US3626191A - Ion exchange vessel having hollow cylindrical ring construction for the transfer of a radioactive substance - Google Patents

Ion exchange vessel having hollow cylindrical ring construction for the transfer of a radioactive substance Download PDF

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Publication number
US3626191A
US3626191A US801093A US3626191DA US3626191A US 3626191 A US3626191 A US 3626191A US 801093 A US801093 A US 801093A US 3626191D A US3626191D A US 3626191DA US 3626191 A US3626191 A US 3626191A
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US
United States
Prior art keywords
column
vessel
hollow cylindrical
pipe
cylindrical ring
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
US801093A
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English (en)
Inventor
Rene Antony Pierlas
Jean Marie Courouble
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.)
Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
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Commissariat a lEnergie Atomique CEA
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 Commissariat a lEnergie Atomique CEA filed Critical Commissariat a lEnergie Atomique CEA
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Publication of US3626191A publication Critical patent/US3626191A/en
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

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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
    • G21F9/12—Processing by absorption; by adsorption; by ion-exchange
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
    • G21G4/00—Radioactive sources
    • G21G4/04—Radioactive sources other than neutron sources
    • G21G4/06—Radioactive sources other than neutron sources characterised by constructional features

Definitions

  • a vessel for the purpose of transferring a radioactive substance which is adsorbed on an ion exchanger in the granular state said vessel being characterized in that it comprises on the one hand a column in the form of a cylindrical ring which is intended to contain an ion exchanger in the granular state and is surrounded by a shield having good ther mal conductivity and on the other hand at least one pipe for the supply of radioactive solution which penetrates into said column and at least one pipe for the discharge of irradiated liquid.
  • the present invention relates to a vessel for the transfer of a radioactive substance which is adsorbed on an ion exchanger in the granular state.
  • the ion exchanger vessel according to the invention in which is circulated a solution containing a radioactive substance to be adsorbed on the ion exchanger makes it possible to satisfy the different practical requirements which are outlined hereinafter, whereas this was not the case with columns of known types which were employed for the same purpose and which usually had the shape of a right cylinder. These requirements are as follows:
  • the vessel must permit connection to one or a number of stationary installations in order that the radioactive solution can circulate therein under the most favorable conditions of safety;
  • the vessel must ensure uniform distribution of said solution throughout the mass of the ion exchanger
  • the vessel must permit heating of the ion exchanger and of said solution while this latter is being circulated;
  • the vessel must serve to transfer the radioactive substance and comply with standards of transportation of radioactive substances.
  • the present invention relates to a vessel for transferring a radioactive substance which is adsorbed on an ion exchanger in the granular state, said vessel being essentially characterized in that it comprises on the one hand a column in the form of a hollow cylindrical ring which is intended to contain an ion exchanger in the granular state and is surrounded by a shield having good thermal conductivity, and on the other hand at least one pipe for the supply of radioac tive solution which penetrates into said column and at least one pipe for the discharge ofirradiated liquid.
  • the circulated ring which constitutes the column can be formed by the juxtaposed assembly of two cylindrical halfrings, at least one pipe for the supply of radioactive solution being intended to penetrate into each half-ring.
  • Said discharge pipe emerges from the column which is designed in the form of a cylindrical ring and provision is made for a cup which is formed in said shield and in which the supply and discharge pipes have their openings, and for a device which serves to heat the radioactive solution which circulates within said column.
  • said heating device is a coil housed within the inner cylinder of the cylindrical ring which forms the column.
  • a coil housed within the inner cylinder of the cylindrical ring which forms the column is employed for circulating a liquid which is irradiated by the radioactive element which is adsorbed on the granular ion exchanger and the downstream end of said coil constitutes said pipe for the discharge ofirradiated liquid.
  • H6. 1 is an axial sectional view of said vessel
  • FIG. 2 is a sectional view of the vessel of FIG. 1, this view being taken at right angles of the longitudinal axis of the vessel.
  • the vessel in accordance with the invention is seen to comprise a column 1 formed by the juxtaposed assembly of two cylindrical half-rings 1a, 1b, said column being surrounded by a shield 2 which possesses good heat conduc' tivity.
  • a cup Sis formed in the shielding 2 and the pipes 3a, 3b, 4a, 412 have their openings in the base of said cup.
  • a coil 6 housed within the cylindrical cavity 7 serves to heat the radioactive solution which circulates within each of the two half-rings la, lb.
  • thermocouples 8 and 9 designate respectively a thermal protection casing and thermocouples.
  • the vessel in accordance with the invention is intended to transfer a radioactive substance which is adsorbed on an ion exchanger in the granular state which is placed within the two cylindrical half-rings la and lb.
  • the ion exchanger consists. for example, of resin beads and the radioactive substance to be adsorbed on said ion exchanger is, for example, caesium contained in a concentrated solution of fission products.
  • the device in accordance with the invention operates according to one of the two modes described hereinafter:
  • the radioactive solution passes through the supply pipes 3a and 3b into the two cylindrical half-rings la, lb (as indicated by the arrows Fl) and impregnates the ion exchanger (not shown in the drawings); the radioactive element which is thus adsorbed on the granular ion exchanger is recovered by elution (discharge pipes 4a, 4b, arrows F2) for the purpose of constituting sources outside the vessel.
  • the cup 5 serves to connect the vessel to a stationary installation, thereby permitting the radioactive solution to circulate under the best conditions of safety.
  • the shape and the dimensions of the two half-rings Ia, lb are chosen so that, while the solution is being circulated, the pressure drop is low (for example of the order of 1 meter of water column in respect of flow rates of a few tens of cubic decimeters of solution per hour) and so that the solution should be uniformly distributed throughout the mass of ion exchanger grains.
  • the coil 6 serves to heat the ion exchanger and the radioactive solution while this latter is being circulated within the cylindrical half-rings la, lb, the temperature attained being within the range, for example, of 60 C. to C.
  • the radioactive element which is adsorbed on the granular ion exchanger constitutes an annular radiation source disposed around the cavity 7 which serves as an irradiation chamber and the coil 6 is employed for the circulation of a liquid which is irradiated by the radioactive element adsorbed on the granular ion exchanger.
  • the downstream end of said coil constitutes the pipe through which the irradiated liquid is discharged.
  • the shielding 2 is in direct contact with the half-rings la, lb, thereby permitting efficient removal of heat produced within the ion exchanger by the radioactive solution. in this manner, the temperature attained within the ion exchanger during periods of storage is maintained at an acceptable value.
  • the thermocouples 9 serve to determine at each moment the temperature which exists within the interior of each cylindrical half-ring la, lb.
  • a vessel for the purpose oftransferring a radioactive sub stance which is adsorbed on an ion exchanger in the granular state said vessel being characterized in that it comprises a column in the form of a hollow cylindrical ring formed by walls defining an enclosed annular hollow for holding an ion exchanger in the granular state surrounding a central space, said ring being surrounded by a shield having good thermal conductivity, and at least one pipe for the supply of radioactive solution which penetrates into said central space and at least one pipe for the discharge of irradiated liquid.
  • a vessel in accordance with Claim 1 characterized in that said hollow cylindrical ring constituting the column is formed by the juxtaposed assembly of two hollow cylindrical half-rings forming separate compartments in said column, at least one pipe for the supply of radioactive solution being intended to penetrate into each half ring.
  • a vessel in accordance with Claim ll characterized in that said discharge pipe emerges from the column which is 5.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • General Chemical & Material Sciences (AREA)
  • Treatment Of Water By Ion Exchange (AREA)
  • Treatment Of Liquids With Adsorbents In General (AREA)
  • Physical Or Chemical Processes And Apparatus (AREA)
  • Medicines That Contain Protein Lipid Enzymes And Other Medicines (AREA)
US801093A 1968-02-28 1969-02-20 Ion exchange vessel having hollow cylindrical ring construction for the transfer of a radioactive substance Expired - Lifetime US3626191A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR141696 1968-02-28

