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