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1.
There is a new reactor planed in your city, roughly estimate the waste composition. From the activity of Th, Pu, Am and Cm estimate the storage time.

a. Calculate the waste produced in a 4% enriched Uranium reactor.
 nuclei name Amount kg Nuclei name Amount kg Cm-244 4,76E-07 U-236 4,89679 Cm-243 6,40E-06 U-235 4,67082 Cm-242 6,63E-04 U-234 0,00475 Am-243 7,04E-07 U-233 2,42E-08 Am-242 1,04E-05 U-232 4,30E-09 Am-241 0,00182 Pa-235 6,16E-15 Pu-242 0,07055 Pa-234 2,21E-05 Pu-241 0,16922 Pa-233 1,08E-08 Pu-240 1,07851 Pa-232 3,43E-11 Pu-239 2,42359 Pa-231 1,08E-08 Pu-238 1,71E-04 Th-235 1,87E-15 Np-240 2,20E-06 Th-234 1,60E-08 Np-239 0,07566 Th-233 1,37E-13 Np-238 1,74E-04 Th-232 9,45E-08 Np-237 0,04164 Th-231 2,12E-11 U-240 8,37E-08 Th-230 3,91E-09 U-239 5,33E-04 Ac-229 5,53E-23 U-238 951,861 Ra-229 3,82E-24 U-237 0,00208 Ra-228 2,80E-18
This table shows the waste composition in Kg after one year, produced form a 4% enriched uraniums reactor with 1E14 flux.

b. How will the waste composition change after: 1 year, 10 years, 100 years and 1000 years.
 Nucei name Start amount (kg) Amount (kg) after 1 year Amount (kg) after 10 year Amount (kg) after 100 year Amount (kg) after 1000 year Cm-244 1,46E-09 1,40E-09 9,93E-10 3,17E-11 3,49E-26 Cm-243 2,01E-07 1,96E-07 1,58E-07 1,86E-08 9,22E-18 Cm-242 1,21E-04 2,58E-05 2,20E-11 4,50E-72 0,00E+00 Am-243 2,12E-11 1,10E-12 8,87E-13 1,04E-13 5,17E-23 Am-242 9,64E-07 1,48E-171 0,00E+00 0 0 Am-241 1,48E-01 1,48E-01 1,50E-01 1,37E-01 3,24E-02 Pu-242 2,67E-02 2,67E-02 0,0267 0,02669 0,02665 Pu-241 1,26E-02 1,20E-02 7,79E-03 1,01E-04 1,37E-23 Pu-240 1,03E+00 1,02841 1,02744 1,01772 0,9255 Pu-239 2,44E+00 2,44E+00 2,44E+00 2,44E+00 2,43E+00 Pu-238 1,82E-02 0,01812 0,0169 0,0083 6,82E-06 Np-240 1,39E-11 2,27E-217 0 0 0 Np-239 6,07E-05 1,43E-13 1,16E-13 1,36E-14 6,74E-24 Np-238 5,52E-07 6,92E-59 0 0 0 Np-237 1,50E-01 0,15059 0,1527 0,1733 0,27556 U-240 1,06E-30 1,01E-217 0 0 0 U-239 1,55E-05 0 0 0 0 U-238 9,52E+02 951,86 951,86 951,86 951,86 U-237 1,56E-06 3,21E-10 2,08E-10 2,70E-12 3,66E-31 U-236 4,97E+00 4,96613 4,96709 4,97662 5,06717 U-235 4,67E+00 4,67E+00 4,67E+00 4,67E+00 4,67E+00 U-234 5,90E-02 5,92E-02 6,04E-02 6,89E-02 7,70E-02 U-233 1,27E-04 1,28E-04 1,32E-04 1,73E-04 7,68E-04 U-232 6,66E-07 6,59E-07 6,02E-07 2,44E-07 2,87E-11 Pa-235 1,48E-16 0 0 0 0 Pa-234 1,66E-07 4,34E-10 4,34E-10 4,34E-10 4,34E-10 Pa-233 4,58E-08 4,57E-08 4,63E-08 5,26E-08 8,36E-08 Pa-232 4,62E-11 6,16E-95 0 0 0 Pa-231 1,57E-05 1,58E-05 1,58E-05 1,62E-05 1,99E-05 Th-235 1,48E-16 0 0 0 0 Th-234 1,40E-08 1,40E-08 1,40E-08 1,40E-08 1,40E-08 Th-233 6,08E-12 0 0 0 0 Th-232 1,37E-04 1,37E-04 1,38E-04 1,51E-04 2,83E-04 Th-231 4,32E-11 2,59E-11 2,59E-11 2,59E-11 2,59E-11 Th-230 5,89E-05 591E-05 6,06E-05 7,68E-05 2,65E-04 Ac-229 1,18E-20 0 0 0 0 Ra-229 1,18E-20 0 0 0 0 Ra-228 5,46E-14 5,46E-14 5,52E-14 6,04E-14 1,13E-13
This table shows the waste composition in Kg, produced form a power plant reactor with 1E14 flux.

