DE50110833D1 - METHOD FOR VOLUME REDUCING DISPOSAL OF RADIOACTIVELY LOADED ION EXCHANGERS - Google Patents

METHOD FOR VOLUME REDUCING DISPOSAL OF RADIOACTIVELY LOADED ION EXCHANGERS

Info

Publication number
DE50110833D1
DE50110833D1 DE50110833T DE50110833T DE50110833D1 DE 50110833 D1 DE50110833 D1 DE 50110833D1 DE 50110833 T DE50110833 T DE 50110833T DE 50110833 T DE50110833 T DE 50110833T DE 50110833 D1 DE50110833 D1 DE 50110833D1
Authority
DE
Germany
Prior art keywords
ion exchangers
volume reducing
radioactively
loaded ion
reducing disposal
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
DE50110833T
Other languages
German (de)
Inventor
Andreas Wolf
Guenther Mann
Manfred Kuehn
Herwig Brunner
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.)
Fraunhofer Gesellschaft zur Forderung der Angewandten Forschung eV
ATC Dr Mann eK
Original Assignee
Fraunhofer Gesellschaft zur Forderung der Angewandten Forschung eV
ATC Dr Mann eK
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 Fraunhofer Gesellschaft zur Forderung der Angewandten Forschung eV, ATC Dr Mann eK filed Critical Fraunhofer Gesellschaft zur Forderung der Angewandten Forschung eV
Priority to DE50110833T priority Critical patent/DE50110833D1/en
Application granted granted Critical
Publication of DE50110833D1 publication Critical patent/DE50110833D1/en
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

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
    • G21F9/32—Processing by incineration
    • 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
    • G21F9/04—Treating liquids
    • G21F9/06—Processing
    • G21F9/12—Processing by absorption; by adsorption; by ion-exchange
    • 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
    • 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
    • G21F9/307—Processing by fixation in stable solid media in polymeric matrix, e.g. resins, tars

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Environmental & Geological Engineering (AREA)
  • Chemical & Material Sciences (AREA)
  • Inorganic Chemistry (AREA)
  • Processing Of Solid Wastes (AREA)
  • Solid-Sorbent Or Filter-Aiding Compositions (AREA)
  • Electrical Discharge Machining, Electrochemical Machining, And Combined Machining (AREA)
  • Treatment Of Water By Ion Exchange (AREA)

Abstract

The invention relates to a method for reducing the volume of radioactively charged ion exchangers to be stored. The inventive method enables radioactively charged ion exchangers, which are especially used in the nuclear domain as adsorber materials, to be disposed of. The radioactive metals and/or radionuclides are eluted from the ion exchangers, the eluate is decontaminated by means of biosorbents, the biosorbents are burned with the combined, radioactive metals and/or radionuclides, and the solid residue of combustion is enclosed in glass powder, cement or bitumen.
DE50110833T 2000-09-07 2001-09-07 METHOD FOR VOLUME REDUCING DISPOSAL OF RADIOACTIVELY LOADED ION EXCHANGERS Expired - Lifetime DE50110833D1 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
DE50110833T DE50110833D1 (en) 2000-09-07 2001-09-07 METHOD FOR VOLUME REDUCING DISPOSAL OF RADIOACTIVELY LOADED ION EXCHANGERS

Applications Claiming Priority (3)

Application Number Priority Date Filing Date Title
DE10045788A DE10045788A1 (en) 2000-09-07 2000-09-07 Process for reducing the volume of radioactive waste
DE50110833T DE50110833D1 (en) 2000-09-07 2001-09-07 METHOD FOR VOLUME REDUCING DISPOSAL OF RADIOACTIVELY LOADED ION EXCHANGERS
PCT/EP2001/010404 WO2002021538A2 (en) 2000-09-07 2001-09-07 Method for reducing the volume of radioactively charged ion exchangers to be stored

Publications (1)

Publication Number Publication Date
DE50110833D1 true DE50110833D1 (en) 2006-10-05

Family

ID=7656401

Family Applications (2)

Application Number Title Priority Date Filing Date
DE10045788A Withdrawn DE10045788A1 (en) 2000-09-07 2000-09-07 Process for reducing the volume of radioactive waste
DE50110833T Expired - Lifetime DE50110833D1 (en) 2000-09-07 2001-09-07 METHOD FOR VOLUME REDUCING DISPOSAL OF RADIOACTIVELY LOADED ION EXCHANGERS

Family Applications Before (1)

Application Number Title Priority Date Filing Date
DE10045788A Withdrawn DE10045788A1 (en) 2000-09-07 2000-09-07 Process for reducing the volume of radioactive waste

Country Status (5)

Country Link
EP (1) EP1346373B1 (en)
AT (1) ATE337603T1 (en)
AU (1) AU2002212220A1 (en)
DE (2) DE10045788A1 (en)
WO (1) WO2002021538A2 (en)

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
UA78704C2 (en) * 2003-12-22 2007-04-25 Oleksandr Oleksandro Kapitonov Method for cleaning liquid radioactive waste and wastewater
FR2943167B1 (en) * 2009-03-11 2011-03-25 Electricite De France TREATMENT OF CARBON RADIOACTIVE WASTE.
FR2956517B1 (en) * 2010-02-17 2012-03-09 Commissariat Energie Atomique PROCESS FOR TREATMENT BEFORE CALCINATION OF A NITRIC AQUEOUS SOLUTION COMPRISING AT LEAST ONE RADIONUCLEID AND POSSIBLY RUTHENIUM

