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Srinivasan, B.; Leonard, R.A.; Aase, S.
Argonne National Lab., IL (United States). Funding organisation: USDOE, Washington, DC (United States)1995
Argonne National Lab., IL (United States). Funding organisation: USDOE, Washington, DC (United States)1995
AbstractAbstract
[en] The first step in processing low-enriched uranium (LEU) targets for production of 99Mo is to dissolve the neutron-irradiated uranium foil coming from the reactor. Appropriate conditions for dissolving the foils were determined by measuring the dissolution rates for uranium foil over a wide range of temperatures and acid concentrations. On the basis of these dissolution rates, the process chemistry, and a model that integrates dissolution rates as a function of temperature and composition, a closed stainless-steel dissolver was designed, built, and tested for dissolving up to 18 g of uranium foil. The results were quite successful, with the uranium foil being dissolved within one hour as desired. To do this, the dissolver temperature must be in the range from 97 to 102 C, and the dissolver solution (cocktail) must have a composition of 3M nitric acid and 2M sulfuric acid. The final dissolver solution is subsequently processed to separate 99Mo from uranium, fission products, and other elements
Source
Sep 1995; 17 p; 18. international meeting on reduced enrichment for research and test reactors; Paris (France); 18-21 Sep 1995; CONF-9509253--10; CONTRACT W-31109-ENG-38; Also available from OSTI as DE96005010; NTIS; US Govt. Printing Office Dep
Record Type
Report
Literature Type
Conference; Numerical Data
Report Number
Country of publication
ACTINIDES, BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, DATA, DAYS LIVING RADIOISOTOPES, ELEMENTS, ENRICHED URANIUM, EVEN-ODD NUCLEI, INFORMATION, INTERMEDIATE MASS NUCLEI, ISOTOPE ENRICHED MATERIALS, ISOTOPES, MATERIALS, METALS, MOLYBDENUM ISOTOPES, NUCLEI, NUMERICAL DATA, RADIOISOTOPES, SEPARATION PROCESSES, URANIUM
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