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Solubility and dissolution behavior of /sup 90/SrF/sub 2/ in aqueous media

Technical Report ·
DOI:https://doi.org/10.2172/7235763· OSTI ID:7235763
A significant fraction of the heat generated by the discharged fuel from nuclear reactors results from the radioactive decay of the fission product /sup 90/Sr. Because of its relative abundance, moderately long halflife (T/sub /sup 1///sub 2// = 28.6 yr), and heat output (0.93 W/g) the /sup 90/Sr is a candidate fuel for radioisotope power generation systems in terrestrial applications. To date, terrestrial applications for /sup 90/Sr have used strontium titanate (SrTiO/sub 3/) or strontium orthotitanate (Sr/sub 2/TiO/sub 4/) as the fuel form. At Hanford strontium is recovered from the high-level waste generated in the fuel reprocessing operation and consists of a mixture of the desired radioactive isotope /sup 90/Sr and stable strontium isotopes. Freshly discharged reactor fuel also contains the radioactive isotopes /sup 89/Sr (T/sub /sup 1///sub 2// = 50.5 days) and /sup 91/Sr (T/sub /sup 1///sub 2// = 9.48 hr), but these isotopes have usually decayed to very low levels by the time the strontium is recovered from the fuel reprocessing wastes. The /sup 90/Sr isotopic content of the strontium will depend on the age of the wastes from which the strontium is recovered. A typical isotopic analysis of strontium recovered from recent Hanford wastes is given.
Research Organization:
Battelle Pacific Northwest Labs., Richland, Wash. (USA)
DOE Contract Number:
E(45-1)-1830
OSTI ID:
7235763
Report Number(s):
BNWL-2101
Country of Publication:
United States
Language:
English