EP0774155B1 - Verfahren zur verwertung von metallteilen, die durch uran radioaktiv kontaminiert sind - Google Patents
Verfahren zur verwertung von metallteilen, die durch uran radioaktiv kontaminiert sind 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
Links
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.
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)
Description
Claims (5)
- 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,
dadurch gekennzeichnet, 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. - Verfahren nach Anspruch 1,
dadurch gekennzeichnet, daß das Uranglas ein bei der Schmelztemperatur des Metalls der Metallteile dünnflüssiges Glas ist. - Verfahren nach einem der Ansprüche 1 bis 2,
dadurch gekennzeichnet, daß das Uranglas ein Glas des Typs Alkalioxid/SiO2/UO2 ist. - Verfahren nach einem der Ansprüche 1 bis 3,
dadurch gekennzeichnet, daß der U 235-Isotopenanteil im Uran des Uranglases unter 0,7 % beträgt. - Verfahren nach einem der Ansprüche 1 bis 4,
dadurch gekennzeichnet, daß der Urananteil im Uranglas kleiner als 50 % ist.
Applications Claiming Priority (3)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE4427179A DE4427179A1 (de) | 1994-08-01 | 1994-08-01 | Verfahren zur Verwertung von Metallteilen, die durch Uran radioaktiv kontaminiert sind |
DE4427179 | 1994-08-01 | ||
PCT/DE1995/000964 WO1996004663A1 (de) | 1994-08-01 | 1995-07-21 | Verfahren zur verwertung von metallteilen, die durch uran radioaktiv kontaminiert sind |
Publications (2)
Publication Number | Publication Date |
---|---|
EP0774155A1 EP0774155A1 (de) | 1997-05-21 |
EP0774155B1 true EP0774155B1 (de) | 2000-09-20 |
Family
ID=6524634
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
EP95925717A Expired - Lifetime EP0774155B1 (de) | 1994-08-01 | 1995-07-21 | Verfahren zur verwertung von metallteilen, die durch uran radioaktiv kontaminiert sind |
Country Status (11)
Country | Link |
---|---|
US (1) | US5732366A (de) |
EP (1) | EP0774155B1 (de) |
JP (1) | JP3471023B2 (de) |
AU (1) | AU2975495A (de) |
CA (1) | CA2196438C (de) |
CZ (1) | CZ291275B6 (de) |
DE (2) | DE4427179A1 (de) |
ES (1) | ES2151074T3 (de) |
RU (1) | RU2153719C2 (de) |
UA (1) | UA39139C2 (de) |
WO (1) | WO1996004663A1 (de) |
Families Citing this family (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE19546789A1 (de) * | 1995-12-14 | 1997-06-19 | Siemens Ag | Verfahren zur Verwertung kontaminierter Metallteile |
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 (de) * | 1983-05-20 | 1984-11-22 | Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover | Verfahren zur dekontamination von radioaktiv kontaminiertem eisen- und/oder stahlschrott |
Family Cites Families (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2479540A1 (fr) * | 1980-03-27 | 1981-10-02 | Gagneraud Pere Fils Entr | Procede de traitement d'elements en magnesium, rendus radioactifs |
DE3204204C2 (de) * | 1982-02-08 | 1986-05-07 | Kraftwerk Union AG, 4330 Mülheim | Verfahren zur Konditionierung radioaktiver Abfälle |
JPS6145999A (ja) * | 1984-08-10 | 1986-03-06 | 株式会社日立製作所 | 放射能汚染アルミニウム材の溶融除染方法 |
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 (de) * | 1990-12-06 | 1992-06-11 | Bader Bibiana | Verfahren und einrichtung zum schmelzen einer umweltschaedlichen substanz mit einem chemische umbesetzungen hervorrufenden rohstoffmenge zum serienmaessigen erzeugen umweltunschaedlicher produkte |
GB2272566B (en) * | 1992-11-17 | 1996-01-24 | Clyde Shaw Ltd | Decontamination method |
-
1994
- 1994-08-01 DE DE4427179A patent/DE4427179A1/de not_active Withdrawn
-
1995
- 1995-07-21 CZ CZ199774A patent/CZ291275B6/cs not_active IP Right Cessation
- 1995-07-21 EP EP95925717A patent/EP0774155B1/de not_active Expired - Lifetime
- 1995-07-21 DE DE59508743T patent/DE59508743D1/de not_active Expired - Lifetime
- 1995-07-21 AU AU29754/95A patent/AU2975495A/en not_active Abandoned
- 1995-07-21 UA UA97010294A patent/UA39139C2/uk unknown
- 1995-07-21 JP JP50608496A patent/JP3471023B2/ja not_active Expired - Fee Related
- 1995-07-21 ES ES95925717T patent/ES2151074T3/es not_active Expired - Lifetime
- 1995-07-21 WO PCT/DE1995/000964 patent/WO1996004663A1/de active IP Right Grant
- 1995-07-21 RU RU97103135/06A patent/RU2153719C2/ru not_active IP Right Cessation
- 1995-07-21 CA CA002196438A patent/CA2196438C/en not_active Expired - Fee Related
-
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 (de) * | 1983-05-20 | 1984-11-22 | Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover | Verfahren zur dekontamination von radioaktiv kontaminiertem eisen- und/oder stahlschrott |
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 |
---|---|
EP0774155A1 (de) | 1997-05-21 |
UA39139C2 (uk) | 2001-06-15 |
JPH10503591A (ja) | 1998-03-31 |
CA2196438A1 (en) | 1996-02-15 |
ES2151074T3 (es) | 2000-12-16 |
WO1996004663A1 (de) | 1996-02-15 |
CA2196438C (en) | 2001-12-18 |
US5732366A (en) | 1998-03-24 |
JP3471023B2 (ja) | 2003-11-25 |
DE4427179A1 (de) | 1996-02-08 |
DE59508743D1 (de) | 2000-10-26 |
CZ7497A3 (en) | 1997-05-14 |
CZ291275B6 (cs) | 2003-01-15 |
RU2153719C2 (ru) | 2000-07-27 |
AU2975495A (en) | 1996-03-04 |
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