EP0774155B1 - Method of reprocessing metal parts contaminated with uranium - Google Patents
Method of reprocessing metal parts contaminated with uranium Download PDFInfo
- Publication number
- EP0774155B1 EP0774155B1 EP95925717A EP95925717A EP0774155B1 EP 0774155 B1 EP0774155 B1 EP 0774155B1 EP 95925717 A EP95925717 A EP 95925717A EP 95925717 A EP95925717 A EP 95925717A EP 0774155 B1 EP0774155 B1 EP 0774155B1
- 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.)
- Expired - Lifetime
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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 slag form, and being the metal parts and / or the melt and / or the not yet solidified Slag is mixed with U 235 depleted uranium.
- FR-A-2 652 193 describes a method for immobilization (Glazing) of radioactive waste, e.g. can be present as uranium oxide.
- melt decontamination When dismantling and also when operating nuclear facilities falls to a large extent contaminated metallic scrap that must be disposed of or recycled. It is usual, to subject this scrap to so-called melt decontamination. The metal is melted. Some of them Contamination-causing radioactive substances prior to melting on the surface of the metal parts have during the melt decontamination process embedded in the slag that forms. Which also forming melt, the volume of which is significantly larger than the volume of the slag, remains largely free of radioactive Fabrics. Processes based on this principle are e.g. from the INSPEC database under No. AN 2709816, at No. AN 2118676 or under No. AN 2596010 known.
- the slag must be radioactive and contain nuclear fuel Waste can be classified as special safety precautions in handling and disposal required. If the contamination by uranium nuclear fuel has been caused, which contains, for example, 3.1% U 235, can only apply melt decontamination to a limited extent if more than approximately in 100 kg of slag 3 grams of U 235 are expected. Because in the melting process Uranium passes into the slag and is concentrated there, this limit is usually exceeded, provided that no additional measures are taken.
- the invention was based on the object of a method for Recycling of metal parts that are radioactively contaminated by uranium are to be specified with a reliable and complete Renaturation of uranium is possible, so that then formed slag to handle and easy is to be disposed of.
- the object is achieved in that the Uranium depleted in the form of uranium glass mixed into U 235 and that the uranium glass takes the form of semolina and / or pearls and / or bars and / or pieces.
- uranium glass Through the homogeneous mixing and incorporation of uranium
- the advantage of uranium glass is that the isotope composition uranium in the slag is also homogeneous. There can be no single zones in the slag, one have too high a U 235 concentration. Hence the whole needs Slag because of its uranium content with respect to the isotopes composition corresponds to natural uranium, not as nuclear fuel waste to be treated.
- the uranium depleted on U 235 is in the form of uranium glass powder, Uranium glass beads, uranium glass rods and / or uranium glass pieces added. Such parts made of uranium glass can be produced using known methods and can be stored become.
- Uranium glass For example, one that melts at low temperature Uranium glass added. It is important that the uranium glass one at the melting temperature of the metal of the metal parts is thin glass. This gives the advantage that through the glass alone, regardless of its uranium content, improved slag liquefaction is achieved. This then leads to an even better homogeneous distribution of the admixed uranium.
- uranium glass of the alkali oxide / SiO 2 / UO 2 type is added.
- Such a glass can contain 50% uranium.
- the alkali oxide can be Na 2 O, for example.
- uranium glass whose uranium contains a U 235 isotope below 0.7%, e.g. approx. 0.2%, has been added. It is then achieved with sufficient addition in the slag a U 235 isotope portion, which is advantageously so small is that the slag can be disposed of easily. If e.g. the U 235 isotope portion of uranium, which is the contamination caused, should be 3.1%, can be reached with Uranium glass, the U 235 isotope content of which is 0.2%, in the Slag has a U 235 isotope content that is less than 0.7% is.
- uranium glass that contains less than 50% uranium is added.
- 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 a uranium content of, for example, 10% is 3.5 g / cm 3 . With a uranium content of 50%, the density of the uranium glass is 7.7 g / cm 3 . The density of iron is approximately 7.8 g / cm 3 .
- the depleted uranium is in added to the shape of uranium glass.
