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COMPLETE DOCUMENT (1862 kb) - OECD Nuclear Energy Agency

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Figure II.30 Overview of the canister<br />

The steel insert is cast with thick steel walls between fuel assemblies. This gives a good<br />

mechanical stability besides providing adequate protection against criticality in the unlikely event that<br />

the canister at some unspecified future time should be filled with water.<br />

The fabrication of copper canisters of the size needed is by no means an industrially available<br />

technology. The seal welding technology has been demonstrated on a laboratory scale in work sponsored<br />

by SKB at The Welding Institute in UK. Full-size canisters have also been fabricated on a trial scale. In<br />

order to develop the key technology, SKB operates a laboratory for encapsulation technology at<br />

Oskarshamn. This laboratory will be ready in 1998 and will primarily be devoted to further<br />

development of the seal-welding process and of the NDE-methods.<br />

4.5.1.3 Performance assessment of spent fuel disposal in clay [190]<br />

Taking into account the uncertainty about the choice of reprocessing as a fuel cycle step, a<br />

study was recently (1996) undertaken by the nuclear sector in Belgium to determine the impact of<br />

5000 tHM spent fuel (consisting of a mixture of UO 2 and MOX fuel with burn-ups ranging from 33<br />

to 45 GWd/tHM) on the Boom Clay repository environment (see next paragraphs describing the RFC<br />

scenarios) in Belgium. The result of the calculation shows that 129 I is the most important contaminant<br />

giving rise to about 10 µSv/year from 20 000 to 200 000 years after disposal. The actinide dose is<br />

several orders of magnitude below that figure during this period (see Figure II.31), and crosses the 237 Np<br />

curve at around 3 000 000 years. Beyond that “geologic” period the decay products of U and Np<br />

become predominant. The very long-term dose on a geological time scale is determined by 226 Ra and<br />

231 Pa. This dose is of the same order of magnitude as the initial 129 I dose, i.e. 10 µSv/year. As a<br />

conclusion, 129 I dominates the dose rate between 10 000 and 2 000 000 years; later, the actinides and<br />

their decay products determine the ultimate dose.<br />

224

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