬ glas für das Verfahren nach der Erfindung benötigt wird:The following is an example of how much uranium glass is required for the process according to the invention:
Bei einer Schmelzdekontamination von kontaminierten Metall¬ teilen sind 55,4 kg Schlacke gebildet worden, die 69,25 g U 238 und 2,21 g U 235 enthalten. Das entspricht einem U 235 Isotopenanteil von 3,09 %. Zur Renaturierung soll der U 235- Isotopenanteil von 3,09 % auf 0,5 % erniedrigt werden. Dieser Anteil liegt unterhalb des U 235 Isotopenanteils von natürli¬ chem Uran. Um die gewünschte Erniedrigung zu erzielen, wird an U 235 verarmtes oder abgereichertes Uran eingesetzt. Der U 235 Isotopenanteil dieses verarmten Urans beträgt z.B. 0,2 %. Von diesem verarmten Uran sind 620 g notwendig, um ei¬ ne Schlacke mit 0,5 % U 235 Isotopenanteil zu bekommen.During melt decontamination of contaminated metal parts, 55.4 kg of slag were formed, which contain 69.25 g of U 238 and 2.21 g of U 235. This corresponds to a U 235 isotope content of 3.09%. For renaturation, the U 235 isotope content should be reduced from 3.09% to 0.5%. This fraction lies below the U 235 isotope fraction of natural uranium. Depleted or depleted uranium is used on U 235 to achieve the desired degradation. The U 235 isotope portion of this depleted uranium is e.g. 0.2%. 620 g of this depleted uranium are necessary in order to obtain a slag with 0.5% U 235 isotope content.
Beim Verfahren nach der Erfindung wird das verarmte Uran in der Form von Uranglas beigemischt. Dieses Uranglas enthält beispielsweise 10 % Uran, dessen U 235 Isotopenanteil 0,2 % ist. Dann sind vorteilhafterweise nur 6,2 kg Glas erforder¬ lich, um den U 235 Isotopenanteil von 55,4 kg Schlacke soweit zu erniedrigen, daß die Schlacke leicht handhabbar und mit einfachen Mitteln zu lagern und zu entsorgen ist.In the method according to the invention, the depleted uranium is admixed in the form of uranium glass. This uranium glass contains, for example, 10% uranium, the U 235 isotope content of which is 0.2%. Then advantageously only 6.2 kg of glass are required to reduce the U 235 isotope content of 55.4 kg of slag to such an extent that the slag is easy to handle and can be stored and disposed of with simple means.
Mit dem Verfahren nach der Erfindung wird insbesondere der Vorteil erzielt, daß die bei einer Schmelzdekontamination entstehende Schlacke, die Uran enthält, leicht zu entsorgen ist. Die Belastung des Personals und von Staubfiltern mit Uranstaub wird weitgehend vermieden. With the method according to the invention, the advantage is achieved in particular that the slag which arises during melt decontamination and contains uranium is easy to dispose of. The burden on staff and dust filters with uranium dust is largely avoided.

