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GB1446016A - Method for the conditioning of high level radioactive wastes for their safe storage and disposal - Google Patents

Method for the conditioning of high level radioactive wastes for their safe storage and disposal

Info

Publication number
GB1446016A
GB1446016A GB3513973A GB3513973A GB1446016A GB 1446016 A GB1446016 A GB 1446016A GB 3513973 A GB3513973 A GB 3513973A GB 3513973 A GB3513973 A GB 3513973A GB 1446016 A GB1446016 A GB 1446016A
Authority
GB
United Kingdom
Prior art keywords
granules
alloy
oxides
radio
vitreous
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
Application number
GB3513973A
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.)
EUROP POUR LE TRAITEMENT CHIMI
Original Assignee
EUROP POUR LE TRAITEMENT CHIMI
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 EUROP POUR LE TRAITEMENT CHIMI filed Critical EUROP POUR LE TRAITEMENT CHIMI
Priority to GB3513973A priority Critical patent/GB1446016A/en
Publication of GB1446016A publication Critical patent/GB1446016A/en
Expired legal-status Critical Current

Links

Classifications

    • C—CHEMISTRY; METALLURGY
    • C03—GLASS; MINERAL OR SLAG WOOL
    • C03B—MANUFACTURE, SHAPING, OR SUPPLEMENTARY PROCESSES
    • C03B19/00—Other methods of shaping glass
    • C03B19/10—Forming beads
    • C03B19/1005—Forming solid beads
    • C03B19/1055—Forming solid beads by extruding, e.g. dripping molten glass in a gaseous atmosphere
    • C—CHEMISTRY; METALLURGY
    • C03—GLASS; MINERAL OR SLAG WOOL
    • C03B—MANUFACTURE, SHAPING, OR SUPPLEMENTARY PROCESSES
    • C03B19/00—Other methods of shaping glass
    • C03B19/10—Forming beads
    • C03B19/1005—Forming solid beads
    • C03B19/104—Forming solid beads by rolling, e.g. using revolving cylinders, rotating discs, rolls
    • C—CHEMISTRY; METALLURGY
    • C03—GLASS; MINERAL OR SLAG WOOL
    • C03B—MANUFACTURE, SHAPING, OR SUPPLEMENTARY PROCESSES
    • C03B19/00—Other methods of shaping glass
    • C03B19/10—Forming beads
    • C03B19/109—Glass-melting furnaces specially adapted for making beads
    • C—CHEMISTRY; METALLURGY
    • C03—GLASS; MINERAL OR SLAG WOOL
    • C03C—CHEMICAL COMPOSITION OF GLASSES, GLAZES OR VITREOUS ENAMELS; SURFACE TREATMENT OF GLASS; SURFACE TREATMENT OF FIBRES OR FILAMENTS MADE FROM GLASS, MINERALS OR SLAGS; JOINING GLASS TO GLASS OR OTHER MATERIALS
    • C03C3/00—Glass compositions
    • C03C3/04—Glass compositions containing silica
    • C03C3/062—Glass compositions containing silica with less than 40% silica by weight
    • C03C3/07—Glass compositions containing silica with less than 40% silica by weight containing lead
    • C03C3/072—Glass compositions containing silica with less than 40% silica by weight containing lead containing boron
    • 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
    • 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

Landscapes

  • Chemical & Material Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Organic Chemistry (AREA)
  • Materials Engineering (AREA)
  • Manufacturing & Machinery (AREA)
  • High Energy & Nuclear Physics (AREA)
  • General Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Inorganic Chemistry (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • General Chemical & Material Sciences (AREA)
  • Geochemistry & Mineralogy (AREA)
  • Processing Of Solid Wastes (AREA)

Abstract

1446016 Treating radio-active waste; radiation sources SOC EUROPEENNE POUR LE TRAITEMENT CHIMIQUE DES COMBUSTIBLES IRRADIES 22 July 1974 [24 July 1973] 35139/73 Heading G6R High level radio-active waste material in the form of granules is embedded in a matrix consisting of a metal or an alloy. The product is in a form suitable for storage or disposal or may be used as a heat source for distilling sea water. The metal may be Pb, A1, an alloy of Pb with Sb, Sn, Bi, or Zn, or an alloy of Al with Si, Mg, or Cu. The matrix maybe clad with stainless steel, Ti, Pb, Al, or Pb or Al alloys. The granules may be of vitreous material, made for example by heating a mixture of radio-active waste oxides with PbO, SiO 2 , and B 2 O 3 to form a lead borosilicate glass. Reference is made to other material for the granules, i.e. aluminium borosilicates, phosphate glass, ceramics, porcelain, phosphites, sulphates, fluorides, silicates, and oxides. The filling of containers with the granules and molten metal is described with reference to drawings; the container may be placed in a larger container and the intervening space filled with molten metal. Another drawing shows an apparatus for making vitreous beads containing waste oxides, in which the vitreous melt is allowed to drop through holes on to a rotating disc.
GB3513973A 1973-07-24 1973-07-24 Method for the conditioning of high level radioactive wastes for their safe storage and disposal Expired GB1446016A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB3513973A GB1446016A (en) 1973-07-24 1973-07-24 Method for the conditioning of high level radioactive wastes for their safe storage and disposal

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB3513973A GB1446016A (en) 1973-07-24 1973-07-24 Method for the conditioning of high level radioactive wastes for their safe storage and disposal

Publications (1)

Publication Number Publication Date
GB1446016A true GB1446016A (en) 1976-08-11

Family

ID=10374292

Family Applications (1)

Application Number Title Priority Date Filing Date
GB3513973A Expired GB1446016A (en) 1973-07-24 1973-07-24 Method for the conditioning of high level radioactive wastes for their safe storage and disposal