Publications (1)

Publication Number Publication Date
US3626191A true US3626191A (en) 1971-12-07

Family

ID=8646708

Family Applications (1)

Application Number Title Priority Date Filing Date
US801093A Expired - Lifetime US3626191A (en) 1968-02-28 1969-02-20 Ion exchange vessel having hollow cylindrical ring construction for the transfer of a radioactive substance

Country Status (11)

Country Link
US (1) US3626191A (nl)
BE (1) BE728061A (nl)
CH (1) CH503351A (nl)
DE (1) DE1908253B2 (nl)
ES (1) ES364173A1 (nl)
FR (1) FR1563936A (nl)
GB (1) GB1220035A (nl)
IL (1) IL31587A (nl)
LU (1) LU58051A1 (nl)
NL (1) NL6902894A (nl)
SE (1) SE344130B (nl)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20140263008A1 (en) * 2013-03-15 2014-09-18 Avantech, Inc. Apparatus and Method for Removal of Radionuclides in Liquids

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3704046A1 (de) * 1987-02-10 1988-08-18 Allgaeuer Alpenmilch Verfahren zum entfernen von radioaktiven metallen aus fluessigkeiten, lebens- und futtermitteln
WO2002065478A1 (fr) * 2001-02-13 2002-08-22 Framatome Anp Procede et dispositif de traitement d'un liquide contamine par au moins un radio-element et d'elimination du radio-element_______

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2968734A (en) * 1956-01-06 1961-01-17 Martin Co Device for the exposure of fluid to radiation
US2992980A (en) * 1957-05-16 1961-07-18 Exxon Research Engineering Co Apparatus for radiation promoted processes
US3156532A (en) * 1961-06-30 1964-11-10 Robert F Doering Yttrium-90 generator
US3369121A (en) * 1966-04-06 1968-02-13 Squibb & Sons Inc Radioactive package and container therefor

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2968734A (en) * 1956-01-06 1961-01-17 Martin Co Device for the exposure of fluid to radiation
US2992980A (en) * 1957-05-16 1961-07-18 Exxon Research Engineering Co Apparatus for radiation promoted processes
US3156532A (en) * 1961-06-30 1964-11-10 Robert F Doering Yttrium-90 generator
US3369121A (en) * 1966-04-06 1968-02-13 Squibb & Sons Inc Radioactive package and container therefor

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20140263008A1 (en) * 2013-03-15 2014-09-18 Avantech, Inc. Apparatus and Method for Removal of Radionuclides in Liquids
US9896352B2 (en) * 2013-03-15 2018-02-20 Avantech, Inc. Apparatus for removal of radionuclides in liquids
US9896351B2 (en) 2013-03-15 2018-02-20 Avantech, Inc. Method for removal of radionuclides in liquids
US10717660B2 (en) 2013-03-15 2020-07-21 Avantech, Inc. Vessel for removing radionuclides from a liquid

Also Published As

Publication number Publication date
LU58051A1 (nl) 1969-06-03
DE1908253A1 (de) 1969-12-04
IL31587A0 (en) 1969-11-12
NL6902894A (nl) 1969-09-01
SE344130B (nl) 1972-03-27
FR1563936A (nl) 1969-04-18
ES364173A1 (es) 1972-01-01
GB1220035A (en) 1971-01-20
DE1908253B2 (de) 1971-06-16
BE728061A (nl) 1969-07-16
CH503351A (fr) 1971-02-15
IL31587A (en) 1972-06-28

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