All results here are gotten from the

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.
activity graph for a 20% 234-Th reactor.png

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

Teachers guide uraniums reactor Gb waste composition.JPG



























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.