- This uranium glass contains for example 10% uranium, the U 235 isotope content 0.2% is. Then only 6.2 kg of glass are advantageously required, around the U 235 isotope content of 55.4 kg slag so far to lower that the slag easy to handle and with simple means of storage and disposal.
Description
Die Erfindung betrifft ein 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.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 slag form, and being the metal parts and / or the melt and / or the not yet solidified Slag is mixed with U 235 depleted uranium.
In der FR-A-2 652 193 ist ein Verfahren zur Immobilisierung (Verglasung) von radioaktivem Abfall beschrieben, der z.B. als Uranoxid vorliegen kann.FR-A-2 652 193 describes a method for immobilization (Glazing) of radioactive waste, e.g. can be present as uranium oxide.
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 unterziehen. Dabei wird das Metall aufgeschmolzen. Einige die Kontamination verursachenden radioaktiven Stoffe, die sich vor dem Aufschmelzen auf der Oberfläche der Metallteile befunden haben, werden während des Schmelzdekontaminationsprozesses 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 radioaktiven Stoffen. Nach diesem Prinzip arbeitende Verfahren sind z.B. aus der Datenbank INSPEC unter No. AN 2709816, unter No. AN 2118676 oder unter No. AN 2596010 bekannt.When dismantling and also when operating nuclear facilities falls to a large extent contaminated metallic scrap that must be disposed of or recycled. It is usual, to subject this scrap to so-called melt decontamination. The metal is melted. Some of them Contamination-causing radioactive substances prior to melting on the surface of the metal parts have during the melt decontamination process embedded in the slag that forms. Which also forming melt, the volume of which is significantly larger than the volume of the slag, remains largely free of radioactive Fabrics. Processes based on this principle are e.g. from the INSPEC database under No. AN 2709816, at No. AN 2118676 or under No. AN 2596010 known.
Die Schlacke muß in der Regel als radioaktiver, kernbrennstoffhaltiger Abfall eingestuft werden, was besondere Sicherheitsvorkehrungen bei der Handhabung und bei der Entsorgung erfordert. Sofern die Kontamination durch Uran-Kernbrennstoff hervorgerufen worden ist, der beispielsweise 3,1 % U 235 enthält, kann eine Schmelzdekontamination nur eingeschränkt angewandt 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.As a rule, the slag must be radioactive and contain nuclear fuel Waste can be classified as special safety precautions in handling and disposal required. If the contamination by uranium nuclear fuel has been caused, which contains, for example, 3.1% U 235, can only apply melt decontamination to a limited extent if more than approximately in 100 kg of slag 3 grams of U 235 are expected. Because in the melting process Uranium passes into the slag and is concentrated there, this limit is usually exceeded, provided that no additional measures are taken.
Ein Überschreiten des Grenzwertes könnte vermieden werden, indem der Schlacke, die Uran enthält, eine andere Schlacke, die kein Uran enthält, beigemischt wird. Mit einer ausreichend großen Menge uranfreier Schlacke könnte die Urankonzentration im notwendigen Ausmaß verkleinert werden. Die notwendige Schlackenmenge wäre aber so groß, daß die Gesamtschlakkenmenge unwirtschaftlich erhöht würde. Es müßte deutlich mehr Schlacke als zuvor verwertet werden.Exceeding the limit could be avoided by the slag that contains uranium, another slag, which does not contain uranium, is added. With a sufficient large amount of uranium-free slag could cause the uranium concentration to be reduced to the extent necessary. The necessary But the amount of slag would be so large that the total amount of slag would be increased uneconomically. It should be clear more slag can be used than before.
Es ist auch schon ein Verfahren vorgeschlagen worden, das eine Renaturierung des Urans, das die Kontamination verursacht, vorsieht. Es kommt dabei darauf an, daß die Isotopenzusammensetzung des Urans, das in die Schlacke eingebunden werden soll oder bereits eingebunden ist, derart verändert wird, daß sie der Isotopenzusammensetzung des natürlichen Urans entspricht. Das bedeutet, daß der Anteil des U 235 im Uran nicht größer als ungefähr 0,7 % sein darf. Uran, das in seiner Isotopenzusammensetzung dem natürlichen Uran gleichkommt, braucht nicht den Sicherheitsbestimmungen unterworfen zu werden, die für Uran-Kernbrennstoff gelten.A method has also been proposed, the one Renaturation of the uranium that causes the contamination provides. It is important that the isotope composition of the uranium that is bound in the slag should or is already involved, is changed in such a way that it corresponds to the isotope composition of natural uranium. This means that the proportion of U 235 in uranium is not may be greater than approximately 0.7%. Uranium, which is in its isotope composition equals natural uranium, does not need to be subject to safety regulations, that apply to uranium nuclear fuel.
