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THE RADIOCHEMICAL DETERMINATION OF RUTHENIUM 103 AND 106 IN REACTOR FUEL PROCESSING AND PLANT SOLUTIONS

Technical Report ·
OSTI ID:4195578
A method for determining Ru/sup 103/ and Ru/sup 106/ in solutions containing mixed fission products is presented. Interchange between added carrier and radioruthenium in the sample is effected by boiling in alkaline solution in the presence of an oxidant. Ruthenium is extracted as tetroxide into carbon tetrachloride and precipitated as the dioxide. After mounting on stainless steel trays, the beta and gamma activities are measured. The observed activities are corrected for the chemical yield of the separation procedure, determined by absorptiometric measurement of a solution prepared from the source after counting. (auth)
Research Organization:
United Kingdom Atomic Energy Authority. Production Group. Chemical Services Dept., Windscale, Sellafield, England
NSA Number:
NSA-14-008443
OSTI ID:
4195578
Report Number(s):
PGR-78(W)
Country of Publication:
Country unknown/Code not available
Language:
English