Claims

Patentansprüche claims
1. Verfahren zur Verwertung von Metallteilen, die durch Uran radioaktiv kontaminiert sind, wobei die Metallteile aufgeschmolzen werden, so daß sich eine Schmelze und eine Schlacke bilden, und wobei den Metallteilen und/oder der Schmelze und/oder der noch nicht erstarrten Schlacke an U 235 verarmtes Uran beigemischt wird, d a d u r c h g e k e n n z e i c h n e t , daß das an U 235 verarmte Uran in der Form von Uranglas beigemischt wird.1. A process for the recovery of metal parts which are radioactively contaminated by uranium, the metal parts being melted so that a melt and a slag form, and the metal parts and / or the melt and / or the not yet solidified slag at U 235 depleted uranium is added, characterized in that the uranium depleted of U 235 is added in the form of uranium glass.
2. Verfahren nach Anspruch 1, d a d u r c h g e k e n n z e i c h n e t , daß das Uranglas die Form von Grieß und/oder Perlen und/oder Stäben und/oder Stücken hat.2. The method according to claim 1, that the uranium glass has the form of semolina and / or pearls and / or rods and / or pieces.
3. Verfahren nach einem der Ansprüche 1 oder 2, d a d u r c h g e k e n n z e i c h n e t , daß das Uranglas ein bei der Schmelztemperatur des Metalls der Metallteile dünnflüssiges Glas ist.3. The method according to any one of claims 1 or 2, so that the uranium glass is a glass which is thin at the melting temperature of the metal of the metal parts.
4. Verfahren nach einem der Ansprüche 1 bis 3, d a d u r c h g e k e n n z e i c h n e t , daß das Uranglas ein Glas des Typs Alkalioxid/Siθ2/Uθ2 ist.4. The method according to any one of claims 1 to 3, so that the uranium glass is a glass of the type alkali oxide / SiO 2 / U O 2.
5. Verfahren nach einem der Ansprüche i bis 4, d a d u r c h g e k e n n z e i c h n e t , daß der U 235-Isotopenanteil im Uran des Uranglases unter 0,7 % beträgt.5. The method according to any one of claims i to 4, that the U 235 isotope content in the uranium of the uranium glass is below 0.7%.
6. Verfahren nach einem der Ansprüche 1 bis 5, d a d u r c h g e k e n n z e i c h n e t , daß der Urananteil im Uranglas kleiner als 50 % ist. 6. The method according to any one of claims 1 to 5, that the uranium content in the uranium glass is less than 50%.
EP95925717A 1994-08-01 1995-07-21 Method of reprocessing metal parts contaminated with uranium Expired - Lifetime EP0774155B1 (en)

Applications Claiming Priority (3)

Application Number Priority Date Filing Date Title
DE4427179A DE4427179A1 (en) 1994-08-01 1994-08-01 Process for recycling metal parts that are radioactively contaminated by uranium
DE4427179 1994-08-01
PCT/DE1995/000964 WO1996004663A1 (en) 1994-08-01 1995-07-21 Method of reprocessing metal parts contaminated with uranium

Publications (2)

Publication Number Publication Date
EP0774155A1 true EP0774155A1 (en) 1997-05-21
EP0774155B1 EP0774155B1 (en) 2000-09-20

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Country Status (11)

Country Link
US (1) US5732366A (en)
EP (1) EP0774155B1 (en)
JP (1) JP3471023B2 (en)
AU (1) AU2975495A (en)
CA (1) CA2196438C (en)
CZ (1) CZ291275B6 (en)
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US5885326A (en) * 1997-06-27 1999-03-23 The United States Of America As Represented By The United States Department Of Energy Process for removing technetium from iron and other metals

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DE3204204C2 (en) * 1982-02-08 1986-05-07 Kraftwerk Union AG, 4330 Mülheim Procedure for conditioning radioactive waste
DE3318377C2 (en) * 1983-05-20 1986-05-15 Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover Process for the decontamination of radioactively contaminated iron and / or steel scrap
JPS6145999A (en) * 1984-08-10 1986-03-06 株式会社日立製作所 Method of melting and decontaminating radioactive contaminated aluminum material
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DE4104396A1 (en) * 1990-12-06 1992-06-11 Bader Bibiana Melting noxious waste-contg. charge to produce environmentally safe useful prod. - by mixing charge except cullet and frit, delivering batchwise with indirect preheating etc.
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AU2975495A (en) 1996-03-04
EP0774155B1 (en) 2000-09-20
JPH10503591A (en) 1998-03-31
DE59508743D1 (en) 2000-10-26
RU2153719C2 (en) 2000-07-27
JP3471023B2 (en) 2003-11-25
UA39139C2 (en) 2001-06-15
DE4427179A1 (en) 1996-02-08
ES2151074T3 (en) 2000-12-16
WO1996004663A1 (en) 1996-02-15
CA2196438C (en) 2001-12-18
CZ291275B6 (en) 2003-01-15
CZ7497A3 (en) 1997-05-14
CA2196438A1 (en) 1996-02-15
US5732366A (en) 1998-03-24

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