c. Compare the waste from the previous reactor to a reactor using: 20% Thorium 4% 235-U and 76% 238-U as fuel.Show the activity of Th, Pu, Am and Cm after: 1 year, 10 years, 100 years and 1000 years.

This graph shows the waste composition in GBq produced form a Thorium power plant reactor (described in this exercise) with 1E14 flux.

This graph shows the waste composition in GBq produced form a 4% enriched Uranium power plant reactor with 1E14 flux.

d. You have one tonne MOX fuel with 7% plutonium and 93% Uranium.
The Plutonium used consist of
 Nuclei name Amount wt% 238-Pu 1 239-Pu 60 240-Pu 25 241-Pu 9 242-Pu 5
And the Uranium consist of
 Nuclei name Amount wt% 234-U 0,003 235-U 0,25 236-U 0,001 238-U 99,74
How much will the waste composition change with the flux?
 nuclei Name Start GBq GBq after 1 a GBq after 10 years GBq after 100 years GBq after 1000 years Cm-244 4,27E+02 4,11E+02 2,91E+02 9,30E+00 1,02E-14 Cm-243 1,86E+03 1,81E+03 1,46E+03 1,72E+02 8,54E-08 Cm-242 7,31E+06 1,56E+06 1,33E+00 2,71E-61 0,00 Am-243 3,54E+04 5,49E+00 4,33E+00 5,08E-01 2,52E-10 Am-242 1,31E+07 2,02E-158 0,00 0,00 0,00 Am-241 9,73E+03 2,95E+04 1,69E+05 3,74E+05 8,93E+04 Pu-242 1,20E+03 1,20E+03 1,20E+03 1,20E+03 1,20E+03 Pu-241 1,26E+07 1,20E+07 7,80E+06 1,01E+05 1,37E-14 Pu-240 1,15E+05 1,15E+05 1,15E+05 1,14E+05 1,04E+05 Pu-239 9,48E+01 9,65E+01 9,65E+01 9,65E+01 9,65E+01 Pu-238 1,01E+05 1,30E+05 1,28E+05 6,31E+04 5,18E+01 Np-240 9,47E+05 7,71E-183 0,00 0,00 0,00 Np-239 6,28E+08 6,25E+00 4,91E+00 5,77E-01 2,86E-10 Np-238 1,05E+05 1,32E-47 0,00 0,00 0,00 Np-237 6,04E-01 6,90E-01 3,37E+00 9,21E+01 6,05E+02 U-240 2,77E+03 2,63E-184 0,00 0,00 0,00 U-239 6,38E+08 0,00 0,00 0,00 0,00 U-238 1,14E+01 1,14E+01 1,14E+01 1,14E+01 1,14E+01 U-237 3,79E+05 2,54E+02 1,64E+02 2,13E+00 2,90E-19 U-236 7,08E-01 7,12E-01 7,42E-01 1,05E+00 3,95E+00 U-235 2,18E-02 2,18E-02 2,18E-02 2,18E-02 2,19E-02 U-234 1,02E+00 1,35E+00 4,72E+00 2,81E+01 5,05E+01 U-233 5,57E-07 3,33E-06 7,00E-05 1,75E-02 1,61E+00 U-232 4,35E-04 4,35E-04 3,98E-04 1,61E-04 1,89E-08 Pa-235 7,53E-03 0,00 0,00 0,00 0,00 Pa-234 1,03E+05 3,10E+01 3,10E+01 3,10E+01 3,10E+01 Pa-233 5,24E-01 6,90E-01 3,37E+00 9,32E+01 6,12E+02 Pa-232 9,54E-02 1,27E-85 0,00 0,00 0,00 Pa-231 3,31E-06 3,79E-06 7,94E-06 4,94E-05 4,60E-04 Th-235 7,80E-03 0,00 0,00 0,00 0,00 Th-234 1,37E+01 1,16E+01 1,16E+01 1,16E+01 1,16E+01 Th-233 1,12E-02 0,00 0,00 0,00 0,00 Th-232 2,35E-11 5,85E-11 3,81E-10 4,36E-09 1,16E-07 Th-231 2,23E-01 2,97E-02 2,97E-02 2,97E-02 2,98E-02 Th-230 2,51E-05 3,59E-05 2,89E-04 1,50E-02 4,06E-01 Ac-229 1,67E-12 0,00 0,00 0,00 0,00 Ra-229 1,81E-12 0,00 0,00 0,00 0,00 Ra-228 1,76E-12 6,25E-12 1,66E-10 3,94E-09 1,15E-07
