Assessing Type of Fuel Damage at Fukushima Daiichi Nuclear Facility
| Average of turbine hall water samples | Expected release by event (% of total nuclide) | |||
| Radionuclide | Activity concentration (Bq/mL) | % of total nuclide | Fuel overheat | Fuel melt |
| 131I | 4.8E+6 | 65 | 40 | 30 |
| 134Cs | 8.5E+5 | 11 | 31 | 23 |
| 136Cs | 9.7E+4 | 1.3 | 4 | 3 |
| 137Cs | 1.4E+6 | 19 | 18 | 14 |
| 140Ba | 1.8E+5 | 2.4 | 2 | 17 |