Published 1975 | Version v1
Miscellaneous Open

Determination of uranium in solutions by the method of absorption of gamma radiation

Description

Using the method fo gamma-radiation absorption a special device was constructed to determine uranium in solutions containing fission products, with activity up to 100 mcurie. Am241 was used as standard source of γ radiation. To measure γ radiation a scintillation probe with photomultiplier was used. The block diagram and calibrating scheme of the device are given. It is stated that relative reproducability of determinations of uranium content in solutions in the concentration range of 10-30 g U in a litre is more than 2%, and for higher concentrations it is more than 1%. The sample self-irradiation does not produce any effect on the measurement results. The device provides continuous measurement of uranium content in flowing solutions with uranium content from 10 to 300 g/l. This allows one to use the device as uranium concentration meter for controlling the spent fuel reprocessing

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Additional details

Additional titles

Original title (Russian)
Определение урана в растворах методом абсорбции гамма-излучения

Publishing Information

Imprint Title
Investigations in the field of spent fuel reprocessing. V. 3
Journal Page Range
p. 162-166.
Report number
INIS-mf--5568

Conference

Title
3. CMEA symposium on investigations in the field of spent fuel reprocessing.
Dates
24 - 26 Apr 1974.
Place
Marianske Lazne, Czechoslovakia.

Optional Information

Notes
6 refs.; 3 figs. Imprint:Issledovaniya v oblasti pererabotki obluchennogo topliva. Tom 3.;Materialy 3. Simpoziuma SEhV.