2005
DOI: 10.1016/j.jnucmat.2005.05.010
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On the oxidation state of UO2 nuclear fuel at a burn-up of around 100MWd/kgHM

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Cited by 56 publications
(92 citation statements)
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“…From the overall PWR data (figure 3), the initiation threshold determined from EPMA measurements by Lassmann and Walker [42] was ranging from 60 to 75 GWd/MtU. However, the determination of the local burn-up in this case is not so accurate as in the HBRP samples.…”
Section: Burn-up and Temperature Threshold (Local Values)mentioning
confidence: 93%
“…From the overall PWR data (figure 3), the initiation threshold determined from EPMA measurements by Lassmann and Walker [42] was ranging from 60 to 75 GWd/MtU. However, the determination of the local burn-up in this case is not so accurate as in the HBRP samples.…”
Section: Burn-up and Temperature Threshold (Local Values)mentioning
confidence: 93%
“…Lattice parameter measurements using micro-XRD have shown that the lattice strain is highest at the radial position where nucleation of the high burn-up structure begins as would be expected if the transformation of the microstructure is initiated by radiation damage (see figure 4 of ref. [28]). EPMA has revealed that when re-crystallisation occurs nearly all the fission gas is swept out of the fuel matrix [21].…”
Section: Re-crystallisation Of Nuclear Fuel At High Burn-upmentioning
confidence: 99%
“…It can be noted that even calculation of the oxygen potential with a complete thermochemical database should also be regarded as approximate given the incomplete knowledge of FP behaviour in the UO 2 kernel. Additionally, the burn-up dependence of the oxygen potential in irradiated fuels remains today an intensely debated point in the literature (see [13,14]). For these reasons, here, the thermodynamic calculations are presented as a function of oxygen potential.…”
Section: Oxygen Potential and Particle Pressurizationmentioning
confidence: 99%
“…Recent measurements [13] have indicated that this oxygenpotential range between À325 and À350 kJ mol À1 can be potentially reached for a burn-up of 9% FIMA in PWR UO 2 fuel at 1273 K. For such low-enriched fuel, the burn-up accumulated after the third irradiation cycle mainly results from the fission of 239 Pu which is known to be a more oxidising process than the fission of 235 U. For the TRISO fuel kernel, the uranium fission is assumed to be preponderant during a longer time considering the higher initial enrichment.…”
Section: Oxygen Potential and Particle Pressurizationmentioning
confidence: 99%