Solid Radioactive Waste Strategy Report.pdf - UK EPR

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EPR UK N° NESH-G/2008/en/0123 REV. A PAGE 108 / 257 Na Nature of waste stream: TABLE 30: ION EXCHANGE RESINS PROCESSING Raw waste volume: 30 to 40 m 3 Ion-exchange resin used for decontamination of the primary circuit (full system decontamination) Proposed matrix: Polymer matrix (epoxy) Package type: NDA specification 500L Solids Drum (V=0.5 m 3 ) Raw waste per package: About 150 kg Waste form density: 1500 kg/m 3 Waste package mass: 750 kg Number of packages: About 370 Physical/chemical composition: The waste in an average package is expected to comprise: · 20% of resin · 80% of polymer matrix – Reference date: At reactor dismantling (year 61) External gamma dose rates: At 1m: < 0.1 mSv/h. At contact: < 2 mSv/h. With a 285 mm steel shielding transport container as indicated in NIREX report N/104.
EPR UK N° NESH-G/2008/en/0123 REV. A PAGE 109 / 257 8.1.6.2 Activated ILW Metallic and concrete wastes from the dismantling of the activated components near the reactor core are solid wastes on the basis of the guidance given in NDA report N/104. Assuming that these wastes are transported from the place of interim storage to the phased geological disposal facility in year 100 and considering their radiological characterisation at this date the waste packaging scenario is as follows: · The shielded 4 metre boxes were developed for packaging wastes arising from the dismantling of nuclear facilities. This freight container type package incorporates concrete liner shielding that can have various thicknesses adapted to the activity level of the wastes. Based on the maximum gross mass of 64t for such a package, with the estimated activation of the components and the requirements in terms of dose rate at contact (2mSv/h) and at 1 metre (0,1mSv/h) from this transport container, this kind of container is not suitable for all of the ILW produced during the dismantling of an EPR. The shielding required for the containment of the core shells of the reactor vessel is of the order of 100mm thick. The other metallic ILW resulting from the dismantling of the reactor (Neutron shield, internals) are not compatible with this kind of package. For concrete waste use of 4 metre boxes without additional shielding is possible. The characteristics of this conditioned waste are given in Table 31. FIGURE 29: 4M 3 BOX · The 3 cubic metre boxes potentially incorporating additional shielding will be used for ILW (Neutron shield and most of the reactor vessel internals) that is not suitable for packaging in 4m boxes. In addition, this packaged waste will required the use of a transport container (of the type Standard Waste Package Container mentioned in the report N/104) providing an additional shielding of 285mm of steel. The characteristics of this conditioned waste are given in Table 32.
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A 2008-11-26 Sarah Greenwood Gary C
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