05.08.2013 Views

ORNL-1771 - Oak Ridge National Laboratory

ORNL-1771 - Oak Ridge National Laboratory

ORNL-1771 - Oak Ridge National Laboratory

SHOW MORE
SHOW LESS

You also want an ePaper? Increase the reach of your titles

YUMPU automatically turns print PDFs into web optimized ePapers that Google loves.

ANP QUARTERLY PROGRESS REPORT<br />

10. ANALYTICAL STUDIES OF REACTOR<br />

The primary analytical problem continues to bs<br />

the separation and determination of trivalent and<br />

tctravalent uranium in both NaZrF,. and NaF-KF-<br />

LiF-base fuels. A successful potentiometric titra-<br />

tion of UF, in molten NaZrF, with metallic zir-<br />

conium was accomplished by means of polarized<br />

platinum electrodes, The observed end point<br />

occurred at a weight of titrant which corresponded<br />

to one-half an squivolent of zirconium metal per<br />

mole of UF,. This stoichiometry indicates reduc-<br />

tion of UF, to a mixed oxidation state. Polaro-<br />

giaphic studies of uranium fluorides in reactor fuels<br />

dissolved in molten ammoniirni formate at 125OC<br />

were initiated. Preliminaiy experiments reve"aled<br />

that tetravalent uranium was not reduced at the<br />

dropping-mercury electrode. Molten ammonium<br />

formate appears to be o useful solvent for fluoride-<br />

base fuels containing various oxidation states of<br />

uranium. The conversion of UF, to UCI, in fluoride<br />

fuels was shown to be quantitative when the fuel<br />

was heated with boron trichloride at 40O0C for<br />

90 min. Trivalent uranium fluoride is converted to<br />

UCI, under these conditions. The solubility of<br />

UF, in NaAICI, was found to be 18 mg/g at 200OC<br />

os contrasted to o solubility of UF, of less than<br />

1 mg/g. Molten NaAICI, is expected to dissolve<br />

telkavalent uranium selectively from the fuels.<br />

Calibration measurements have been completed<br />

on the apparatus for the determination of oxygen as<br />

metallic oxides in reactor fuels. The reaction in-<br />

volver thc hydrofluorination of the oxide and<br />

measurement of the increase in conductivity of<br />

liquid HF as a function of the water formed,<br />

Investigations were also made on the oxidation<br />

of UF, with oxygen at elevated temperatures. At<br />

30OoC, UF, is converted quantitatively to UF,<br />

and UO,. The mechanism of the oxidation of UF,<br />

with oxygen is being studied. An oxide residue of<br />

about 11% of the original material was found when<br />

UF, was heated in oxygen at 3OOOC for 2 hr.<br />

An improved method for the determination of<br />

lithium in NaF-KF-LiF-base fuels WQ5 developed,<br />

The chloride salt is extracted with 2-ethylhexano1,<br />

and the chloride is titrated in the nonaqueous<br />

mediums,<br />

148<br />

c. D, Susan0<br />

Anal yt ical Chemi stry Di vi si on<br />

J. M. Warde<br />

Metallurgy Division<br />

Studies were also made on the solubilities of<br />

potassium, TZI bi d iom, and cesi urn tetrapheny i borate s<br />

in various organic solvents to ascertain differential<br />

solubilities. The feasibility of a spectrophoto-<br />

metric titration of fluoride in NaF-KF(RbF)-Li F-<br />

base materials by decolorization of zirconium or<br />

aluminum complexes was investigated. Determina-<br />

tion of the concentration of oil in helium was mode<br />

by absorbing the hydrocarbons in petroleum ether<br />

and weighing the residue obtained after evaporation.<br />

It was found that prior bleeding of the line effec-<br />

tively eliminated contamination by oil.<br />

ANALYTBCAL CHEMISTRY OF<br />

REACTOR MATERBALS<br />

J. c. White<br />

Analytical Chemistry Division<br />

Research and development were continued on the<br />

problem of determining UF, and UF, in NaZrF,-<br />

and NaF-KF-LIF-base reactor fuels. A number of<br />

new opproachss to this problem were investigated,<br />

including redox titrations of the fluoride mixtures in<br />

the molten state, for which polarized platinum<br />

electrodes were used, and polarographic studies of<br />

fluoride mixtures in molten ammonium formate.<br />

Work was continued on the determinotion of oxygen<br />

in fluoride fuels and on the determination of alkali<br />

metals and fluoride ion in NaF-KF-LiF-base ma-<br />

terial s,<br />

Determination of Oxygen in Fluwide Fuels<br />

A. S, Meyer, Jr. J. M, Peele<br />

Analytical Chemistry Division<br />

The apparatus for the determination of oxygen as<br />

oxides in fluoride fuels, which was described<br />

briefly in a previous report, ' has been constructed.<br />

A schematic drawing of this apparatus is shown in<br />

Fig, 10.1.<br />

The hydrogen fluoride purification still, which<br />

was fabricated from mild steell is equipped with<br />

a 24 x 1 in. packed column with an estimated<br />

efficiency of 25 theoretical plates. Conductivity<br />

'A. S. Meyer, Jr. and J. M. Peele, ANP Quar. hog.<br />

Rep. lune IO, 1954, <strong>ORNL</strong>-1729, p 110.

Hooray! Your file is uploaded and ready to be published.

Saved successfully!

Ooh no, something went wrong!