Evaluation of 89Sr and 90Sr yield for SrCo 3 irradiations in SM reactor neutron trap
Автор: Kuznetsov Rostislav, Tarasov Valery, Romanov Evgenii, Butkalyuk Pavel, Tselishev Ivan, Kozlov Dmitry
Журнал: Известия Самарского научного центра Российской академии наук @izvestiya-ssc
Рубрика: Физика и электроника
Статья в выпуске: 6-1 т.16, 2014 года.
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The results of numerical simulation and experimental studies of 89Sr production by irradiation of 88Sr-enrihed carbonate in a nuclear reactor are shown. 89Sr samples with specific activity of 0.5-0.6Ci/g are produced by use of 25-30 days irradiation in SM reactor neutron trap. Impurities are estimated to be of value (0.6-1.0)·10 -5% for 90Sr и (4.0-6.0)·10 -2% for 85Sr.
89sr, 90sr, high-flux reactor sm, neutron cross-sections, strontium carbonate
Короткий адрес: https://sciup.org/148203492
IDR: 148203492
