Research Article
German Spent Nuclear Fuel Legacy: Characteristics and High-Level Waste Management Issues
Table 7
Dose coefficients (adult humans) for intake by ingestion and inhalation for important nuclides present in the German spent fuel legacy.
| | Transuranic elements | Fission products | | Nuclide | Dose coefficient (nSv/Bq) | | Dose coefficients (nSv/Bq) | | | Ingestion | Inhalation |
Nuclide | Ingestion | Inhalation |
| | Np-237 | 110 | 23 000 | Se-79 | 2.9 | 2.6 | | Pu-238 | 230 | 46 000 | Sr-90 | 28 | 36 | | Pu-239 | 250 | 50 000 | Zr-93 | 1.1 | 10 | | Pu-240 | 250 | 50 000 | Tc-99 | 0.64 | 4 | | Pu-241 | 4.8 | 900 | Pd-107 | 0.037 | 0.085 | | Pu-242 | 240 | 48 000 | Sn-126 | 4.7 | 28 | | Am-241 | 200 | 42 000 | I-129 | 110 | 15 | | Am-242m | 190 | 37 000 | Cs-135 | 2 | 3.1 | | Am-243 | 200 | 41 000 | Cs-137 | 13 | 9.7 | | Cm-242 | 12 | 5200 | | | | | Cm-243 | 150 | 31 000 | | | | | Cm-244 | 120 | 27 000 | | | | | Cm-245 | 210 | 42 000 | | | |
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