The effects of alpha-radiolysis on UO2 dissolution determined from electrochemical experiments with 238Pu-doped UO2
- 1. Atomic Energy of Canada Ltd., Whiteshell Labs., Pinawa, MB (Canada)
- 2. Integrity Corrosion Consulting, Ltd., Calgary, AB (Canada)
- 3. Ontario Power Generation, Toronto, ON (Canada)
Description
The long-term stability of spent nuclear fuel under deep geologic repository conditions will be determined mostly by the influence of α-radiolysis, since the dose-rate for α-radiolysis will exceed that for γ/β-radiolysis beyond a fuel age of ∝ 100 years and will persist for more than 10 000 years. Dissolution rates derived from studies with currently available spent fuel include radiolysis effects from γ/β- as well as α-radiolysis. The use of external α-sources and chemically added H2O2 in UO2 studies has provided much information on the basic chemistry/electrochemistry of α-radiolysis effects on UO2 fuel dissolution. Here, alpha-radiolysis effects were measured directly by performing electrochemical experiments with α-doped UO2. The 238Pu-doped UO2 pellets, produced by milling, pressing and sintering, had activities of approximately 0.01 and 0.1 Ci/g. Discs cut from these pellets were fabricated into electrodes. Corrosion potentials (Ecorr) were measured for these electrodes, in glass cells containing deaerated 0.1 M NaClO4 (pH 9.5) for periods up to 1600 h. The effects of carbonate and Fe(II) on Ecorr values were also investigated. Preliminary results showed that Ecorr values correlated with doping levels, and were slightly higher than Ecorr values obtained with UO2 electrodes in the presence of external α-sources. The presence of carbonate reduced Ecorr values considerably. Addition of Fe(II) caused generally small reductions in Ecorr values, suggesting that Fe(II) affects the dissolution process, either by scavenging radiolytic oxidants, reducing oxidized surface states, or reducing dissolved U(VI). These effects were often transient due to depletion of the added Fe(II). Accurate dissolution rates could not be determined from measured solution and surface concentrations because of material entering the solutions during the electroreduction procedure, probably due to the dissolution of fines present on the electrode surface after polishing. Experiments are continuing in order to confirm the preliminary findings, with greater attention being paid to determining accurate dissolution rates. (orig.)
Additional details
Publishing Information
- Journal Title
- Radiochimica Acta
- Journal Volume
- 90
- Journal Issue
- 9-11
- Journal Page Range
- p. 603-609
- ISSN
- 0033-8230
- CODEN
- RAACAP
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 34011153
- Subject category
- S38: RADIATION CHEMISTRY, RADIOCHEMISTRY AND NUCLEAR CHEMISTRY; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Descriptors DEI
- ALPHA PARTICLES; CORROSION; DISSOLUTION; DOPED MATERIALS; ELECTROCHEMISTRY; HYDROGEN PEROXIDE; IRON IONS; PLUTONIUM 238; RADIOACTIVE WASTE DISPOSAL; RADIOLYSIS; SPENT FUELS; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; CHALCOGENIDES; CHARGED PARTICLES; CHEMICAL RADIATION EFFECTS; CHEMICAL REACTIONS; CHEMISTRY; DECOMPOSITION; ENERGY SOURCES; EVEN-EVEN NUCLEI; FUELS; HEAVY ION DECAY RADIOISOTOPES; HEAVY NUCLEI; HYDROGEN COMPOUNDS; IONIZING RADIATIONS; IONS; ISOTOPES; MANAGEMENT; MATERIALS; NUCLEAR FUELS; NUCLEI; OXIDES; OXYGEN COMPOUNDS; PEROXIDES; PLUTONIUM ISOTOPES; RADIATION EFFECTS; RADIATIONS; RADIOACTIVE WASTE MANAGEMENT; RADIOISOTOPES; REACTOR MATERIALS; SILICON 32 DECAY RADIOISOTOPES; SPONTANEOUS FISSION RADIOISOTOPES; URANIUM COMPOUNDS; URANIUM OXIDES; WASTE DISPOSAL; WASTE MANAGEMENT; YEARS LIVING RADIOISOTOPES