1. Scorie Nucleari Adriano Duatti Laboratorio di MedicinaNucleare, Departimento di Scienze C/A e Radiologiche, Università di Ferrara, Via L. Borsari, 46, 44100 Ferrara, Italy (email: dta@unife.it)

2. Sources of waste

3. Classification of radioactive wastes

4. Low-level Waste

5. Intermediate-level Waste

6. High-level Waste

7. Radioactive medical source

8. Other low-level sources

9. The Nuclear Fuel Cycle

11. Fuel Production

12. Uraninite (Pitchblende) Yellowcake U3O8U3O8 UO 2 Uranium fuel

13. Fuel rods (UO 2 ) UF 6 Uranium fuel

14. Reaction in standard UO 2 fuel

15. Fission product yields by mass for thermal neutron fission of U-235, Pu-239, and U-233 used in the thorium cycle Fission products

17. NuclideT 1/2, yYield,%E, keV  155 Eu4.760.0803252  58 Kr10.760.2180687  113m Cd14.10.0008316  90 Sr28.94.5052826  137 Cs30.236.3371176  121m Sn43.90.00005390  151 Sm900.531477  Medium-lived fission products

18. NuclideT 1/2, MyYield,%E, keV  99m Tc0.2116.1385294  126 Sn0.2300.10844050  79 Se0.2950.0447151  93 Zr1.535.457591  135 Cs2. 36.9110269  107 Pd6.51.249933  129 I15.70.8410194  Long-lived fission products

19. ‘Front End’ Waste

20. ‘Back End’ Waste

21. Annual operation of a 1000 MWe nuclear power reactor A typical reactor generates about 27 tonnes of spent fuel or 3 m 3 per year of vitrified waste

22. Decay in radioactivity of fission fuel in one tonne of spent fuel

23. Storage in ponds at reactor sites There are about 270,000 tonnes of used fuel in storage, much of it at reactor sites. About 90% of this is in storage ponds, the balance in dry storage. Annual arisings of used fuel are about 12,000 tonnes, and 3,000 tonnes of this goes for reprocessing. Final disposal is not urgent in any logistical sense

24. Waste Management in the Nuclear Fuel Cycle

25. Waste Management in the Nuclear Fuel Cycle: LLW and ILW

26. Waste Management in the Nuclear Fuel Cycle: LLW Incineration

27. Waste Management in the Nuclear Fuel Cycle: ILW Compaction and Cementation Compaction Cementation

28. Near-surface disposal facilities at ground level. These facilities are on or below the surface where the protective covering is of the order of a few metres thick. Waste containers are placed in constructed vaults and when full the vaults are backfilled. Eventually they will be covered and capped with an impermeable membrane and topsoil. These facilities may incorporate some form of drainage and possibly a gas venting system. Near-surface disposal facilities in caverns below ground level. Unlike near-surface disposal at ground level where the excavations are conducted from the surface, shallow disposal requires underground excavation of caverns but the facility is at a depth of several tens of metres below the Earth's surface and accessed through a drift. Waste Management in the Nuclear Fuel Cycle: LLW Disposal

29. Waste Management in the Nuclear Fuel Cycle: HLW

30. Vitrification

32. Typical Storage Container for Spent Fuel

33. Waste Management in the Nuclear Fuel Cycle: HLW The Synroc method

34. Waste Management in the Nuclear Fuel Cycle: HLW Disposal

35.  Disposal in strong fractured rocks  Disposal in clay  Disposal in natural rock salt  Disposal in outer space  Disposal at a subduction zone  Disposal at sea  Sub seabed disposal  Disposal in ice sheets Waste Management in the Nuclear Fuel Cycle: HLW

36. The Oklo natural reactor

38. Decay in radioactivity of high-level waste after recycling one tonne of spent fuel

40. Reprocessing: the PUREX method PUREX is an acronym standing for Plutonium and Uranium Recovery by EXtraction. Essentially, it is a liquid-liquid extraction ion-exchange method. The irradiated fuel is first dissolved into nitric acid. An organic solvent composed of 30% tributyl phosphate (TBP) in odorless kerosene (or hydrogenated propylene trimer) is used to recover the uranium and plutonium; the fission products remain in the aqueous nitric phase. Once separated from the fission products, further processing allows separation of the heavier plutonium from the uranium.

42. Reaction in MOX fuel

43. International organisations and safety standards

49. Grazie