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COMPLETE DOCUMENT (1862 kb) - OECD Nuclear Energy Agency

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As a conclusion, the SPIN studies should shed light on the type and amount of wastes<br />

produced under the various partial or complete recycling options for plutonium and minor actinides in a<br />

power reactor park, to define the technical operations to be performed, and to evaluate their cost over<br />

uncertain time frame. This leads to the emergence of new concepts, as new extractants for partitioning,<br />

or innovative systems to transmute minor actinides and long-lived fission products.<br />

3.2 Summary of current strategy studies<br />

Strategic assessment studies of P&T have been undertaken in Europe and in Japan. The<br />

Japanese study was conducted by JNC and emphasised the role of FRs and Actinide Burner reactors.<br />

An important strategy study has been undertaken under the leadership of CEA in the framework of the<br />

3rd European Union R&D programme on <strong>Nuclear</strong> Fission. This strategic assessment programme has<br />

been continued on an international basis within the European Union and expanded during the current<br />

R&D programme (1994-1998). These studies are summarised below.<br />

3.2.1 European Union strategy study [77,160]<br />

3.2.1.1 Reference and P&T scenario<br />

Reference scenarios with and without conventional reprocessing, and scenarios using P&T are<br />

compared to assess their possibilities.<br />

The three reference scenarios are considered:<br />

• the Rl scenario covers the period from 2000 to 2100. The reactor population consists of<br />

PWRs supplied with UO 2 fuel at 4% 235 U enrichment and reaching a mean burn-up of<br />

47.5 GWd/tHM. The installed capacity is 120 GWe, i.e. 80 reactors, with an annual<br />

electrical production of 740 TWh (roughly the present installed generating capacity in the<br />

European Union). The fuel cycle is open without reprocessing.<br />

• scenarios R2 and R3 both include a plutonium recycling strategy but in different types of<br />

reactors. In the R2 scenario, plutonium is recycled as MOX fuel in PWRs. The fuel cycle<br />

is closed by PUREX reprocessing with the losses of 0.3% for U and 0.5% for Pu. In the<br />

R3 scenario it is recycled in fast reactors(FRs: 1 500 MWe) and the losses during FR fuel<br />

reprocessing are 0.9% for U and 0.25% for Pu. Recycling in PWRs is assumed to be<br />

applicable from the outset of the scenario (in the year 2000) while recycling in FRs is<br />

assumed not to begin before 2020, considering the lack of industrial maturity in this<br />

solution. The two scenarios therefore differ only after 2020.<br />

Three scenarios are considered for partitioning and transmutation, two with available<br />

technologies, RP1-1 and RP1-2, and one with very advanced technologies, RP2:<br />

• the RP1-1 scenario is compared with the R2 scenario. The transmutation of Np and Am<br />

starts from 2010 in PWRs in homogeneous or in heterogeneous mode. In homogeneous<br />

mode, neptunium or americium oxide is mixed with the UO 2 fuel to the extent of 1%. The<br />

losses during reprocessing are 0.3% for U, 0.5% for Pu, 5% for Np and Am and 100% for<br />

(Cm).<br />

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