US3563890A - Process and material for extracting dissolved radioactive ions from liquids - Google Patents

Process and material for extracting dissolved radioactive ions from liquids Download PDF

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Publication number
US3563890A
US3563890A US651977A US3563890DA US3563890A US 3563890 A US3563890 A US 3563890A US 651977 A US651977 A US 651977A US 3563890D A US3563890D A US 3563890DA US 3563890 A US3563890 A US 3563890A
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US
United States
Prior art keywords
ions
liquids
radioactive
support
salts
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
US651977A
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English (en)
Inventor
Horst Willi Perl
Walter Fritz Rittner
Oskar Max Glemser
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.)
Sartorius Membranfilter GmbH
Original Assignee
Sartorius Membranfilter 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
Application filed by Sartorius Membranfilter GmbH filed Critical Sartorius Membranfilter GmbH
Application granted granted Critical
Publication of US3563890A publication Critical patent/US3563890A/en
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
    • G21F9/04Treating liquids
    • G21F9/06Processing
    • G21F9/10Processing by flocculation
    • 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
    • G21F9/04Treating liquids
    • G21F9/06Processing
    • G21F9/12Processing by absorption; by adsorption; by ion-exchange

Definitions

  • Microcrystalline, difficultly soluble salts which are isotopic with radioactive ions, are formed by precipitation on the surface of a support in an agitated liquid suspension of the support.
  • a liquid in which said radioactive ions are dissolved is passed through a column and contacted in said column with said salts bonded to the surface of the support. This results in an isotopic exchange between said salts and ions.
  • radioactive sewage can be purified by an ion exchange.
  • the ions of the crystal lattice of a precipitate are in a state of thermodynamic equilibrium with the isotopic ions which are present in a solution (liquid phase) in contact with the precipitate (solid phase).
  • a solution liquid phase
  • solid phase precipitate
  • Ions which were originally in solution occupy sites in the lattice of the solid phase and ions of the lattice are dissolved.
  • the contact times are of an order of seconds.
  • the radioactive solution is sucked through a thin layer of a difiicultly soluble salt which has just been precipitated.
  • the process according to the invention enables a rapid and complete exchange of isotopes and an ultimate reduction of the radioactive matter to a very small volume.
  • the following significant aspects are considered:
  • Difi icultly soluble salts of various systems can be prepared in microcrystalline form and fixed in a fine three-dimensional distribution (impregnation).
  • the wadding which is impregnated with the difiicultly soluble salts can be stored and does not lose its exchange capacity and may be used without need for preceding chemical operations such as precipitation or the like.
  • the impregnated wadding has a high exchange capacity so that it can be used in a column process for decontaminating large amounts of liquid.
  • EXAMPLE 1 The precipitation with equirnolar amounts results in a formation of approximately equivalent crystals, which are free of a surplus of cations or anions at their surface. This prevents the formation of a double electrical layer at the crystal-soultion phase boundary; such double electrical layer could result in undesired secondary effects.
  • EXAMPLE 2 The wadding is impregnated as in Example 1 but YCl .6H 0 and Na HPO are used instead of Sr(NO EXAMPLE 3
  • the wadding is impregnated as in Example 1 but Sr(NO and YCl .6H O are added at the same time and are precipitated simultaneously with a solution of Na SO and Na HPO
  • EXAMPLE 4 The wadding is impregnated as in Example 1 but AgNO and an NaI solution are used.
  • EXAMPLE 5-DECONTAMINATION 0.5 gram of a cellulose wadding impregnated according to Example 3 was suspended in H 0 and introduced in a column 30 centimeters long and 2.5 centimeters in diameter. The cellulose column had a height of 5 centimeters. A cock and a superimposed frit slab were provided at the lower end of the column. In other experiments, the frit plate in the column was replaced by glass wool so that a high flow rate was obtained.
  • An Sr-90 stock solution which contained 23 milligrams Sr(NO 100 milliters as a carrier, 0.5 milliliter was pipetted from said stock solution and filled up to 10 milliliters. The activity was measured in a liquid counting tube and amounted to 14678 pulses per 30 seconds as an average of 10 measurements. These 10 milliliters were diluted to 250 milliliters and the diluted solution was passed through the prepared column at a flow rate of about 200 milliliters per minute. Various samples of 10 milliliters each were taken from the effluent and measured. It was found that the activity of the total volume was about 40 pulses per 30 seconds, which is less than 0.3% of the original activity.
  • a process of extracting dissolved radioactive ions from a liquid which comprises passing said liquid through a column and contacting said liquid in said column with microcrystalline, ditficultly soluble salts, which are iso topic with the dissolved radioactive ions and bonded to the surface of a support, to effect an isotopic exchange between said difiicultly soluble salts and said dissolved radioactive ions, said support consists of a loose, bulky material, and said salts being dispersed Within said material.
  • said support consists of a substance selected from the class consisting of cellulose acetate and cellulose nitrate.

