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Benker, D.E.; Bigelow, J.E.; Bond, W.D.
Oak Ridge National Lab., TN (USA)1986
Oak Ridge National Lab., TN (USA)1986
AbstractAbstract
[en] High-burnup mixed oxide fuel pins from the Fast-Flux Test Facility (FFTF) reactor were sheared in a single-pin shear, dissolved in nitric acid, and then used in solvent extraction tests to assist in establishing operating parameters for fuel recycle facilities. The fuel burnups were 2, 36, 55, and 90 MWd/kg for initial cooling times of 2.5, 1.3, 1, and 1 year, respectively. These tests include the first experiments using fuel of approximately the reference burnup (80-MWd/kg peak burnup) irradiated under reference conditions. The FFTF is a sodium-cooled reactor with stainless steel-clad fuel; the oxide fuel, which is of two compositions, has Pu/(U + Pu) ratios of approx.0.225 and 0.275. The peak fuel center temperature was about 16400C, the peak internal cladding temperature was approx.5300C, the peak heat rating was approx.300 W/cm, and the peak fluence (E > 0.1 MeV) was approx.15.7 x 1022 neutrons/cm2
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1986; 9 p; 4. European nuclear conference and 9. FORATOM congress (ENC '86) and international nuclear trade fair; Geneva (Switzerland); 1-6 Jun 1986; Available from NTIS, PC A02/MF A01 as DE86006213
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Report
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Conference
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COORDINATED RESEARCH PROGRAMS, ENERGY SOURCES, EPITHERMAL REACTORS, FAST REACTORS, FUEL ELEMENTS, FUELS, HYDROGEN COMPOUNDS, INORGANIC ACIDS, INORGANIC COMPOUNDS, LIQUID METAL COOLED REACTORS, MATERIALS, NITROGEN COMPOUNDS, NUCLEAR FUELS, OXYGEN COMPOUNDS, REACTOR COMPONENTS, REACTOR MATERIALS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH PROGRAMS, RESEARCH REACTORS, SEPARATION PROCESSES, SODIUM COOLED REACTORS, SOLID FUELS, TEST FACILITIES, TEST REACTORS
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