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Title: IODATE METHOD FOR PURIFYING PLUTONIUM

Abstract

A method is presented for removing radioactive fission products from aqueous solutions containing such fission products together with plutonium. This is accomplished by incorporating into such solutions a metal iodate precipitate to remove fission products which form insoluble iodates. Suitable metal iodates are those of thorium and cerium. The plutonium must be in the hexavalent state and the pH of the solution must be manintained at less than 2.

Inventors:
;
Publication Date:
Research Org.:
Originating Research Org. not identified
OSTI Identifier:
4247522
Patent Number(s):
US 2856261
Assignee:
U.S. Atomic Energy Commission DTIE; NSA-13-008359
Resource Type:
Patent
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-59
Country of Publication:
United States
Language:
English
Subject:
PATENTS; ACIDITY; BINDING ENERGY; CERIUM COMPOUNDS; ELECTRONS; FISSION PRODUCTS; IODIC ACID; MINERAL ACIDS; PLUTONIUM; PRECIPITATION; RADIOACTIVITY; REFINING; SEPARATION PROCESSES; SOLUTIONS; THORIUM COMPOUNDS; WATER

Citation Formats

Stoughton, R.W., and Duffield, R.B.. IODATE METHOD FOR PURIFYING PLUTONIUM. United States: N. p., 1958. Web.
Stoughton, R.W., & Duffield, R.B.. IODATE METHOD FOR PURIFYING PLUTONIUM. United States.
Stoughton, R.W., and Duffield, R.B.. 1958. "IODATE METHOD FOR PURIFYING PLUTONIUM". United States. doi:.
@article{osti_4247522,
title = {IODATE METHOD FOR PURIFYING PLUTONIUM},
author = {Stoughton, R.W. and Duffield, R.B.},
abstractNote = {A method is presented for removing radioactive fission products from aqueous solutions containing such fission products together with plutonium. This is accomplished by incorporating into such solutions a metal iodate precipitate to remove fission products which form insoluble iodates. Suitable metal iodates are those of thorium and cerium. The plutonium must be in the hexavalent state and the pH of the solution must be manintained at less than 2.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = 1958,
month =
}
  • An effective method for purifying plutonium hexafluoride for the reprocessing of the spent nuclear fuel or for the recovery of fuel plutonium from the scrap by fluoride-volatility with high decontamination factors is presented using a selective adsorption of the fission products fluorides by letting the gas mixture flow through a layer of an adsorbent consisting of one or more of the specified compounds selected from hexafluoro sodium aluminate, zinc fluoride, nickel fluoride and ferric fluoride at an elevated temperature. The principle of the purification method is based on the fact that the fluorides of the fission products are easily adsorbedmore » by the adsorbent but little plutonium hexafluoride is adsorbed. The fluorides of the fission products are easily removed from the adsorbent by heating and the recycling use of the adsorbent is possible.« less
  • A process is described for precipitating plutonium on a uranous iodate carrier from an aqueous acid solution conA plutonium solution more concentrated than the original solution can then be obtained by oxidizing the uranium to the hexavalent state and dissolving the precipitate, after separating the latter from the original solution, by means of warm nitric acid.