ORNL-1816 - the Molten Salt Energy Technologies Web Site
ORNL-1816 - the Molten Salt Energy Technologies Web Site
ORNL-1816 - the Molten Salt Energy Technologies Web Site
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PERIOD ENDING DECEMBER 70, 7954<br />
- A<br />
10. ANALYTICAL STUDIES OF REACTOR MATERIALS<br />
The research effort in analytical ch<br />
concentrated primarily on NaF-KF-LiF-base reactor<br />
fuel, and, in particular, on analysis after it had<br />
been utilized as a solvent for <strong>the</strong> reduction of<br />
UF, by Uo to UF,. Tentative methods for <strong>the</strong><br />
determination of Uo and UF, were developed.<br />
Studies were continued on <strong>the</strong> determination of<br />
oxygen as oxides in fluoride fuels. Development<br />
work was completed on <strong>the</strong> determination of sulfur<br />
in various reactor fuels and coolants and in off-<br />
gases from <strong>the</strong> production of fluoride fuels. Be-<br />
cause of <strong>the</strong> urgency of o<strong>the</strong>r activities, no fur<strong>the</strong>r<br />
workwas done on<strong>the</strong> determination of alkali metals<br />
in NaF-KF-LiF-base fuels.'<br />
ANALYTICAL CHEMISTRY OF<br />
REACTOR MATERIALS<br />
J. C. White<br />
Analytical Chemistry Division<br />
Determination of Uranium Metal in<br />
Fluoride <strong>Salt</strong> Mixtures<br />
A. S. Meyer, Jr. B. L. McDowell<br />
Analytical Chemistry Division<br />
A method based on <strong>the</strong> measurement of <strong>the</strong><br />
hydrogen derived from <strong>the</strong> decomposition of UH,<br />
was developed for <strong>the</strong> determination of Uo in<br />
nronosed reortor fuels. In this determination Uo<br />
is con lverted to UH, by heatina in<br />
".<br />
of hvdroaen , " at 250'C 'for 1 hr. - The . UH, is decomposed<br />
by heating ina stream of Co, at 4OO0C,<br />
m<br />
C. D. Susano<br />
Analytical Chemistry Division<br />
xoduced by <strong>the</strong> reduc-<br />
_ _ The CO is reduced at temper-<br />
, L -- * .,.?-.<br />
' )th Uo and UF,.<br />
1,. ce Go Le McDowell, ANP<br />
Quar. Prog. Rep. Sept. 10, 1954. <strong>ORNL</strong>-1771, p 152.<br />
J. M. Warde<br />
Metal I urgy D iv is ion<br />
_.1<br />
The volumes of gas derived from reactions 1 and<br />
2 are reproducible; 1.5 moles of CO is formed for<br />
each mole of UH, decomposed when <strong>the</strong> ignition<br />
is carried out at temperatures between 500 and<br />
6OO0C, and 0.5 mole of CO is formed per mole of<br />
UF, under similar conditions. The CO must be<br />
removed from <strong>the</strong> effluent gases before ttle meas-<br />
urement of hydrogen is made. This is accornplished<br />
by passing <strong>the</strong> gases through a tube packed with<br />
I,O, and powdered pumice, which is maintained at<br />
a temperature of 150°C. The CO is oxidized to<br />
CO, in <strong>the</strong> following reaction:<br />
5CO + I,O, + 5C0, + 1,<br />
When <strong>the</strong> method was tested by analyzing samples<br />
of pure uranium metal, <strong>the</strong> hydrogen evolved<br />
corresponded to 97% of <strong>the</strong> <strong>the</strong>oretical value with<br />
a coefficient of variation of 2%. Satisfactory<br />
precision has also been obtained for <strong>the</strong> deter-<br />
mination of Uo in NaF-KF-LiF-base fuels and in<br />
UF,. The concentration limits of <strong>the</strong> methcds have<br />
not been measured experimentally, but, on <strong>the</strong><br />
basis of <strong>the</strong> quantities measured, concentrcitions of<br />
Uo as low as 0.05% may be determined when 1-9<br />
samples are utilized.<br />
Since <strong>the</strong> I,O, tubes may become inactivated<br />
after only limited service, a more dependable<br />
method of eliminating <strong>the</strong> CO is needed. In a<br />
modified procedure that is being considered, UH,<br />
will be decomposed in an atmosphere of iimmonia<br />
and <strong>the</strong> hydrogen will be measured over a solution<br />
A. S. Meyer, Jr.<br />
D. L. Manning<br />
in Fluoride Fuels<br />
W. J. Ross<br />
B. L. McDoweII<br />
* I . , P I . . m. ..<br />
d eve I o p i n rimetric metb<br />
priate conditions, trivalent uranium is selectively<br />
oxidized by cupric chloride, CuCI,, titanium tetra-