EP0032686B1 - Verfahren zum Endkonditionieren fester radioaktiver, insbesondere Kernbrennstoff enthaltender, organischer Abfälle - Google Patents

Verfahren zum Endkonditionieren fester radioaktiver, insbesondere Kernbrennstoff enthaltender, organischer Abfälle Download PDF

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Publication number
EP0032686B1
EP0032686B1 EP81100115A EP81100115A EP0032686B1 EP 0032686 B1 EP0032686 B1 EP 0032686B1 EP 81100115 A EP81100115 A EP 81100115A EP 81100115 A EP81100115 A EP 81100115A EP 0032686 B1 EP0032686 B1 EP 0032686B1
Authority
EP
European Patent Office
Prior art keywords
waste
cement
mixture
water
particles
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
EP81100115A
Other languages
German (de)
English (en)
French (fr)
Other versions
EP0032686A2 (de
EP0032686A3 (en
Inventor
Friedrich-Wilhelm Dr. Ledebrink
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.)
Alkem GmbH
Original Assignee
Alkem GmbH
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
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First worldwide family litigation filed litigation Critical https://patents.darts-ip.com/?family=6092322&utm_source=google_patent&utm_medium=platform_link&utm_campaign=public_patent_search&patent=EP0032686(B1) "Global patent litigation dataset” by Darts-ip is licensed under a Creative Commons Attribution 4.0 International License.
Application filed by Alkem GmbH filed Critical Alkem GmbH
Publication of EP0032686A2 publication Critical patent/EP0032686A2/de
Publication of EP0032686A3 publication Critical patent/EP0032686A3/de
Application granted granted Critical
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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
    • G21F9/04—Treating liquids
    • G21F9/06—Processing
    • G21F9/16—Processing by fixation in stable solid media
    • G21F9/162—Processing by fixation in stable solid media in an inorganic matrix, e.g. clays, zeolites
    • G21F9/165—Cement or cement-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
    • G21F9/301—Processing by fixation in stable solid media
    • G21F9/302—Processing by fixation in stable solid media in an inorganic matrix
    • G21F9/304—Cement or cement-like matrix

