Leaching of 53 MW/d kg U spent nuclear fuel in a flow-through reactor
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Daniel Serrano-Purroy
Abstract
The dissolution behaviour of powdered commercial spent fuel (UO2 with burn-up of 53 MW/d kg U) has been studied in a carbonate-containing solution ([HCO3-] =0.001 mol dm-3) by using a flow-through reactor specially designed for the use in a hot cell. This method allows studying spent fuel dissolution while avoiding the parallel process of secondary solid phase formation. The dissolution behaviour of U, Np, Pu, Sr and Cs was studied. The main trend of the results obtained in this work is that only neptunium releases congruently with uranium (FIAPNp/FIAPU=1.21±0.01) because both strontium and caesium have higher FIAP values (FIAPSr/FIAPU=2.3±0.8; FIAPCs/FIAPU=5±1) and plutonium lower (FIAPPu/FIAPU=0.07±0.02). The FIAP value for uranium at the steady-state is 4(±2)×10-4.
© by Oldenbourg Wissenschaftsverlag, München, Germany
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Articles in the same Issue
- Proton induced reactions on 89Y with particular reference to the production of the medically interesting radionuclide 89Zr
- Recovery of U and Pu from simulated spent nuclear fuel by adducts of organic reagents with HNO3 followed by their separation from fission products by countercurrent chromatography
- New chemical sensors based on extraction systems for stable fission products analysis
- Combined effect of H2O2 and HCO3- on UO2(s) dissolution rates under anoxic conditions
- Leaching of 53 MW/d kg U spent nuclear fuel in a flow-through reactor
- Investigation of the radiolytic stability of a CyMe4-BTBP based SANEX solvent
- Separation of no-carrier-added arsenic-77 from neutron irradiated germanium
- Comparative studies of S-bridged complexes of 99mTc with fac(S)-[M(aet)3] (M=RhIII, IrIII; aet=2-aminoethanethiolate)
- Characterization of pottery from Cerro de Las Ventanas, Zacatecas, México
- Radiation chemical effects on radiochemistry: A review of examples important to nuclear power
