COMPLETE DOCUMENT (1862 kb) - OECD Nuclear Energy Agency
COMPLETE DOCUMENT (1862 kb) - OECD Nuclear Energy Agency
COMPLETE DOCUMENT (1862 kb) - OECD Nuclear Energy Agency
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Table II.22 Masses in wastes (kg/TWhe) *<br />
ISOTOPE OPEN MIX 1 MIX 2 FAST<br />
237 Np 1.67 0.0300 0.0318 0.00806<br />
238 Pu<br />
239 Pu<br />
240 Pu<br />
241 Pu<br />
242 Pu<br />
1.12<br />
14.1<br />
6.44<br />
3.44<br />
2.54<br />
0.00684<br />
0.0329<br />
0.0462<br />
0.00903<br />
0.0139<br />
0.00656<br />
0.0159<br />
0.0372<br />
0.00706<br />
0.0140<br />
0.00299<br />
0.0857<br />
0.0573<br />
0.00713<br />
0.00536<br />
Total Pu 27.7 0.109 0.0807 0.159<br />
241 Am<br />
242m Am<br />
243 Am<br />
1.09<br />
0.00271<br />
0.550<br />
0.0508<br />
6.0×10 -4<br />
0.0553<br />
0.0520<br />
0.00285<br />
0.0588<br />
0.0330<br />
0.00188<br />
0.0158<br />
Total Am 1.65 0.107 0.114 0.0507<br />
242 Cm<br />
243 Cm<br />
244 Cm<br />
245 Cm<br />
2.63×10 -5<br />
0.00325<br />
0.220<br />
0.0198<br />
2.89×10 -5<br />
0.00220<br />
0.0557<br />
0.00282<br />
2.39×10 -5<br />
0.00174<br />
0.0535<br />
0.00271<br />
1.85×10 -5<br />
0.00159<br />
0.0236<br />
0.00128<br />
Total Cm 0.243 0.0608 0.0580 0.0264<br />
Total actinides 31 0.31 0.29 0.24<br />
Total actinides without<br />
Cm recycling<br />
31 6.3 6.0 2.9<br />
* 1 GWe-year = 8.76 TWh<br />
4.3.1.6 Conclusions<br />
Assuming industrial and economic feasibility, it would theoretically be possible to reduce<br />
substantially the output of radiotoxic heavy nuclei associated with the supply electricity from a mixed<br />
reactor park composed of LWR-UO 2 , LWR-MOX and FRs.<br />
This can be done by separating the heavy nuclei from the wastes during spent fuel<br />
reprocessing and recycling all of them (reprocessed U, Pu and MAs) to the reactor. Equilibrium between<br />
production and consumption of TRUs would theoretically require a period corresponding to at least<br />
5 complete fuel cycles. Such a scenario requires the gradual build-up of a FR generating capacity of at<br />
least 20% i.e. 20 GWe, the equivalent of about 14 EFRs of 1 450 GWe each, in a 100 GWe reactor<br />
park.<br />
The only “wastes” to be stored definitively would be the fission products and the residues due<br />
to losses in reprocessing and fuel fabrication operations. However, analyses of multi-recycling MAs<br />
show that they do not all offer the same potential for reducing the radiotoxic inventory:<br />
• Neptunium is in fact easily separable and neptunium fuels would raise no fabrication<br />
problems in homogeneous mode. However, the irradiation of neptunium leads to the<br />
formation of Pu-238 which is detrimental to reprocessing. Moreover, no significant<br />
205
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