Definitions

  • the invention relates to a process for the final conditioning of solid, voluminous, largely dimensionally stable radioactive, in particular nuclear fuel containing, organic waste such as rubber gloves, foils, bottles and tubes made of plastic, wipes made of cellulose or synthetics, components made of wood or natural fibers, with the formation of a curable mixture from the shredded waste, an inorganic binder and water.
  • organic waste such as rubber gloves, foils, bottles and tubes made of plastic, wipes made of cellulose or synthetics, components made of wood or natural fibers
  • organic waste produced during the production of nuclear reactor fuel elements can include long-lasting radiotoxic nuclides, such as e.g. B. Plutonium 239 with a half-life of 24 390 years.
  • radiotoxic nuclides such as e.g. B. Plutonium 239 with a half-life of 24 390 years.
  • waste container e.g. B. a 200-liter barrel
  • wastes can originally be water-containing wastes, ashes, powders and granules (ion exchangers), which result in a solid end product after hardening by homogeneous mixing with a cement paste.
  • the removal of solid, voluminous, organic, nuclear fuel-containing waste from fuel element factories by cementing has so far not been carried out because the mixing of the raw waste in cement meant an unsolved problem.
  • the raw waste is a mixture of voluminous largely organic dimensionally stable natural and plastics, such as. B. rubber gloves, plastic films, bottles, tubes, wipes made of cellulose or synthetics, components made of wood, natural fibers and. a.
  • they are composed of 70% by weight of polyvinyl chloride, 15% by weight of neoprene, 10% by weight of cellulose, the rest of various other plastics.
  • These materials are usually mixed with inorganic waste, e.g. B. metal, glass and ceramics.
  • the invention is therefore based on the object of simply and safely introducing solid and voluminous organic wastes of this type, which are difficult to handle, into cement blocks which have sufficient strength, do not form cracks over time and bring about a reduction in the final waste volume.
  • a method of the type mentioned at the outset is characterized in that the waste is comminuted to such small, free-flowing particles that the adhesive forces acting on the waste particles in the mixture of cement as an inorganic binder and water outweigh the buoyancy forces that the waste particles be mixed homogeneously into the cement-water mixture and that finally the mixture of cement, water and the waste particles is cured to form a concrete block that can be disposed of.
  • inorganic waste preferably made of metal, glass and ceramic, is advantageously introduced into the cement-water mixture without voids.
  • Raw waste can be freed of inorganic waste by sorting and the remaining voluminous and dimensionally stable organic waste can be ground in a shredding plant, e.g. B. on grain sizes less than 5 mm.
  • the ground waste which can be mixed very well with the cement paste, is stirred in homogeneously and then poured into a waste drum. Then the pore volume in the cement block is reduced by shaking with vacuum support and at the same time the pressure resistance is increased.
  • this waste After curing, this waste is dimensionally and leach-resistant and suitable for final storage.
  • the waste After curing, the waste is dimensionally stable and leachable and suitable for final storage.
  • the raw waste originating from the glove boxes of a production plant for Pu-containing fuel elements with an average Pu content of about 0.1 g / dm 3 is first separated by sorting non-crushable inorganic admixtures (scrap, glass, etc.) in preparation for a subsequent comminution .
  • sorting non-crushable inorganic admixtures scrap, glass, etc.
  • the raw waste is crushed to an average grain size of about 0.2 mm.
  • the raw waste is compacted from approx. 0.2 kgjdm 3 to 0.45 kg / dm 3 , its Pu content increases by a factor of 2.5 to 0.25 g / dm 3.
  • the mean absolute density of the plastics in the raw waste is around 1.28kg / dm3 due to the high PVC content.
  • the barrel Before curing, the barrel is placed on a vibrating table and the cement-waste mixture is compacted largely without pores.
  • the concrete has hardened after 24 hours.
  • the characteristic data of this final waste container are:
  • the organic, pre-sorted raw waste is crushed to a grain size of approx. 2 mm in a granulator.
  • 40 kg of the waste (89 dm 3 ) with 10 g Pu, corresponding to 3.4 Ci ⁇ -activity, are mixed with 90 kg water and 200 kg cement in an intensive mixer within an alpha-tight concrete cell.
  • the cell floor there is a tubular opening with a diameter of approx. 50 cm, which is enclosed in an alpha-tight manner from the outside by a very long »endless « hose, the lower end of which is welded.
  • a 200 liter drum is placed under the tubular outlet opening of the cell and the endless hose, which resembles a sack, is inserted into the drum in the manner of a drum inner lining.
  • approx. 30 kg of metallic or ceramic scrap parts are placed in the lined barrel before the finished cement mixture is poured in.
  • the plastic hose is welded and the filled drum is placed on a vibrating table to compress the concrete.
  • the barrel is closed and placed in a 400 liter barrel and the space is poured with concrete. After the concrete has hardened, the final container is ready for final storage.
  • the characteristic data of the final container are:
  • slightly radioactive water for the preparation of the cement paste is also particularly advantageous, since it has also been made ready for final storage in this way, without it having to be subjected to any special cleaning processes, etc.

Landscapes

  • Chemical & Material Sciences (AREA)
  • Inorganic Chemistry (AREA)
  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Processing Of Solid Wastes (AREA)
EP81100115A 1980-01-17 1981-01-09 Verfahren zum Endkonditionieren fester radioaktiver, insbesondere Kernbrennstoff enthaltender, organischer Abfälle Expired EP0032686B1 (de)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE3001629 1980-01-17
DE19803001629 DE3001629A1 (de) 1980-01-17 1980-01-17 Verfahren zur endkonditionierung fester radioaktiverabfaelle

Publications (3)

Publication Number Publication Date
EP0032686A2 EP0032686A2 (de) 1981-07-29
EP0032686A3 EP0032686A3 (en) 1981-09-09
EP0032686B1 true EP0032686B1 (de) 1985-01-02

Family

ID=6092322

Family Applications (1)

Application Number Title Priority Date Filing Date
EP81100115A Expired EP0032686B1 (de) 1980-01-17 1981-01-09 Verfahren zum Endkonditionieren fester radioaktiver, insbesondere Kernbrennstoff enthaltender, organischer Abfälle

