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
ANP QUARTERLY PROGRESS REPORT felt for further study of the accuracy of the method. A testing program was inaugurated in which an enriched sample of U,O, containing 99.86 at. % U235 and 0.07 at. % U238, obtained from B. Harmatz,’ was used as the starting material. This material was chemically purified for use as a standard, and the isotope ratio was carefully de- termined. The material was then dissolved in HNO, and diluted to make a standard stock solution. Small portions of this solution were put through the normal ether extraction process used for extracting -type fuel samples. Any change sition was attributed to contami- nation by natural uranium present in reagents and glassware. The observed uranium contamination than 0.5 pg per sample, the normal uranium con- chemical separations of 7B. Harmatz, H. C. McCurdy, and F. N. Case, Catalog of Uranium, Thorium, and Plutonium Isotopes, ORNL- 1724, p 2 (May 19, 1954). 128 fuel uranium is negligible for the usual fuel samples which exceed 500 pg of uranium. The second test of the isotopic dilution method verified the concentration of the standard solutions, the accuracy of the spiking, and the reliability of the mass spectrometer. Known mixtures of normal and enriched uranium solutions were examined in the mass spectrometer, and the results were com- pared with the expected U2,’ concentrations, The greatest difference between calculated percentages and measured percentages was only 0.65%, and the average difference was 0.37%. The results of these studies show that the isotopic dilution method is reliable and that good results can be obtained under the conditions which have been used for ARE-type fuel analyses. The method of determining burnup based on measure- ments of the U236 grown in is less subject to error from sample contamination than is the method based on measurements of U238 and is therefore considered to give the more reliable data. f t
PERIOD ENDING DECEMBER 70, 7954 - A 10. ANALYTICAL STUDIES OF REACTOR MATERIALS The research effort in analytical ch concentrated primarily on NaF-KF-LiF-base reactor fuel, and, in particular, on analysis after it had been utilized as a solvent for the reduction of UF, by Uo to UF,. Tentative methods for the determination of Uo and UF, were developed. Studies were continued on the determination of oxygen as oxides in fluoride fuels. Development work was completed on the determination of sulfur in various reactor fuels and coolants and in off- gases from the production of fluoride fuels. Be- cause of the urgency of other activities, no further workwas done onthe determination of alkali metals in NaF-KF-LiF-base fuels.' ANALYTICAL CHEMISTRY OF REACTOR MATERIALS J. C. White Analytical Chemistry Division Determination of Uranium Metal in Fluoride Salt Mixtures A. S. Meyer, Jr. B. L. McDowell Analytical Chemistry Division A method based on the measurement of the hydrogen derived from the decomposition of UH, was developed for the determination of Uo in nronosed reortor fuels. In this determination Uo is con lverted to UH, by heatina in ". of hvdroaen , " at 250'C 'for 1 hr. - The . UH, is decomposed by heating ina stream of Co, at 4OO0C, m C. D. Susano Analytical Chemistry Division xoduced by the reduc- _ _ The CO is reduced at temper- , L -- * .,.?-. ' )th Uo and UF,. 1,. ce Go Le McDowell, ANP Quar. Prog. Rep. Sept. 10, 1954. ORNL-1771, p 152. J. M. Warde Metal I urgy D iv is ion _.1 The volumes of gas derived from reactions 1 and 2 are reproducible; 1.5 moles of CO is formed for each mole of UH, decomposed when the ignition is carried out at temperatures between 500 and 6OO0C, and 0.5 mole of CO is formed per mole of UF, under similar conditions. The CO must be removed from the effluent gases before ttle meas- urement of hydrogen is made. This is accornplished by passing the gases through a tube packed with I,O, and powdered pumice, which is maintained at a temperature of 150°C. The CO is oxidized to CO, in the following reaction: 5CO + I,O, + 5C0, + 1, When the method was tested by analyzing samples of pure uranium metal, the hydrogen evolved corresponded to 97% of the theoretical value with a coefficient of variation of 2%. Satisfactory precision has also been obtained for the deter- mination of Uo in NaF-KF-LiF-base fuels and in UF,. The concentration limits of the methcds have not been measured experimentally, but, on the basis of the quantities measured, concentrcitions of Uo as low as 0.05% may be determined when 1-9 samples are utilized. Since the I,O, tubes may become inactivated after only limited service, a more dependable method of eliminating the CO is needed. In a modified procedure that is being considered, UH, will be decomposed in an atmosphere of iimmonia and the hydrogen will be measured over a solution A. S. Meyer, Jr. D. L. Manning in Fluoride Fuels W. J. Ross B. L. McDoweII * I . , P I . . m. .. d eve I o p i n rimetric metb priate conditions, trivalent uranium is selectively oxidized by cupric chloride, CuCI,, titanium tetra-
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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-