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Title: METHOD OF SEPARATING FISSION PRODUCTS FROM FUSED BISMUTH-CONTAINING URANIUM

Abstract

A process is described for removing metal selectively from liquid metal compositions. The method effects separation of flssion product metals selectively from dilute solution in fused bismuth, which contains uraniunn in solution without removal of more than 1% of the uranium. The process comprises contacting the fused bismuth with a fused salt composition consisting of sodium, potassium and lithium chlorides, adding to fused bismuth and molten salt a quantity of bismuth chloride which is stoichiometrically required to convert the flssion product metals to be removed to their chlorides which are more stable in the fused salt than in the molten metal and are, therefore, preferentially taken up in the fused salt phase.

Inventors:
Issue Date:
Research Org.:
Originating Research Org. not identified
OSTI Identifier:
4330398
Patent Number(s):
2840464
Assignee:
U.S. Atomic Energy Commission DTIE; NSA-12-014420
NSA Number:
NSA-12-014420
Resource Type:
Patent
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-58
Country of Publication:
United States
Language:
English
Subject:
PATENTS; BISMUTH; BISMUTH CHLORIDES; FISSION PRODUCTS; FUSED SALTS; LITHIUM CHLORIDES; PATENT; POTASSIUM CHLORIDES; SEPARATION PROCESSES; SODIUM CHLORIDES; SOLUTIONS; URANIUM

Citation Formats

Wiswall, R.H. METHOD OF SEPARATING FISSION PRODUCTS FROM FUSED BISMUTH-CONTAINING URANIUM. United States: N. p., 1958. Web.
Wiswall, R.H. METHOD OF SEPARATING FISSION PRODUCTS FROM FUSED BISMUTH-CONTAINING URANIUM. United States.
Wiswall, R.H. Tue . "METHOD OF SEPARATING FISSION PRODUCTS FROM FUSED BISMUTH-CONTAINING URANIUM". United States.
@article{osti_4330398,
title = {METHOD OF SEPARATING FISSION PRODUCTS FROM FUSED BISMUTH-CONTAINING URANIUM},
author = {Wiswall, R.H.},
abstractNote = {A process is described for removing metal selectively from liquid metal compositions. The method effects separation of flssion product metals selectively from dilute solution in fused bismuth, which contains uraniunn in solution without removal of more than 1% of the uranium. The process comprises contacting the fused bismuth with a fused salt composition consisting of sodium, potassium and lithium chlorides, adding to fused bismuth and molten salt a quantity of bismuth chloride which is stoichiometrically required to convert the flssion product metals to be removed to their chlorides which are more stable in the fused salt than in the molten metal and are, therefore, preferentially taken up in the fused salt phase.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1958},
month = {6}
}