GB896758A - Improvements in or relating to the separation of technetium from fission product solutions - Google Patents

Improvements in or relating to the separation of technetium from fission product solutions

Info

Publication number
GB896758A
GB896758A GB3866159A GB3866159A GB896758A GB 896758 A GB896758 A GB 896758A GB 3866159 A GB3866159 A GB 3866159A GB 3866159 A GB3866159 A GB 3866159A GB 896758 A GB896758 A GB 896758A
Authority
GB
United Kingdom
Prior art keywords
technetium
separation
solution
relating
iron
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
GB3866159A
Inventor
Gwilym Morgan Phillips
Joseph Jackson Hillary
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.)
UK Atomic Energy Authority
Original Assignee
UK Atomic Energy Authority
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 UK Atomic Energy Authority filed Critical UK Atomic Energy Authority
Priority to GB3866159A priority Critical patent/GB896758A/en
Publication of GB896758A publication Critical patent/GB896758A/en
Expired 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
    • G21F9/007—Recovery of isotopes from radioactive waste, e.g. fission products

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)

Abstract

896,758. Separation of technetiiim. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. Oct. 18, 1960 [Nov 13, 1959J No. 38661/59. Class 39(4). Technetium is separated from an acidified nitrate solution of fission products by making the solution alkaline with sodium hydroxide, contacting the solution with a strongly basic anion exchange resin which retains the technetium, and eluting the technetium from the resin with nitric acid. The eluate may be concentrated and purified from iron, chromium, and ruthenium by complexing the iron as .a tartrate, making the solution alkaline with sodium hydroxide, extracting the technetium with methyl ethyl ketone and distilling off the ketone.
GB3866159A 1959-11-13 1959-11-13 Improvements in or relating to the separation of technetium from fission product solutions Expired GB896758A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB3866159A GB896758A (en) 1959-11-13 1959-11-13 Improvements in or relating to the separation of technetium from fission product solutions

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB3866159A GB896758A (en) 1959-11-13 1959-11-13 Improvements in or relating to the separation of technetium from fission product solutions

Publications (1)

Publication Number Publication Date
GB896758A true GB896758A (en) 1962-05-16

Family

ID=10404883

Family Applications (1)

Application Number Title Priority Date Filing Date
GB3866159A Expired GB896758A (en) 1959-11-13 1959-11-13 Improvements in or relating to the separation of technetium from fission product solutions

Country Status (1)

Country Link
GB (1) GB896758A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3436354A (en) * 1967-01-17 1969-04-01 Union Carbide Corp Production of a solution containing radioactive technetium
US3468808A (en) * 1967-06-16 1969-09-23 Union Carbide Corp Production of high purity radioactive technetium-99m

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3436354A (en) * 1967-01-17 1969-04-01 Union Carbide Corp Production of a solution containing radioactive technetium
US3468808A (en) * 1967-06-16 1969-09-23 Union Carbide Corp Production of high purity radioactive technetium-99m

Similar Documents

Publication Publication Date Title
GB896758A (en) Improvements in or relating to the separation of technetium from fission product solutions
ES263657A1 (en) A procedure for the preparation of sorbic acid (Machine-translation by Google Translate, not legally binding)
CA567255A (en) Separation of plutonium by anion exchange resin
Barta et al. Treatment of waste waters from the manufacture of citric acid by sulphide fermentation
AU214767B2 (en) Improvements relating to ion-exchange processes
GB876014A (en) Treatment of aqueous liquid solutions of chelate-forming metal ions with chelate exchange resins
AU5139859A (en) Improvements relating to ion-exchange resins
AU237382B2 (en) Improvements in or relating to methods of extracting metals by anion exchange process
AU242753B2 (en) Improvements in or relating to nuclear reactor. control rods
AU234009B2 (en) Improvements relating to ion-exchange resins and their manufacture
AU231826B2 (en) Improvements relating to ion-exchange processes
AU239532B2 (en) Improvements relating to ion-exchange processes
AU220565B2 (en) Improvements relating to anion-exchange resins
AU216210B2 (en) Improvements in or relating to nuclear reactors
AU214571B2 (en) Improvements in or relating to nuclear reactors
AU221057B2 (en) Improvements in or relating to nuclear reactors
AU1944156A (en) Improvements relating to ion-exchange processes
AU272984B2 (en) Process for the preparation of a unanium-iv nitrate solution suitable to be employed as reducing agent for plutonium in a reprocessing flow sheet
AU5518359A (en) Improvements in or relating to methods of extracting metals by anion exchange process
AU232113B2 (en) Improvements in or relating to plants including nuclear reactors
AU231746B2 (en) Improvements relating to electromagnetic code conversion arrangements
AU228433B2 (en) Improvements in or relating to nuclear reactor pressure vessels
AU234894B2 (en) Improvements in or relating to nuclear reactors
AU226590B2 (en) Improvements in or relating to nuclear reactors
AU234589B2 (en) Improvements in or relating to nuclear reactors