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Solid Radioactive Waste Strategy Report.pdf - UK EPR

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<strong>EPR</strong> <strong>UK</strong><br />

N° NESH-G/2008/en/0123<br />

REV. A PAGE 106 / 257<br />

Raw waste production<br />

1800<br />

1600<br />

1400<br />

Mass (t)<br />

1200<br />

1000<br />

800<br />

600<br />

ILW<br />

LLW<br />

VLLW<br />

400<br />

200<br />

0<br />

61 66 71<br />

Years<br />

FIGURE 27: RAW WASTE PRODUCTION AGAINST TIME<br />

8.1.6 <strong>Waste</strong> processing<br />

8.1.6.1 ILW<br />

8.1.6.1.1 Contaminated ILW<br />

This consists of the Ion-Exchange Resins used during the full decontamination of the primary<br />

circuit.<br />

Ion exchange resins will be encapsulated in a solid matrix which is in direct contact with the<br />

waste container. Based on the NIREX report N/104, the container proposed for this waste is the<br />

unshielded waste package “500 litre <strong>Solid</strong>s Drum”.<br />

A transport container providing an additional shielding not bigger than 285 mm of steel is then<br />

required for transport and waste handling in the proposed deep geological disposal facility.<br />

Ion-exchange resins can be dewatered or immobilised in a polymer matrix (epoxy) inside this<br />

container.<br />

Epoxy resins is usually mixed into a container pre-equipped with a stirring device. Epoxy matrix<br />

enables a greater quantity of ion exchange resin to be immobilised in the matrix than cement<br />

mortar. Note that if the waste containment can be assured by the container itself, no additives<br />

need be considered.

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