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

  2. Process Flow HAL Calciner Melter Product Container

  3. Overview of Vitrification Process

  4. Calciner in vitrification cell

  5. Glass granules to the lower end of the calciner

  6. Melter Crucible

  7. Pour Cell

  8. WVP

  9. Vitrified Product Store (VPS) Charge Face

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

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

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

  14. Waste Typical Contents Overall DimensionsGross 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–from4013 mm x 2438 mm 65,000 decommissioningplan x 2200 mm high 3 m3 BoxFor large solid waste1720 mm x 1720 mm 12,000 plan x1225 mm height 3 m3 DrumFor liquid and sludge1720 mm diameter x 12,000 type wastes 1225 mm height 500 litre DrumFor most operational800 mm diameter x 2,000 ILW 1200 mm height Nirex Standard Containers

  15. 4 metre box for LLW (Nirex)

  16. 4 metre box for ILW

  17. Prototype 3 m3 box during manufacture

  18. Prototype 3 m3 box

  19. 3 m3 drum

  20. 3 m3 box inside RSTC-285

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

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

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