MOX@EON: EON Operational Experience - US Nuclear Waste ...
MOX@EON: EON Operational Experience - US Nuclear Waste ...
MOX@EON: EON Operational Experience - US Nuclear Waste ...
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Practical Aspects of MOX - Handling (2): Fuel-Rod-<br />
Design<br />
• heat-conductivity lower<br />
• Pufiss-distribution inhomogenous<br />
compared to U-235 nuclei in U-Matrix:<br />
>60% proportion of fissile nuclei in<br />
PuO microcrystal vs 5% proportion of<br />
fissile nuclei in UO2 microcrystal<br />
• more reactivity and power at higher<br />
bup (reflecting k inf (burnup))<br />
• higher fuel temperature<br />
• more fission gas release<br />
• KWU-plants: generally additional<br />
lower fuel-rod-plenum!<br />
Fuel thermal conductivity [W/(m K)]<br />
6<br />
5<br />
4<br />
3<br />
2<br />
UO2 and MOX fuel thermal conductivity (95% TD)<br />
UO2, B=0 MWd/kg(HM)<br />
UO2, B=10 MWd/kg(HM)<br />
UO2, B=30 MWd/kg(HM)<br />
UO2, B=50 MWd/kg(HM)<br />
UO2, B=80 MWd/kg(HM)<br />
MOX, B=0 MWd/kg(HM)<br />
MOX, B=10 MWd/kg(HM)<br />
MOX, B=30 MWd/kg(HM)<br />
MOX, B=50 MWd/kg(HM)<br />
MOX, B=80 MWd/kg(HM)<br />
1<br />
0 500 1000 1500 2000 2500 3000<br />
Temperature [°C]<br />
17
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