Country Status (3)

Country Link
EP (1) EP0032686B1 (enrdf_load_stackoverflow)
JP (1) JPS56168200A (enrdf_load_stackoverflow)
DE (2) DE3001629A1 (enrdf_load_stackoverflow)

Families Citing this family (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3143078C2 (de) * 1981-10-30 1985-03-21 Neidhart, Bernd, Dr.-Ing., 4600 Dortmund Gerät zur Aufbereitung von radioaktive Flüssigkeiten enthaltenden Zählfläschchen aus Kunststoff
DE3343422A1 (de) * 1983-12-01 1985-06-20 Kernforschungsanlage Jülich GmbH, 5170 Jülich Verfahren zum konditionieren kontaminierten abfalls durch zementieren
JPS6288999A (ja) * 1985-10-15 1987-04-23 日揮株式会社 放射性不燃性固体廃棄物の固化処理法
JPH0641999B2 (ja) * 1985-11-21 1994-06-01 日揮株式会社 放射性廃棄物焼却灰の固化処理法
JPS6383697A (ja) * 1986-09-29 1988-04-14 日揮株式会社 放射性溶融水冷スラグの固化処理法
JPH0718262B2 (ja) * 1986-11-08 1995-03-01 清水建設株式会社 構造物の解体工法及びその装置
DE3713446A1 (de) * 1987-04-22 1988-11-03 Transnuklear Gmbh Verfahren zur konditionierung von festen, radioaktiv kontaminierten, gaer- bzw. faulfaehigen abfaellen
DE10148146B4 (de) * 2001-09-28 2009-08-27 Forschungszentrum Jülich GmbH Verfahren zur Entsorgung eines mit mindestens einem Radiotoxikum kontaminierten Gegenstandes aus Reaktorgraphit und/oder Kohlestein

Family Cites Families (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3012385A (en) * 1959-04-15 1961-12-12 Terry D Hufft Means for disposal of atomic waste
DE2228938A1 (de) * 1972-06-14 1974-01-03 Nukem Gmbh Verfahren und einrichtung zur verfestigung von festen und fluessigen radioaktiven abfallstoffen, insbesondere von nasschlaemmen
DE2356253C2 (de) * 1973-11-10 1982-06-09 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe Verfahren zur Verfestigung einer organischen, radioaktive Stoffe enthaltenden Abfallflüssigkeit
DE2421142A1 (de) * 1974-05-02 1975-11-13 Elba Werk Maschinen Gmbh & Co Verfahren und vorrichtung zur beseitigung radioaktiver abfaelle
JPS5133124A (en) * 1974-09-13 1976-03-22 Nyuuze Kk Pii aaru shii koho
FR2290745A1 (fr) * 1974-11-05 1976-06-04 Asea Atom Ab Procede pour enrober dans le ciment des matieres organiques echangeuses d'ions, granulees ou usees
AT338387B (de) * 1975-06-26 1977-08-25 Oesterr Studien Atomenergie Verfahren zum einbetten von radioaktiven und/oder toxischen abfallen
DE2648263A1 (de) * 1976-10-25 1978-09-28 Kraftwerk Union Ag Verfahren zum einbinden wasserhaltiger radioaktiver abfaelle
DE2717656A1 (de) * 1977-04-21 1978-10-26 Nukem Gmbh Verfahren zur herstellung auslaugfester und salzlaugebestaendiger bloecke aus zement und radioaktiven abfaellen
DE2726087C2 (de) * 1977-06-10 1978-12-21 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe Verfahren zur endlagerreifen, umweltfreundlichen Verfestigung von" und mittelradioaktiven und/oder Actiniden enthaltenden, wäßrigen Abfallkonzentraten oder von in Wasser aufgeschlämmten, feinkörnigen festen Abfällen

Also Published As

Publication number Publication date
DE3167986D1 (en) 1985-02-14
EP0032686A2 (de) 1981-07-29
DE3001629A1 (de) 1981-09-24
EP0032686A3 (en) 1981-09-09
JPS56168200A (en) 1981-12-24
JPH0151800B2 (enrdf_load_stackoverflow) 1989-11-06

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