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exotic nuclei structure and reaction noyaux exotiques ... - IPN - IN2P3

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G(t)<br />

R(I<br />

NoTr<br />

R(I<br />

Tr<br />

)<br />

)<br />

R(d<br />

R(d<br />

NoTr<br />

Tr<br />

t)<br />

)t<br />

T<br />

Where t is the time of the nuclear shut down [y], R<br />

the radiotoxicity of a given mass of materials [Sv/<br />

GWe], I is the total mass of fuel (core + cycle) [kg], d<br />

the annual production of waste [kg/y], “No Tr” for no<br />

transmutation <strong>and</strong> “Tr” for transmutation of minor actinides,<br />

<strong>and</strong> T the geological time of waste repository<br />

at which the comparison is made. This ratio represents<br />

the gain in terms of radiotoxicity obtained by<br />

the transmutation of minor actinides, taking into account<br />

both cumulated waste produced <strong>and</strong> materials<br />

inventory in the cycle.<br />

This comparison shows that the transmutation of minor<br />

actinides must last during centuries to be effective.<br />

This is due to the large amount of plutonium present<br />

in the core of the reactor <strong>and</strong> in the reprocessing<br />

plants, that becomes a waste when nuclear power<br />

shuts down. It should be interesting now to focus on<br />

the more efficient ways to transmute the final inventories,<br />

essentially made of plutonium or 233 U.<br />

Conclusion<br />

The MURE code is a complete tool dedicated to calculation<br />

of reactor evolution <strong>and</strong> safety parameters,<br />

which is now available at the NEA-OECD data bank.<br />

Thermo-hydraulics <strong>and</strong> neutronics coupling has been<br />

implemented for dynamical studies. MURE allows to<br />

carry out detailed neutronic studies of st<strong>and</strong>ard or<br />

innovative reactors. Using these methods a preliminary<br />

study of a Sodium Fast Reactor using U/Pu or<br />

Th/U cycles has been done.<br />

A complete tool of reprocessing <strong>and</strong> refuelling has<br />

been recently implemented. It has been used to investigate<br />

the strategy of minor actinide reprocessing<br />

in core for both U/Pu <strong>and</strong> Th/U cycles. Moreover, we<br />

have proposed a way to compare the global waste<br />

production of a given fleet at equilibrium, which takes<br />

into account the cumulated waste production <strong>and</strong> the<br />

whole material inventory that becomes a waste at the<br />

end of the nuclear fleet. This comparison shows that<br />

the impact of minor actinides transmutation is very<br />

long to become efficient (several centuries). In this<br />

context, the advantage of the thorium cycle has been<br />

quantified.<br />

119

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