This table shows the waste composition in GBq for waste produced from 1E14 flux reactor.
 nuclei Name Start GBq GBq after 1 a GBq after 10 years GBq after 100 years GBq after 1000 years Cm-244 1,28E-03 1,23E-03 8,71E-04 2,78E-05 3,06E-20 Cm-243 7,35E-01 7,17E-01 5,79E-01 6,80E-02 3,38E-11 Cm-242 2,08E+05 4,46E+04 3,81E-02 7,77E-63 0,00 Am-243 7,41E+00 2,15E-03 1,71E-03 2,01E-04 9,98E-14 Am-242 8,15E+05 1,25E-159 0,00 0,00 0,00 Am-241 3,69E+04 7,22E+04 3,21E+05 6,86E+05 1,64E+05 Pu-242 5,20E+02 5,20E+02 5,20E+02 5,20E+02 5,19E+02 Pu-241 2,26E+07 2,15E+07 1,39E+07 1,81E+05 2,46E-14 Pu-240 1,49E+05 1,49E+05 1,48E+05 1,47E+05 1,34E+05 Pu-239 9,36E+02 9,36E+02 9,36E+02 9,36E+02 9,35E+02 Pu-238 4,33E+05 4,31E+05 4,01E+05 1,97E+05 1,62E+02 Np-240 1,25E+03 2,04E-203 0,00 0,00 0,00 Np-239 7,31E+06 2,44E-03 1,94E-03 2,28E-04 1,13E-13 Np-238 1,19E+02 1,49E-50 0,00 0,00 0,00 Np-237 5,50E-02 2,12E-01 5,51E+00 1,69E+02 1,11E+03 U-240 7,34E-18 6,97E-205 0,00 0,00 0,00 U-239 2,69E+08 0,00 0,00 0,00 0,00 U-238 1,15E+01 1,15E+01 1,15E+01 1,15E+01 1,15E+01 U-237 7,20E+02 4,53E+02 2,94E+02 3,81E+00 5,18E-19 U-236 4,32E-02 4,76E-02 8,71E-02 4,80E-01 4,21E+00 U-235 1,82E-01 1,82E-01 1,82E-01 1,82E-01 1,83E-01 U-234 7,51E+00 8,73E+00 1,93E+01 9,22E+01 1,62E+02 U-233 5,99E-08 5,35E-07 8,93E-05 3,19E-02 2,95E+00 U-232 5,70E-06 5,72E-06 5,23E-06 2,12E-06 2,49E-10 Pa-235 2,54E-03 0,00 0,00 0,00 0,00 Pa-234 3,04E+02 3,13E+01 3,13E+01 3,13E+01 3,13E+01 Pa-233 4,52E-02 1,93E-01 5,48E+00 1,71E+02 1,12E+03 Pa-232 1,49E-03 1,99E-87 0,00 0,00 0,00 Pa-231 3,91E-06 7,76E-06 4,24E-05 3,88E-04 3,82E-03 Th-235 8,65E-03 0,00 0,00 0,00 0,00 Th-234 1,17E+01 1,17E+01 1,17E+01 1,17E+01 1,17E+01 Th-233 3,39E-04 0,00 0,00 0,00 0,00 Th-232 1,61E-12 3,85E-12 3,37E-11 1,29E-09 1,07E-07 Th-231 2,55E-01 2,48E-01 2,48E-01 2,48E-01 2,49E-01 Th-230 6,41E-05 1,39E-04 1,30E-03 5,10E-02 1,31E+00 Ac-229 1,24E-14 0,00 0,00 0,00 0,00 Ra-229 1,95E-13 0,00 0,00 0,00 0,00 Ra-228 8,34E-14 3,84E-13 1,34E-11 1,11E-09 1,05E-07
This table shows the waste composition in GBq for waste produced from 1E12 flux reactor.