Es ist bereits bekannt, daß zur Verringerung des Isotopenanteils des U 235 den Metallteilen, der Schmelze und/oder der noch nicht erstarrten Schlacke an U 235 verarmtes Uran beigemischt wird. Dadurch erhält man, wenn das Verfahren durchgeführt ist, eine Schlacke, in die Uran eingebunden ist, dessen U 235-Isotopenanteil dem U 235-Isotopenanteil von natürlichem Uran entspricht oder diesen sogar unterschreitet. Ein Verfahren dieser Art ist in der DE 33 18 377 A1 offenbart. It is already known that to reduce the proportion of isotopes of the U 235 the metal parts, the melt and / or the not yet solidified slag mixed with U 235 depleted uranium becomes. This gives you when the procedure is done is a slag in which uranium is bound, the U 235 isotope portion of the U 235 isotope portion of natural Uranium corresponds to or even falls below this. A procedure this type is disclosed in DE 33 18 377 A1.
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 Zumischen dieses Pulvers gelangt Staub in die Umgebungsluft. Der Staub muß dann zum Schutz des Personals durch Filter entfernt werden.So far it has been common to add uranium depleted in U 235 in the form of UO 2 or U 3 O 8 . 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 in, dust gets into the ambient air. The dust must then be removed by filters to protect 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 was based on the object of a method for Recycling of metal parts that are radioactively contaminated by uranium are to be specified with a reliable and complete Renaturation of uranium is possible, so that then formed slag to handle and easy is to be disposed of.
Die Aufgabe wird gemäß der Erfindung dadurch gelöst, daß das an U 235 verarmte Uran in der Form von Uranglas beigemischt wird, und daß das Uranglas die Form von Grieß und/oder Perlen und/oder Stäben und/oder Stücken hat.The object is achieved in that the Uranium depleted in the form of uranium glass mixed into U 235 and that the uranium glass takes the form of semolina and / or pearls and / or bars and / or pieces.
Damit wird der Vorteil erzielt, daß das an U 235 verarmte 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.This has the advantage that the depleted of U 235 Uranium homogeneously with during the melt decontamination process mixed with the uranium that caused the contamination can be. You get the same advantage if you do that Uranium glass, which contains the uranium depleted on U 235, the untreated, metallic scrap, and / or the melt and / or the still liquid slag, if this is already from separated from the rest of the melt.
Durch die homogene Vermischung und Einbindung des Urans aus dem Uranglas wird der Vorteil erzielt, daß die Isotopenzusammensetzung 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 gesamte 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.Through the homogeneous mixing and incorporation of uranium The advantage of uranium glass is that the isotope composition uranium in the slag is also homogeneous. There can be no single zones in the slag, one have too high a U 235 concentration. Hence the whole needs Slag because of its uranium content with respect to the isotopes composition corresponds to natural uranium, not as nuclear fuel waste to be treated. One can advantageously handle the slag in a simple manner and dispose of.
Das an U 235 verarmte Uran wird in der Form von Uranglasgrieß, Uranglasperlen, Uranglasstäben und/oder Uranglasstükken beigemischt. Derartige Teile aus Uranglas sind mit bekannten Verfahren herstellbar und können bevorratet werden.The uranium depleted on U 235 is in the form of uranium glass powder, Uranium glass beads, uranium glass rods and / or uranium glass pieces added. Such parts made of uranium glass can be produced using known methods and can be stored become.
Beispielsweise wird ein bei niedriger Temperatur schmelzendes Uranglas beigemischt. Dabei kommt es darauf an, daß das Uranglas ein bei der Schmelztemperatur des Metalls der Metallteile 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, one that melts at low temperature Uranium glass added. It is important that the uranium glass one at the melting temperature of the metal of the metal parts is thin glass. This gives the advantage that through the glass alone, regardless of its uranium content, improved slag liquefaction is achieved. This then leads to an even better homogeneous distribution of the admixed uranium.