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Solid-Sorbent Or Filter-Aiding Compositions (AREA)
  • Measurement Of Radiation (AREA)
US651977A 1966-07-11 1967-07-10 Process and material for extracting dissolved radioactive ions from liquids Expired - Lifetime US3563890A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DES0104735 1966-07-11

Publications (1)

Publication Number Publication Date
US3563890A true US3563890A (en) 1971-02-16

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ID=7526060

Family Applications (1)

Application Number Title Priority Date Filing Date
US651977A Expired - Lifetime US3563890A (en) 1966-07-11 1967-07-10 Process and material for extracting dissolved radioactive ions from liquids

Country Status (4)

Country Link
US (1) US3563890A (de)
DE (1) DE1564656A1 (de)
FR (1) FR1583660A (de)
GB (1) GB1146794A (de)

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4431609A (en) * 1983-01-27 1984-02-14 The United States Of America As Represented By The United States Department Of Energy Removal of radium from acidic solutions containing same by adsorption on coal fly ash
DE3513943A1 (de) * 1985-04-18 1986-10-23 Dornier System Gmbh, 7990 Friedrichshafen Verfahren zur verbesserung der abtrennwirkung beim abtrennen radioaktiver isotope in elementarer oder chemisch gebundener form aus fluessigkeiten und gasen
WO2002021538A2 (de) * 2000-09-07 2002-03-14 Atc Dr. Mann Verfahren zur volumenreduzierenden entsorgung von zu lagernden radioaktiv belasteten ionenaustauschern
US20040262225A1 (en) * 2003-04-04 2004-12-30 New Mexico State University Technology Transfer Corporation Treatment of arsenic-contaminated water using akaganeite adsorption

Families Citing this family (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2904627C2 (de) * 1979-02-07 1984-04-12 Alkem Gmbh, 6450 Hanau Verfahren zum Aufbereiten von Abfällen
JPS55106399A (en) * 1978-12-22 1980-08-15 Alkem Gmbh Radioactive waste processing method
GB8625657D0 (en) * 1986-10-27 1986-11-26 British Nuclear Fuels Plc Ion exchange material
DE3740420A1 (de) * 1987-11-28 1989-06-08 Basf Ag Mehrschichtiges elektrophotographisches aufzeichnungsmaterial

Cited By (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4431609A (en) * 1983-01-27 1984-02-14 The United States Of America As Represented By The United States Department Of Energy Removal of radium from acidic solutions containing same by adsorption on coal fly ash
DE3513943A1 (de) * 1985-04-18 1986-10-23 Dornier System Gmbh, 7990 Friedrichshafen Verfahren zur verbesserung der abtrennwirkung beim abtrennen radioaktiver isotope in elementarer oder chemisch gebundener form aus fluessigkeiten und gasen
WO2002021538A2 (de) * 2000-09-07 2002-03-14 Atc Dr. Mann Verfahren zur volumenreduzierenden entsorgung von zu lagernden radioaktiv belasteten ionenaustauschern
WO2002021538A3 (de) * 2000-09-07 2002-11-07 Atc Dr Mann Verfahren zur volumenreduzierenden entsorgung von zu lagernden radioaktiv belasteten ionenaustauschern
US20040262225A1 (en) * 2003-04-04 2004-12-30 New Mexico State University Technology Transfer Corporation Treatment of arsenic-contaminated water using akaganeite adsorption
US7314569B2 (en) * 2003-04-04 2008-01-01 Arrowhead Center, Inc. Treatment of arsenic-contaminated water using akaganeite adsorption

Also Published As

Publication number Publication date
GB1146794A (en) 1969-03-26
FR1583660A (de) 1969-11-28
DE1564656A1 (de) 1970-02-12

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