Solid Radioactive Waste Strategy Report.pdf - UK EPR

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EPR UK N° NESH-G/2008/en/0123 REV. A PAGE 94 / 257 TABLE 22: COMPOSITION OF CONCRETE USED IN CALCULATIONS Element % by weight Na 1.7 Mg 2.3 Al 6.8 Si 25.1 P 0.1 K 1.9 Ca 7.1 Ti 0.5 Mn 0.05 Fe 4.5 S 0.2 Ga 0.002 Ba 0.04 B 0.001 O 47.9 C 0.07 H 0.67 Sum 99 % Rest: not significant trace elements For concrete, site specific evaluations would have to be performed, considering the actual composition for that particular site. Level of Neutron Flux For this assessment EPR design neutron flux data have been used: in particular, the assessment of the impact of the neutron propagation study outside of the core. Note: · No loading factor has been considered (100% nominal power has been assumed for all operations); · The maximum flux level has been assumed to apply evenly to all areas of a component. In particular no flux axial distribution has been modelled, the axial midpoint flux has been conservatively assumed to apply to the entire length of each component; · The worst radial propagation has been chosen: azimuth distortion of the core effect can lead to factor 3 or 4 between maximum and minimum level flux at one axial position. Consequently, the activation calculations have produced highly conservative estimates for radionuclide inventories. However, it will be very difficult to derive a good average for some input parameters. This would require a more specific neutron propagation study to be carried out.
EPR UK N° NESH-G/2008/en/0123 REV. A PAGE 95 / 257 Power and Operating History This EPR operating programme assumed for the activation calculations is as follows: · 38 operating fuel cycles of 18 months (100% nominal power) followed by plant shutdown of 16 days; · A longer plant shutdown is considered every 10 years (40 days); · The total operating time is 60 years; · The thermal power is 4500 MWth. Activation Results Steels Based on the results of the activation calculations, steels have been grouped into three families of ILW dependent on activity levels: · The most activated: o Neutron shield and lower support plate; o Specific activity associated with 60 Co ~ 2.1E+9 Bq/g for raw waste 5 years 3 after shutdown. · The intermediate activated: o o Core barrel, upper core plate, flow distribution device and upper support columns (which are located under the upper support plate); Specific activity associated with 60 Co ~ 3.6E+8 Bq/g for raw waste 5 years after shutdown. · The less activated: o o Pressure vessel + cladding (in the active region of the fuel assemblies); Specific activity with 60 Co ~ 2.8E+5 Bq/g for raw waste 5 years after shutdown. All other internal structures, namely the upper support columns (above upper support plate), the upper support plate, the upper support assembly, the pressure vessel (upper and lower fuel assemblies) and vessel cladding (upper and lower fuel assemblies) will be classified as LLW at the time of production. Concrete It is predicted that the following categories of waste will be generated for the reactor pit: · 5 years after shutdown: o o o 60 cm depth of concrete is ILW; Then 90 cm depth is LLW; The remainder is VLLW. · 40 years after shutdown: o 80 cm depth is LLW; 3 Based on 60 years of electricity production for an EPR followed by an assumption of immediate dismantling of a single reactor, the ILW resins (from primary circuit decontamination) are produced in year 61 and ILW solid dismantling wastes between years 67 and 70. Therefore, 5 years after shutdown has been chosen to evaluate conservative radiological characteristics.
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