Combined effect of H2O2 and HCO3- on UO2(s) dissolution rates under anoxic conditions
-
Ignasi Casas
Abstract
The influence of both hydrogen peroxide (H2O2) and bicarbonate (HCO3-) on the dissolution of UO2 has been studied in this work. Two different series of experiments have been carried out using a flow-through reactor. In the first series, the influence of H2O2 concentration (between 10-6 and 5×10-4 mol dm-3) on the dissolution rate of UO2 has been studied at a fixed bicarbonate concentration of 2×10-3 mol dm-3. An increase in the dissolution rate is observed as the concentration of hydrogen peroxide increases. In the second series, the influence of bicarbonate (between 10-4 and 10-2 mol dm-3) on the dissolution rate of UO2 has been studied in the presence of a fixed hydrogen peroxide concentration (10-4 mol dm-3). The main result was that UO2 dissolution rates increased with bicarbonate concentration. From the experimental data, an oxidative dissolution model has been developed that can reproduce spent nuclear fuel dissolution rates obtained under relatively low oxygen concentrations. Under these conditions, the influence of radiolysis products, rather than O2 concentration, is expected to determine the oxidative dissolution rates of the fuel.
© by Oldenbourg Wissenschaftsverlag, München, Germany
Artikel in diesem Heft
- 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
Artikel in diesem Heft
- 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