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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-

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