Beispielsweise wird Uranglas des Typs Alkalioxid/SiO2/UO2 beigemischt. Ein solches Glas kann 50 % Uran enthalten. Das Alkalioxid kann z.B. Na2O sein.For example, uranium glass of the alkali oxide / SiO 2 / UO 2 type is added. Such a glass can contain 50% uranium. The alkali oxide can be Na 2 O, for example.
Beispielsweise wird Uranglas, dessen Uran einen U 235 Isotopenanteil 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 Kontamination 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 contains a U 235 isotope below 0.7%, e.g. approx. 0.2%, has been added. It is then achieved with sufficient addition in the slag a U 235 isotope portion, which is advantageously so small is that the slag can be disposed of easily. If e.g. the U 235 isotope portion of uranium, which is the contamination caused, should be 3.1%, can be reached with Uranium glass, the U 235 isotope content of which is 0.2%, in the Slag has a U 235 isotope content that is less than 0.7% is.
Beispielsweise wird Uranglas, das weniger als 50 % Uran enthält, 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/cm3. Bei einem Urananteil von 50 % beträgt die Dichte des Uranglases 7,7 g/cm3. Die Dichte von Eisen ist ca. 7,8 g/cm3.For example, uranium glass that 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 a uranium content of, for example, 10% is 3.5 g / cm 3 . With a uranium content of 50%, the density of the uranium glass is 7.7 g / cm 3 . The density of iron is approximately 7.8 g / cm 3 .
Im folgenden wird an einem Beispiel erläutert, wieviel Uranglas für das Verfahren nach der Erfindung benötigt wird:The following is an example of how much uranium glass for the method according to the invention:
Bei einer Schmelzdekontamination von kontaminierten Metallteilen 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 natürlichem 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 eine Schlacke mit 0,5 % U 235 Isotopenanteil zu bekommen.In the case of melt decontamination of contaminated metal parts 55.4 kg of slag were formed, the 69.25 g U 238 and 2.21 g U 235 included. This corresponds to a U 235 Isotope content of 3.09%. The U 235 isotope portion is intended for renaturation be reduced from 3.09% to 0.5%. This Portion lies below the U 235 isotope portion of natural Uranium. To achieve the desired humiliation, Depleted or depleted uranium is used on U 235. The U 235 isotope fraction of this depleted uranium is e.g. 0.2%. 620 g of this depleted uranium are required to produce one To get 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 erforderlich, 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 in added to the shape of uranium glass. This uranium glass contains for example 10% uranium, the U 235 isotope content 0.2% is. Then only 6.2 kg of glass are advantageously required, around the U 235 isotope content of 55.4 kg slag so far to lower that the slag easy to handle and with simple means of storage and disposal.
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, in particular Advantage achieved that with melt decontamination the resulting slag containing uranium is easy to dispose of is. The burden on staff and dust filters with Uranium dust is largely avoided.
Claims (5)
- Method for processing metal parts which are radioactively contaminated by uranium, with the metal parts being melted down, so that a melt and a slag form, and with U 235-depleted uranium being admixed to the metal parts and/or the melt and/or the slag which has not yet solidified, characterized in that the U 235-depleted uranium is admixed in the form of uranium glass, and in that the uranium glass has the form of granules and/or pearls and/or rods and/or pieces.
- Method according to claim 1, characterized in that the uranium glass is a glass which is liquid at the melting temperature of the metal of the metal parts.
- Method according to one of claims 1 to 2, characterized in that the uranium glass is a glass of the alkali oxide/SiO2/UO2 type.
- Method according to one of claims 1 to 3, characterized in that the U 235 isotope component in the uranium of the uranium glass amounts to less than 0.7 %.
- Method according to one of claims 1 to 4, characterized in that the uranium component in the uranium glass is less than 50 %.
