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Download Issues in the use of Weapons-Grade MOX Fuel in VVER-1000 by J J Carbajo; Oak Ridge National Laboratory. .; United PDF

By J J Carbajo; Oak Ridge National Laboratory. .; United States. Dept. of Energy.; United States. Dept. of Energy. Office of Scientific and Technical Information

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Extra resources for Issues in the use of Weapons-Grade MOX Fuel in VVER-1000 Nuclear Reactors : Comparison of UO2 and MOX Fuels

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2. The specific power density for either fuel was taken as 42 W/g. Previous calculations (both Russian and by ORNL) have been reported in Refs. 3 and 4. 3. Decay heats are given in watts per kilogram (W/kg) of heavy metal for the two main classes of contributors: actinides and fission products (FPs). MOX fuel has a larger actinide contribution and a lower fission product contribution than UO2 fuel. For the same burnup level, the total decay heat of MOX fuel is lower than UO2 fuel during the first day after shutdown, but after one day, MOX decay heat is larger than UO2 fuel.

Source terms for fresh fuel (MOX and UO2) are also different, with a larger source term and possible larger doses for MOX fuel. This is covered in Sect. 9. 4 SUMMARY AND CONCLUSIONS Spent MOX and UO2 fuels have different source terms, with larger MOX actinides and iodine inventories than UO2 fuel. MOX fuel may also have larger gap releases than UO2 fuel that may result in larger pressures inside the gap. This has implications in severe accident and dose calculations, with larger potential consequences and doses for accidents with MOX fuel.

Because of the neutron spectrum differences, the gadolinium burns out more slowly in the MOX assembly, therefore, it is typical to use lower gadolinium loadings in the MOX assembly. 3 NEUTRON FLUX SPECTRUM Because the thermal cross sections are larger for plutonium than for uranium, the thermal flux in the MOX assemblies is significantly lower than that of the UO2 assemblies. 2 shows values of the thermal flux, fast flux, and flux ratios for typical MOX and UO2 assemblies. 2 Comparison of the thermal and fast neutron fluxes in MOX and UO2 fuel assemblies.

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