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EP0774155B1 - Procede de revalorisation de pieces metalliques contaminees par de l'uranium - Google Patents

Procede de revalorisation de pieces metalliques contaminees par de l'uranium Download PDF

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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
Application number
EP95925717A
Other languages
German (de)
English (en)
Other versions
EP0774155A1 (fr
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
Siemens Corp
Original Assignee
Siemens AG
Siemens Corp
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Siemens AG, Siemens Corp filed Critical Siemens AG
Publication of EP0774155A1 publication Critical patent/EP0774155A1/fr
Application granted granted Critical
Publication of EP0774155B1 publication Critical patent/EP0774155B1/fr
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

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Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28Treating solids
    • G21F9/30Processing
    • G21F9/301Processing by fixation in stable solid media
    • G21F9/302Processing by fixation in stable solid media in an inorganic matrix
    • G21F9/305Glass or glass like matrix
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28Treating solids
    • G21F9/30Processing
    • G21F9/308Processing 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)

Claims (5)

  1. Procédé de valorisation de pièces métalliques qui sont contaminées radioactivement par de l'uranium, les pièces métalliques étant fondues de manière à former une masse fondue et une scorie et de l'uranium appauvri en U 235 étant ajouté aux pièces métalliques et/ou à la masse fondue et/ou aux scories qui ne sont pas encore solidifiées,
       caractérisé en ce qu'il consiste à ajouter l'uranium appauvri en U 235 sous la forme de verre à l'uranium et en ce que le verre à l'uranium a la forme de graviers et/ou de perles et/ou de barreaux et/ou de morceaux.
  2. Procédé suivant la revendication 1,
       caractérisé en ce que le verre à l'uranium est un verre très fluide à la température de fusion du métal des parties métalliques.
  3. Procédé suivant l'une des revendications 1 à 2,
       caractérisé en ce que le verre à l'uranium est un verre du type oxyde de métal alcalin/SiO2/UO2.
  4. Procédé suivant l'une des revendications 1 à 3,
       caractérisé en ce que la proportion d'isotope U 235 dans l'uranium du verre à l'uranium est inférieure à 0,7 %.
  5. Procédé suivant l'une des revendications 1 à 4,
       caractérisé en ce que la proportion d'uranium dans le verre à l'uranium est inférieure à 50 %.
EP95925717A 1994-08-01 1995-07-21 Procede de revalorisation de pieces metalliques contaminees par de l'uranium Expired - Lifetime EP0774155B1 (fr)

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 (fr) 1994-08-01 1995-07-21 Procede de revalorisation de pieces metalliques contaminees par de l'uranium

Publications (2)

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

Family

ID=6524634

Family Applications (1)

Application Number Title Priority Date Filing Date
EP95925717A Expired - Lifetime EP0774155B1 (fr) 1994-08-01 1995-07-21 Procede de revalorisation de pieces metalliques contaminees par de l'uranium

Country Status (11)

Country Link
US (1) US5732366A (fr)
EP (1) EP0774155B1 (fr)
JP (1) JP3471023B2 (fr)
AU (1) AU2975495A (fr)
CA (1) CA2196438C (fr)
CZ (1) CZ291275B6 (fr)
DE (2) DE4427179A1 (fr)
ES (1) ES2151074T3 (fr)
RU (1) RU2153719C2 (fr)
UA (1) UA39139C2 (fr)
WO (1) WO1996004663A1 (fr)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
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)

* Cited by examiner, † Cited by third party
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 (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
ZA786514B (en) * 1978-11-09 1980-07-30 Litovitz T Immobilization of radwastes in glass containers and products formed thereby
FR2479540A1 (fr) * 1980-03-27 1981-10-02 Gagneraud Pere Fils Entr Procede de traitement d'elements en magnesium, rendus radioactifs
US4376070A (en) * 1980-06-25 1983-03-08 Westinghouse Electric Corp. Containment of nuclear waste
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

Patent Citations (1)

* Cited by examiner, † Cited by third party
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)

* Cited by examiner, † Cited by third party
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
CA2196438A1 (fr) 1996-02-15
JPH10503591A (ja) 1998-03-31
US5732366A (en) 1998-03-24
WO1996004663A1 (fr) 1996-02-15
EP0774155A1 (fr) 1997-05-21
ES2151074T3 (es) 2000-12-16
UA39139C2 (uk) 2001-06-15
CZ291275B6 (cs) 2003-01-15
AU2975495A (en) 1996-03-04
CA2196438C (fr) 2001-12-18
DE4427179A1 (de) 1996-02-08
RU2153719C2 (ru) 2000-07-27
DE59508743D1 (de) 2000-10-26
CZ7497A3 (en) 1997-05-14
JP3471023B2 (ja) 2003-11-25

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