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PROCESSING OF RADIOACTIVE WASTE

Patent ·
OSTI ID:4839183

A process for concentrating fission-product-containing waste solutions from fuel element processing is described. The process comprises the addition of sugar to the solution, preferably after it is made alkaline; spraying the solution into a heated space whereby a dry powder is formed; heating the powder to at least 220 deg C in the presence of oxygen whereby the powder ignites, the sugar is converted to carbon, and the salts are decomposed by the carbon; melting the powder at between 800 and 900 deg C; and cooling the melt. (AEC) antidiuretic hormone from the blood by the liver. Data are summarized from the following: tracer studies on cardiovascular functions; the determination of serum protein-bound iodine; urinary estrogen excretion in patients with arvanced metastatic mammary carcinoma; the relationship between alheroclerosis aad lipoproteins; the physical chemistry of lipoproteins; and factors that modify the effects of densely ionizing radia

Research Organization:
Originating Research Org. not identified
NSA Number:
NSA-15-031907
Assignee:
U.S. Atomic Energy Commission
Patent Number(s):
US 3006859
OSTI ID:
4839183
Country of Publication:
United States
Language:
English

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