Solid Radioactive Waste Strategy Report.pdf - UK EPR

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EPR UK N° NESH-G/2008/en/0123 REV. A PAGE 96 / 257 o The remainder is VLLW. These concrete thicknesses lead to the following volume and mass of waste (density 2.35 g/cm3): TABLE 23: VOLUME MASS OF WASTE ILW concrete LLW concrete 5 years after shutdown 77 m 3 / 180 te 205 m 3 / 483 te 40 years after shutdown none 112 m 3 / 264 te No account has been taken in the modelling of the effect of steel reinforcement or concrete impurities. Dose Rate Calculations Calculation Assumptions Dose rate calculations inform the selection of the type of packaging that can be used for each raw activated waste. Calculations take into account: · Geometry of each package type: The 3 m 3 and 4 m boxes are assessed to be suitable for packaging these wastes at year 100 based on transport dose rate limits; · The waste packing density within the packages is assumed to be about 3 te/m 3 (based on 13% steel and 87% concrete). The bulk density of the raw waste is estimated to be 1 te/m 3 . Dose rates have been calculated for several source intensities, in order to define the specific activity limit for 60 Co (The dominant contributor to external package dose rates) that would satisfy the transport dose rate criteria (contact dose rate < 2mSv/hr and 1m dose rate < 0.1mSv/hr). Results The most activated wastes These wastes are derived from dismantling of the neutron shield and the lower support plate.
EPR UK N° NESH-G/2008/en/0123 REV. A PAGE 97 / 257 TABLE 24: SPECIFIC ACTIVITIES OF WASTE PACKAGES FOR MOST ACTIVATED WASTES Packaging Maximum specific activity ( 60 Co) allowable with respect to transport dose rate criteria Specific activity ( 60 Co) of this packed waste 3-cubic metre box within a SWTC 285 transport container 3-cubic metre box with an additional 100 mm internal steel shielding, and a SWTC 285 transport container 1E+8 Bq/g of raw waste 5E+9 Bq/g of raw waste ~2.1E+7 Bq/g of raw waste 40 years after shutdown ~2.1E+9 Bq/g of raw waste 5 years after shutdown The typical activated wastes These wastes are derived from the dismantling of the core barrel, the upper core plate, the flow distribution device and the upper support columns. TABLE 25: SPECIFIC ACTIVITIES OF WASTE PACKAGES FOR TYPICAL ACTIVATED WASTES Packaging Maximum specific activity ( 60 Co) allowable with respect to transport dose rate criteria Specific activity ( 60 Co) of this packed waste 3-cubic metre box with a SWTC 285 transport container 3-cubic metre box with an additional 100 mm internal steel shielding, and a SWTC 285 transport container 1E+8 Bq/g of raw waste 5E+9 Bq/g of raw waste ~1E+6 Bq/g of raw waste 40 years after shutdown ~3.6E+8 Bq/g of raw waste 5 years after shutdown The least activated wastes These wastes are derived from the reactor pressure vessel and the sections of the reactor pressure vessel cladding near the centre point of the fuel assemblies (The upper and lower sections will be LLW). TABLE 26: SPECIFIC ACTIVITIES OF WASTE PACKAGES FOR LEAST ACTIVATED WASTES Packaging Maximum specific activity ( 60 Co) allowable with respect to transport criteria Specific activity ( 60 Co) of this packed waste 4-metre box with an additional 100 mm internal concrete shielding 4-metre box with an additional 400 mm internal concrete shielding 7E+3 Bq/g of raw waste 3E+5 Bq/g of raw waste ~2.8E+3 of raw waste 40 years after shutdown ~2.8E+5 Bq/g of raw waste 5 years after shutdown
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