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 EP0774155A1 (en) | 1997-05-21 |
| EP0774155B1 true EP0774155B1 (en) | 2000-09-20 |
Family
ID=6524634
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| EP95925717A Expired - Lifetime EP0774155B1 (en) | 1994-08-01 | 1995-07-21 | Method of reprocessing metal parts contaminated with uranium |
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) |
| DE (2) | DE4427179A1 (en) |
| ES (1) | ES2151074T3 (en) |
| RU (1) | RU2153719C2 (en) |
| UA (1) | UA39139C2 (en) |
| WO (1) | WO1996004663A1 (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE19546789A1 (en) * | 1995-12-14 | 1997-06-19 | Siemens Ag | Process for recycling contaminated metal parts |
| 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 |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE3318377A1 (en) * | 1983-05-20 | 1984-11-22 | Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover | METHOD FOR DECONTAMINATING RADIOACTIVELY CONTAMINATED IRON AND / OR STEEL SCRAP |
Family Cites Families (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2479540A1 (en) * | 1980-03-27 | 1981-10-02 | Gagneraud Pere Fils Entr | PROCESS FOR PROCESSING MAGNESIUM ELEMENTS, MADE RADIOACTIVE |
| DE3204204C2 (en) * | 1982-02-08 | 1986-05-07 | Kraftwerk Union AG, 4330 Mülheim | Procedure for conditioning radioactive waste |
| 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 |
| USH1013H (en) * | 1989-08-11 | 1992-01-07 | W. R. Grace & Co.-Conn. | Process for the immobilization and volume reduction of low level radioactive wastes from thorium and uranium processing |
| 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. |
| GB2272566B (en) * | 1992-11-17 | 1996-01-24 | Clyde Shaw Ltd | Decontamination method |
-
1994
- 1994-08-01 DE DE4427179A patent/DE4427179A1/en not_active Withdrawn
-
1995
- 1995-07-21 JP JP50608496A patent/JP3471023B2/en not_active Expired - Fee Related
- 1995-07-21 DE DE59508743T patent/DE59508743D1/en not_active Expired - Lifetime
- 1995-07-21 RU RU97103135/06A patent/RU2153719C2/en not_active IP Right Cessation
- 1995-07-21 AU AU29754/95A patent/AU2975495A/en not_active Abandoned
- 1995-07-21 CZ CZ199774A patent/CZ291275B6/en not_active IP Right Cessation
- 1995-07-21 EP EP95925717A patent/EP0774155B1/en not_active Expired - Lifetime
- 1995-07-21 WO PCT/DE1995/000964 patent/WO1996004663A1/en active IP Right Grant
- 1995-07-21 CA CA002196438A patent/CA2196438C/en not_active Expired - Fee Related
- 1995-07-21 ES ES95925717T patent/ES2151074T3/en not_active Expired - Lifetime
- 1995-07-21 UA UA97010294A patent/UA39139C2/en unknown
-
1997
- 1997-02-03 US US08/794,567 patent/US5732366A/en not_active Expired - Lifetime
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE3318377A1 (en) * | 1983-05-20 | 1984-11-22 | Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover | METHOD FOR DECONTAMINATING RADIOACTIVELY CONTAMINATED IRON AND / OR STEEL SCRAP |
Non-Patent Citations (1)
| Title |
|---|
| M.R. CHAKRABARTY: "Formation and Properties of Uranium Glasses", CERAMIC BULLETIN, vol. 48, no. 11, - 1969, pages 1076 - 1078 * |
Also Published As
| Publication number | Publication date |
|---|---|
| JP3471023B2 (en) | 2003-11-25 |
| ES2151074T3 (en) | 2000-12-16 |
| JPH10503591A (en) | 1998-03-31 |
| DE59508743D1 (en) | 2000-10-26 |
| CZ291275B6 (en) | 2003-01-15 |
| UA39139C2 (en) | 2001-06-15 |
| CA2196438A1 (en) | 1996-02-15 |
| RU2153719C2 (en) | 2000-07-27 |
| CA2196438C (en) | 2001-12-18 |
| CZ7497A3 (en) | 1997-05-14 |
| DE4427179A1 (en) | 1996-02-08 |
| WO1996004663A1 (en) | 1996-02-15 |
| US5732366A (en) | 1998-03-24 |
| EP0774155A1 (en) | 1997-05-21 |
| AU2975495A (en) | 1996-03-04 |
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