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Title: ADSORPTION-BISMUTH PHOSPHATE METHOD FOR SEPARATING PLUTONIUM

Abstract

A process is given for separating plutonium from uranium and fission products. Plutonium and uranium are adsorbed by a cation exchange resin, plutonium is eluted from the adsorbent, and then, after oxidation to the hexavalent state, the plutonium is contacted with a bismuth phosphate carrier precipitate.

Inventors:
; ;
Publication Date:
Research Org.:
Originating Research Org. not identified
OSTI Identifier:
4141035
Patent Number(s):
US 2942937
Assignee:
U.S. Atomic Energy Commission DTIE; NSA-14-025574
Resource Type:
Patent
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-60
Country of Publication:
United States
Language:
English
Subject:
CHEMISTRY; ADSORPTION; BISMUTH PHOSPHATES; FISSION PRODUCTS; IONS; PLUTONIUM; RESINS; SEPARATION PROCESSES; URANIUM

Citation Formats

Russell, E.R., Adamson, A.W., and Boyd, G.E. ADSORPTION-BISMUTH PHOSPHATE METHOD FOR SEPARATING PLUTONIUM. United States: N. p., 1960. Web.
Russell, E.R., Adamson, A.W., & Boyd, G.E. ADSORPTION-BISMUTH PHOSPHATE METHOD FOR SEPARATING PLUTONIUM. United States.
Russell, E.R., Adamson, A.W., and Boyd, G.E. 1960. "ADSORPTION-BISMUTH PHOSPHATE METHOD FOR SEPARATING PLUTONIUM". United States. doi:.
@article{osti_4141035,
title = {ADSORPTION-BISMUTH PHOSPHATE METHOD FOR SEPARATING PLUTONIUM},
author = {Russell, E.R. and Adamson, A.W. and Boyd, G.E.},
abstractNote = {A process is given for separating plutonium from uranium and fission products. Plutonium and uranium are adsorbed by a cation exchange resin, plutonium is eluted from the adsorbent, and then, after oxidation to the hexavalent state, the plutonium is contacted with a bismuth phosphate carrier precipitate.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = 1960,
month = 6
}
  • A process is given for separating plutonium from fission products present on a bismuth phosphate carrier. The dried carrier is first treated with hydrogen fluoride at between 500 and 600 deg C whereby some fission product fluorides volatilize away from plutonium tetrafluoride, and nonvolatile fission product fluorides are formed then with anhydrous fluorine at between 400 and 500 deg C. Bismuth and plutonium distill in the form of volatile fluorides away from the nonvolatile fission product fluorides. The bismuth and plutonium fluorides are condensed at below 290 deg C.
  • A process is patented for metathesizing a Pu-carrying bismuth phosphate precipitate to a more easily acid-soluble hydroxide by reaction with a water-soluble carbonate, bicarbonate, or hydroxide in an aqueous medium.
  • A bismuth phosphate carrier precipitation process is patented for separating plutonium from fission products. Purification of plutonium is accomplished by precipitating bismuth phosphate in the presence of quadrivalent plutonium, thereby carrying plutonium from soluble fission products, and in another step precipitating bismuth phos phate in the presence of hexavalent plutonium, thereby carrying insoluble fission products from plutonium. Cerous ions are added to the solution containing Pu>s4/sup > /d mercuric ions are added to the solution containing Pu>s6/sup > /ior to precipitation thereby enhancing the separation.
  • A process is given for isolating plutonium present in the tetravalent state in an aqueous solution together with fission products. First, the plutonium and fission products are coprecipitated on a bismuth phosphate carrier. The precipitate obtained is dissolved, and the plutonium in the solution is oxidized to the hexavalent state (with ceric nitrate, potassium dichromate, Pb/ sub 3/O/sub 4/, sodium bismuthate and/or potassium dichromate). Thereafter a carrier for fission products is added (bismuth phosphate, lanthanum fluoride, ceric phosphate, bismuth oxalate, thorium iodate, or thorium oxalate), and the fission-product precipitation can be repeated with one other of these carriers. After removalmore » of the fission-product-containing precipitate or precipitates. the plutonium in the supernatant is reduced to the tetravalent state (with sulfur dioxide, hydrogen peroxide. or sodium nitrate), and a carrier for tetravalent plutonium is added (lanthanum fluoride, lanthanum hydroxide, lanthanum phosphate, ceric phosphate, thorium iodate, thorium oxalate, bismuth oxalate, or niobium pentoxide). The plutonium-containing precipitate is then dissolved in a relatively small volume of liquid so as to obtain a concentrated solution. Prior to dissolution, the bismuth phosphate precipitates first formed can be metathesized with a mixture of sodium hydroxide and potassium carbonate and plutonium-containing lanthanum fluorides with alkali-metal hydroxide. In the solutions formed from a plutonium-containing lanthanum fluoride carrier the plutonium can be selectively precipitated with a peroxide after the pH was adjusted preferably to a value of between 1 and 2. Various combinations of second, third, and fourth carriers are discussed.« less
  • A process is described for separating plutonium from fission products carried therewith when plutonium in the reduced oxidation state is removed from a nitric acid solution of irradiated uranium by means of bismuth phosphate as a carrier precipitate. The bismuth phosphate carrier precipitate is dissolved by treatment with nitric acid and the plutonium therein is oxidized to the hexavalent oxidation state by means of potassium dichromate. Separation of the plutonium from the fission products is accomplished by again precipitating bismuth phosphate and removing the precipitate which now carries the fission products and a small percentage of the plutonium present. Themore » amount of plutonium carried in this last step may be minimized by addition of sodium fluoride, so as to make the solution 0.03N in NaF, prior to the oxidation and prccipitation step.« less