Country Status (1)

Country Link
GB (1) GB1446016A (en)

Cited By (13)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2379888A1 (en) * 1977-02-02 1978-09-01 Gelsenberg Ag PROCESS FOR THE PREPARATION OF SOLID MATERIALS CONTAINING RADIO-ACTIVE PRODUCTS
FR2445594A1 (en) * 1978-12-28 1980-07-25 Kernforschungsz Karlsruhe PROCESS FOR THE PREPARATION OF BODIES CONTAINING HIGHLY RADIOACTIVE WASTE CONSTITUTED BY GLASS PELLETS INCORPORATED IN A METAL MATRIX
DE3006085A1 (en) * 1979-02-27 1980-09-04 Wiederaufarbeitung Von Kernbre METHOD AND DEVICE FOR DOSING MOLTEN MATERIAL
FR2482764A1 (en) * 1980-05-16 1981-11-20 Nukem Gmbh PROCESS FOR THE INCLUSION OF RADIOACTIVE METAL WASTE CONTAINING TRITIUM
US4472298A (en) * 1980-05-16 1984-09-18 Nukem Gmbh Process for embedding radioactive, especially tritium containing waste
US4571307A (en) * 1982-12-23 1986-02-18 Commissariat A L'energie Atomique Process for conditioning radioactive waste
US4770817A (en) * 1982-04-30 1988-09-13 Westinghouse Electric Corp. Encapsulation of solids in alpha-alumina
WO2000079542A1 (en) * 1999-06-17 2000-12-28 Clean Technologies International Corporation Metal alloy storage product and treatment process for radioactive waste
US7034197B2 (en) 1998-06-12 2006-04-25 Clean Technologies International Corporation Metal alloy and metal alloy storage product for storing radioactive materials
US7365237B2 (en) 2002-09-26 2008-04-29 Clean Technologies International Corporation Liquid metal reactor and method for treating materials in a liquid metal reactor
EP3029685A4 (en) * 2013-07-31 2017-03-15 Joint Stock Company "Akme-Engineering" Method for long-term storage of waste nuclear fuel
CN111712886A (en) * 2017-12-08 2020-09-25 阿科姆工程合资(控股)公司 Method for long-term storage of spent fuel and cooled storage tank for its implementation
CN115050502A (en) * 2022-05-31 2022-09-13 武汉理工大学 Glass curing treatment method for lead-bismuth alloy nuclear waste

Cited By (18)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2379888A1 (en) * 1977-02-02 1978-09-01 Gelsenberg Ag PROCESS FOR THE PREPARATION OF SOLID MATERIALS CONTAINING RADIO-ACTIVE PRODUCTS
FR2445594A1 (en) * 1978-12-28 1980-07-25 Kernforschungsz Karlsruhe PROCESS FOR THE PREPARATION OF BODIES CONTAINING HIGHLY RADIOACTIVE WASTE CONSTITUTED BY GLASS PELLETS INCORPORATED IN A METAL MATRIX
DE3006085A1 (en) * 1979-02-27 1980-09-04 Wiederaufarbeitung Von Kernbre METHOD AND DEVICE FOR DOSING MOLTEN MATERIAL
FR2482764A1 (en) * 1980-05-16 1981-11-20 Nukem Gmbh PROCESS FOR THE INCLUSION OF RADIOACTIVE METAL WASTE CONTAINING TRITIUM
US4472298A (en) * 1980-05-16 1984-09-18 Nukem Gmbh Process for embedding radioactive, especially tritium containing waste
US4770817A (en) * 1982-04-30 1988-09-13 Westinghouse Electric Corp. Encapsulation of solids in alpha-alumina
US4571307A (en) * 1982-12-23 1986-02-18 Commissariat A L'energie Atomique Process for conditioning radioactive waste
US7034197B2 (en) 1998-06-12 2006-04-25 Clean Technologies International Corporation Metal alloy and metal alloy storage product for storing radioactive materials
US6355857B1 (en) * 1999-06-17 2002-03-12 Clean Technologies International Corporation Metal alloy treatment process for radioactive waste
EP1222666A1 (en) * 1999-06-17 2002-07-17 Clean Technologies International Corporation Metal alloy storage product and treatment process for radioactive waste
EP1222666A4 (en) * 1999-06-17 2004-10-27 Clean Technologies Int Corp Metal alloy storage product and treatment process for radioactive waste
WO2000079542A1 (en) * 1999-06-17 2000-12-28 Clean Technologies International Corporation Metal alloy storage product and treatment process for radioactive waste
US7365237B2 (en) 2002-09-26 2008-04-29 Clean Technologies International Corporation Liquid metal reactor and method for treating materials in a liquid metal reactor
EP3029685A4 (en) * 2013-07-31 2017-03-15 Joint Stock Company "Akme-Engineering" Method for long-term storage of waste nuclear fuel
CN111712886A (en) * 2017-12-08 2020-09-25 阿科姆工程合资(控股)公司 Method for long-term storage of spent fuel and cooled storage tank for its implementation
CN111712886B (en) * 2017-12-08 2024-03-19 阿科姆工程合资(控股)公司 Method for long-term storage of spent fuel and cooled storage tank for implementation thereof
CN115050502A (en) * 2022-05-31 2022-09-13 武汉理工大学 Glass curing treatment method for lead-bismuth alloy nuclear waste
CN115050502B (en) * 2022-05-31 2024-10-15 武汉理工大学 Glass curing treatment method for lead bismuth alloy nuclear waste

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Legal Events

Date Code Title Description
PS Patent sealed
PCNP Patent ceased through non-payment of renewal fee