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RADIOACTIVE WASTE MANAGEMENT (PART 1)

RADIOACTIVE WASTE MANAGEMENT (PART 1). A RAHMAN RWE NUKEM Ltd (UK). Decommissioning. Facility or Installation to be decommissioned. Removal from regulatory controls. Cessation of Operation. Nuclear fuel – irradiated (SNF) and un-irradiated Stored radioactive materials

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RADIOACTIVE WASTE MANAGEMENT (PART 1)

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  1. RADIOACTIVE WASTE MANAGEMENT(PART 1) A RAHMAN RWE NUKEM Ltd (UK)

  2. Decommissioning Facility or Installation to be decommissioned Removal from regulatory controls

  3. Cessation of Operation • Nuclear fuel – irradiated (SNF) and un-irradiated • Stored radioactive materials • Various types of contaminated materials – systems, equipment, components etc • Contaminated buildings and structures • Contaminated soil

  4. Radioactive Waste Management • What is radioactive waste? • Where from does it arise? • Waste classification • Regulatory aspects • Management of radwaste • Treatment and conditioning • Storage and transportation • Disposal

  5. Radioactive Substance Radioactive Substance Radioactive material Radioactive waste

  6. Radioactive Material /Radioactive Waste Radioactive material – activity level higher than the minimum activity level and of some value to the owner Radioactive waste – activity level higher than the minimum activity level, but of no further value to the owner

  7. Specific activity limits for radioactive substances Specific Activity Country Additional information (Bq.g-1) 1.00 Belgium Specific activity in solids from / emitters 0.04 -emitters 0.40 / emitters 0.10 Germany Specific activity from types of emitters (scrap metals from nuclear facilities) 1.00 Specific activity from all types of emitters (reuse / recycle of metals) 1.00 Italy Specific activity from / emitters

  8. Specific Activity (Bq.g-1) Country Additional information Specific activity limits for radioactive substances 0.10 Slovakia Specific activity for / emitters 0.10 Sweden Specific activity for all types (above natural activity in similar materials) 0.40 UK Specific activity for all types of emission in solids if insoluble in water. For liquids and gases, concentrations are much lower.

  9. Decommissioning of Nuclear Facilities Following cessation of operation, it involves: • Decontamination • Dismantling • Removal of radioactive and non-radioactive materials • Restoration of site for unrestricted (sometimes restricted) use • Regulators approval - delicensing

  10. Work Organization Dismantling Cutting Sorting Identification Temporary storage Treatment Characterization Evacuation

  11. Classification of Radioactive Waste Wastes may be classified on: • Activity concentration • Half lives • Heat generation capability • Source or origin • Material composition • Physical state • Radio-toxicity

  12. Waste Classification Scheme Waste classification may be on: • Storage consideration • Disposal consideration In the UK – storage consideration based on activity concentration IAEA – disposal consideration based on half lives In France – hybrid of the two

  13. UK Waste Classification Waste Class Characteristics VLLW 0.4 Bq g-1 < A < 4 Bq.g-1 or 40 kBq of / per single item LLW 4 Bq g-1 < A < 4 kBq.g-1 of  or 12 kBq.g-1 of / ILW A is higher than LLW but no heat generation HLW or A is higher than ILW or of heat HGW generating

  14. United Kingdom

  15. IAEA Waste Classification Waste Class Characteristics Exempt Waste A < clearance level or dose < 10 Sv y-1 LILW A>clearance level, P<2kWm-3 LILW-SL(1) Mainly short lived A, long lived A<400Bq g-1 LILW-LL(2) Mainly long lived A HLW(2) A is long lived, P > 2 kW m-3

  16. Short (t1/2 < 30 y) Long (t1/2 > 30 y) FA and TFA Type A Type B Type C Waste classification in France Half life Category A < 100 Bq.g-1 100 < A < 3.7 kBq.g-1 for  Low thermal output

  17. Principles of waste management • Waste minimisation • Sustainable development • Polluter pays principle

  18. Regulatory regimes • International • IAEA Joint Convention • IAEA Transport Regulations • European • National

  19. The Joint Convention ‘The Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management’ • Individuals, society and the environment to be adequately protected from spent fuel • Burden of future generation must not exceed that of present generation

  20. Major elements of the Convention • Legislative and regulatory framework (Article 19) • Human and financial resources (Article 22) • Radiation protection (Article 24) • Fully consistent with ICRP-60 • Decommissioning (Article 26) • Trans-boundary movement of waste (Article 27)

  21. Environmental discharge • Excluded source • Exemption levels • Clearance levels

  22. Authorized recycle or Exclusion reuse Generic materials (radiation sources) Regulatory Authorized control disposal Exemption Clearance Regulatory Options for Options for wastes or radiation sources materials after their main use Management of low activity substance Options for radiation source control

  23. Exclusion of sources • Risks are trivial • Not amenable to control • Difficult to monitor • Impossible to implement

  24. Exemption levels Sources are exempt from regulatory controls regarding registration and notification for use and accumulation if • individual risks low to be of no regulatory concern • collective risks low • no likelihood of untoward consequences

  25. Exemption levels E  10 μSv.y-1; geometric mean of 3 μSv.y-1 and 30 μSv.y-1 collective dose commitment  1 man-Sv.y-1

  26. Exemption levels Radionuclide Concentration Total activity (Bq.g-1) (Bq) H-3 1.0E+06 1.0E+09 C-14 1.0E+04 1.0E+07 Co-60 1.0E+01 1.0E+05 Ni-63 1.0E+05 1.0E+08 I-131 1.0E+02 1.0E+06 U-235 1.0E+01 1.0E+04 Pu-239 1.0E+00 1.0E+04

  27. Clearance levels Sources are released from regulatory controls on • General clearance for recycle, reuse or disposal without restrictions • Specific clearance with release terms specified

  28. Clearance levels • Effective dose, E = 10 μSv.y-1 • Collective dose = 1 man-Sv.y-1 • Clearance level  exemption level

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