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chemical properties, which can be managed in a safer way for long term intermediate<br />

storage or disposal (e.g. americium and curium).<br />

A proper conditioning, resulting in a reduction of the solubility, is the<br />

most obvious approach. Incorporation into a stable matrix reduces the<br />

migration risk of accidental dispersion during the storage period and migration<br />

in the repository.<br />

However, major changes in the safety situation will arise in a P&T fuel<br />

cycle, due to the transition to new fuels, which are generally much more<br />

radioactive both before and after irradiation, with higher levels of residual heat<br />

and helium production resulting from intense alpha activity.<br />

Transmutation requires new fuel fabrication plants and irradiation<br />

technologies, which must be developed and implemented on an industrial scale.<br />

Existing nuclear power plants could in principle be used for transmutation, but<br />

many practical obstacles may arise (e.g. interference with the daily operation of<br />

the plants). New irradiation facilities such as dedicated FRs, accelerator driven<br />

transmutation devices and even fusion reactors have been proposed for transmutation–incineration<br />

purposes.<br />

One of the main objectives of P&T has always been to reduce the long<br />

term hazard of spent fuel or HLW, this hazard being associated with the<br />

radioactive source term itself. In contrast, in the management of waste the long<br />

term radiological risk is stressed; this long term radiological risk is a<br />

combination of the potential hazard and the confining properties of the<br />

geologic media. The measures that have to be taken for hazard reduction are<br />

very different and much more fundamental than those for risk reduction.<br />

For a desired reduction factor in total radiotoxicity of 1000, a target value<br />

of 99.9% has to be achieved for the recovery of each of the individual TRUs<br />

during the reprocessing–partitioning operations. With a 100-fold reduction in<br />

the TRU content the reduction in radiotoxicity could theoretically be reached<br />

after less than 1000 years.<br />

It is obvious that a 100-fold reduction of the TRU mass in the waste<br />

compared with the OTC cannot be achieved in a single pass through a reactor.<br />

Multiple recycling will hence be necessary. In fact, the ideal P&T system should<br />

have a fuel cycle that is fully closed for the TRUs. Only the fission products<br />

would enter the waste stream, together with a 0.1% fraction of the cumulated<br />

and/or recycled TRU fraction. Given the limitations of irradiation facilities,<br />

such a system must be operated for many decades before equilibrium is<br />

reached in the core composition and in the radiotoxic output of the TRU losses.<br />

11

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