Family Cites Families (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1564656A1 (en) * 1966-07-11 1970-02-12 Sartorius Membranfilter Gmbh Process for the decontamination of fluids containing radioactive ions
FR2068158A5 (en) * 1969-11-28 1971-08-20 Commissariat Energie Atomique Strontium-90 removal from irradiated fuel effluent - using carboxylic acid cation exchange resin
US4120933A (en) * 1977-09-27 1978-10-17 The United States Of America As Represented By The Unites States Department Of Energy Decontamination of plutonium from water with chitin
JPS6113195A (en) * 1984-06-28 1986-01-21 住友化学工業株式会社 Method of treating radioactive waste water
US4800024A (en) * 1986-04-07 1989-01-24 Iso-Clear Systems Corporation Removal of heavy metals and heavy metal radioactive isotopes from liquids
DE4117234A1 (en) * 1991-05-27 1992-12-03 Winfried Prof Dr Ing Hartmeier Compsn. for heavy metal bio:sorption - comprises an alginate gel insoluble in water
DE4138544A1 (en) * 1991-11-23 1993-05-27 Winfried Prof Dr Ing Hartmeier Agent for bio-sorption of heavy metals - comprising water insol. alginate gel with high content of dry matter for reducing heavy metals content of water to below limits for drinking water
JP2726375B2 (en) * 1993-08-13 1998-03-11 動力炉・核燃料開発事業団 Method for separating and recovering Pu and Np from nitric acid solution containing Pu and Np
JPH0868893A (en) * 1994-08-29 1996-03-12 Sumitomo Metal Mining Co Ltd Processing method for waste liquid including various radioactive materials and heavy metal elements
DE19718452C2 (en) * 1997-04-30 2001-09-13 Mann Guenther Biosorbents for metal ions and process for their manufacture
DE19844171A1 (en) * 1998-09-25 2000-03-30 Koeckritz Tim Biosorption process for removal of metals from solution, uses the consumption of citric acid by growing fungi to raise the pH to cause biosorption of metals into the fungal biomass

Also Published As

Publication number Publication date
DE10045788A1 (en) 2002-04-04
AU2002212220A1 (en) 2002-03-22
EP1346373B1 (en) 2006-08-23
WO2002021538A2 (en) 2002-03-14
EP1346373A2 (en) 2003-09-24
WO2002021538A3 (en) 2002-11-07
ATE337603T1 (en) 2006-09-15

Similar Documents

Publication Publication Date Title
Stefanovsky et al. Chemical-technological and mineralogical-geochemical aspects of the radioactive waste management
Luhar et al. Solidification/stabilization technology for radioactive wastes using cement: An appraisal
DE50110833D1 (en) METHOD FOR VOLUME REDUCING DISPOSAL OF RADIOACTIVELY LOADED ION EXCHANGERS
DE60133392D1 (en) PROCESS FOR IMMOBILIZING RADIOACTIVE AND HARMFUL WASTE
Falciglia et al. Performance study and influence of radiation emission energy and soil contamination level on γ-radiation shielding of stabilised/solidified radionuclide-polluted soils
Abdel Rahman et al. Leaching tests and modelling of cementitious wasteforms corrosion
Bennett et al. Review of waste immobilisation matrices
Josephson Immobilization and leachability of hazardous wastes
Kim et al. Development of a practical decontamination procedure for uranium-contaminated concrete waste
Szecsody et al. Remediation of technetium in vadose zone sediments using ammonia and hydrogen sulfide gases
Palmer Radioactive waste management
Marra et al. Radioactive waste management
Hommel Using Correlations to Cs-137 to Reduce Uncertainty in SRS Tank Farm Tc-99 and I-129 Inventories-19266
Brown et al. Solid Secondary Waste Form Testing Activities for the Integrated Disposal Facility Performance Assessment Support-17567
Welch et al. Immobilization of transuranic sludge in glass-ceramic materials
Dyer Geochemical Model of Eh and pH Transitions in Pore Fluids during Saltstone and SDU Concrete Aging: Saltstone Disposal Facility PA Revision
Seaman et al. Contaminant Leaching From Intact Saltstone Monoliths–17517
Tokoyoda et al. Decontamination of Radio-Cs in Soil and Incineration Fly Ash to the Clearance Level by Pyrolysis-18247
Simner et al. Selection and Validation of Alternate Slag Sources for Saltstone Production-16145
Swanberg et al. Waste Form Development for Solidification of Liquid Secondary Wastes to Support Hanford Direct Feed Low Activity Waste Vitrification-17484
Chang Co-disposal of low-level radioactive waste within sanitary landfills.
Fitzpatrick et al. In situ vitrification: a potential remedial action technique for hazardous waste
Bostick et al. Blast furnace slag-cement grout blends for the immobilization of technetium-containing wastes
Vijayan et al. Technology perspectives on the management of spent-resin wastes generated from nuclear power reactor operations
Shade et al. In situ vitrification of buried waste sites

Legal Events

Date Code Title Description
8364 No opposition during term of opposition