Head-end and solvent extraction studies using fast-flux test facility fuel

Conference · Wed Jan 01 04:00:00 EST 1986

OSTI ID:5916155

Benker, D E; Bigelow, J E; Bond, W D; Campbell, D O; Chattin, F R; Crouse, D J; Fellows, R L; King, L J; Kitts, F G; Mailen, J C

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 1640/sup 0/C, the peak internal cladding temperature was approx.530/sup 0/C, the peak heat rating was approx.300 W/cm, and the peak fluence (E > 0.1 MeV) was approx.15.7 x 10/sup 22/ neutrons/cm/sup 2/.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5916155
• Report Number(s): CONF-860603-1; ON: DE86006213
• Country of Publication: United States
• Language: English

Related Subjects

050800* -- Nuclear Fuels-- Spent Fuels Reprocessing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
BURNUP
CONSOLIDATED FUEL REPROCESSING PROGRAM
COORDINATED RESEARCH PROGRAMS
DISSOLUTION
EPITHERMAL REACTORS
EXTRACTION
FAST REACTORS
FFTF REACTOR
FUEL ELEMENTS
FUEL PINS
FUELS
HEAD END PROCESSES
HYDROGEN COMPOUNDS
INORGANIC ACIDS
LIQUID METAL COOLED REACTORS
MIXED OXIDE FUELS
NITRIC ACID
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH PROGRAMS
RESEARCH REACTORS
SEPARATION PROCESSES
SODIUM COOLED REACTORS
SOLID FUELS
SOLVENT EXTRACTION
TEST REACTORS