ANALYTICAL METHOD FOR THE DETERMINATION OF IODINE-131 IN REACTOR FUEL PROCESSING AND EFFLUENT TREATMENT PLANT SOLUTIONS
Technical Report
·
OSTI ID:4827600
Interchange between radioactive iodine and added carrier is obtained by an oxidation reduction cycle and the iodine is then extracted as the element into carbon tetrachloride. The iodine is extracted into dilute sodium bisulphite solution and precipitated as silver iodide. The BETA -activity of the precipitate is measured with a Geiger-Mueller counier. The method is applicable to samples (3 x 10/sjup 4/ to 6 x 10/sup 5/ dpm) from the Windscale primary separation plant, uranium purification plant, and effluent treatment plant. (auth)
- Research Organization:
- United Kingdom Atomic Energy Authority. Production Group, Windscale, Sellafield, England
- NSA Number:
- NSA-16-022006
- OSTI ID:
- 4827600
- Report Number(s):
- PG-Report-334
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
Similar Records
THE DETERMINATION OF 131 IODINE IN THYROID GLANDS
ANALYTICAL METHODS FOR THE DETERMINATION OF IODINE-131 IN VEGETATION, MILK, THYROID GLANDS AND NATURAL WATERS
THE DETERMINATION OF RADIOIODINE
Technical Report
·
Fri Jan 31 23:00:00 EST 1958
·
OSTI ID:4343182
ANALYTICAL METHODS FOR THE DETERMINATION OF IODINE-131 IN VEGETATION, MILK, THYROID GLANDS AND NATURAL WATERS
Technical Report
·
Sat Dec 31 23:00:00 EST 1960
·
OSTI ID:4057599
THE DETERMINATION OF RADIOIODINE
Technical Report
·
Sun May 01 00:00:00 EDT 1960
·
OSTI ID:4169266