1. 1 RADIOACTIVE WASTE MANAGEMENT (PART 4) A RAHMAN RWE NUKEM Ltd (UK) Name, company and chapter

2. 2 Process Flow HALCalciner Melter Product Container

3. 3 Overview of Vitrification Process

4. 4 Calciner in vitrification cell

5. 5 Glass granules to the lower end of the calciner

6. 6 Melter Crucible

7. 7 Pour Cell

8. 8 WVP

9. 9 Vitrified Product Store (VPS) Charge Face

10. 10 Storage vs. Disposal The IAEA defines disposal as: ‘ The emplacement of waste in an approved, specified facility (e.g. near surface or deep geological repository) without the intention of retrieval’.

11. 11 Storage and Disposal Radioactive waste Interim storage Retrieval from storage Treatment & conditioning StorageDisposal

12. 12 Transportation Transportation includes Packaging – design, fabrication and maintenance Consignment – preparation, handling, storage in transit and final receipt

13. 13 IAEA Waste Packages Excepted packages Industrial packages Type A packages Type B packages Type C packages

14. 14 Nirex Standard Containers WasteTypical ContentsOverall Dimensions Gross Container Mass (kg) 4 m LLW Box For LLW 4013 mm x 2438 mm 30,000 plan x 2200 mm high 2 m LLW Box For LLW 1960 mm x 2438 mm 30,000 plan x 2200 mm high 4 m Box For large items–from 4013 mm x 2438 mm 65,000 decommissioning plan x 2200 mm high 3 m 3 Box For large solid waste 1720 mm x 1720 mm 12,000 plan x1225 mm height 3 m 3 Drum For liquid and sludge 1720 mm diameter x 12,000 type wastes 1225 mm height 500 litre Drum For most operational 800 mm diameter x 2,000 ILW 1200 mm height

15. 15 4 metre box for LLW (Nirex)

16. 16 4 metre box for ILW

17. 17 Prototype 3 m 3 box during manufacture

18. 18 Prototype 3 m 3 box

19. 19 3 m 3 drum

20. 20 3 m 3 box inside RSTC- 285

21. 21 Waste Disposal Objectives To protect human beings and the environment To eliminate or reduce dose burden and responsibilities to future generations

22. 22 Possible Disposal Facilities Near surface disposal  Short lived LLW Deep geological disposal  Long lived LLW  Short or long lived ILW  HLW after interim storage

23. 23 Safety Considerations Pre-closure or operational safety – similar to operational nuclear facilities Post-closure safety – risk based over thousands of years

24. 24 SAFETY DOCUMENTATION Safety documentation covering design, construction, commissioning, operation and decommissioning Decommissioning Plan (DP) Decommissioning Safety Case (DSC) Post Decommissioning Report (PDR)