Solid Radioactive Waste Strategy Report.pdf - UK EPR

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EPR UK N° NESH-G/2008/en/0123 REV. A PAGE 90 / 257 8.1.2.1 Radiological Characteristics After 60 Years Of Operation 8.1.2.2 Primary Circuit Contamination The expected radionuclide contamination in components arising during normal operation has been derived by the designer. This has been based on up to date operational experience from French and German reactors. The figures have been revised to reflect the advanced technical, geometrical and design features of the UK EPR. During plant operation, corrosion products can deposit on the inner surface of pipes and components, and build up as loosely bound deposits and/or a solid contamination layer. The forecasted EPR corrosion product specification is given in Table 20. TABLE 20: RADIOACTIVE DEPOSIT OF CORROSION PRODUCTS ON INNER SURFACE OF THE MAIN COOLANT LOOPS Nuclide Primary piping Hot/Cold legs (Bq/m 2 ) Steam Generators (Bq/m 2 ) Fe-59 7.0E7 to 2.0E8 5.0E7 to 1.2E8 Mn-54 2.5E8 to 4.0E8 6.5E7 to 1.3E8 Co-58 3.0E9 to 5.2E9 2.5E8 to 2.6E9 Co-60 5.0E8 to 9.8E8 2.5E8 to 5.0E8 Prior to dismantling, the primary circuit will be chemically decontaminated. The contamination will be collected on ion exchange resins. The contamination data for the primary circuit has been used for the characterisation of the waste (ion exchange resins) produced during the full decontamination of the primary circuit. The entire primary system to be decontaminated has an overall volume of about 395 m 3 and a total surface area of 15800 m 2 . The steam generators make the greatest contribution to the overall surface area (14000 m 2 ). Note: These figures exclude component replacement. Activation Activation only occurs to primary circuit components exposed to the neutron flux from the reactor core. These components are illustrated in Figure 25.
EPR UK N° NESH-G/2008/en/0123 REV. A PAGE 91 / 257 FIGURE 25: EPR COMPONENTS DESIGN – REACTOR PRESSURE VESSEL INTERNALS Purpose and Method The purpose of the assessment is to predict the extent of activation of main reactor pit components of the UK EPR. This assessment determines the waste classification ILW, LLW or VLLW for such components. The activation modelling tool used was DARWIN-PEPIN 2.1.1, which resolves the Bateman equation. This calculation code required the following input data: · Material type (concrete, steel); · Level of neutron flux (energetic repartition into 3 groups); · Power and operating history. The output data is the activation in Bq/g for each radionuclide. From this data, a waste classification level is assigned. The global activity of each waste stream is calculated by considering the associated mass of materials and components. Calculations were performed for several materials and flux levels. Complementary dose rate assessments are made to define the packaging requirements for each raw waste stream using the MERCURE 5.3 code.
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