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Radioactive Waste Management & Disposal Flashcards

7 cards from real NRRPT practice questions. Tap to flip, then mark Knew It or Still Learning — missed cards come back until you master them.

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  1. The 'decay-in-storage' method is most applicable for radioactive waste containing isotopes with:

    Answer: Half-lives less than 90 days

    Decay-in-storage is practical for short-lived radionuclides (typically half-lives ≤90 days) so the waste can decay to background levels before disposal as non-radioactive waste.

  2. Which treatment method is most commonly used to reduce the volume of liquid radioactive waste generated at nuclear facilities?

    Answer: Evaporation/concentration

    Evaporation concentrates radioactive contaminants into a small volume of sludge or dried solids while producing relatively clean condensate, achieving high volume reduction ratios.

  3. What does the prohibition on 'free liquids' in LLW disposal containers require?

    Answer: Packaged waste must not contain liquid that can drain from the container

    10 CFR Part 61 prohibits free-standing liquids in LLW packages to prevent leachate migration and ensure package integrity during burial.

  4. Cementation, bituminization, and polymer impregnation are all examples of which radioactive waste treatment process?

    Answer: Solidification/stabilization

    Solidification/stabilization processes immobilize radionuclides in a solid matrix, reducing leachability and improving waste form stability for long-term disposal.

  5. Greater-Than-Class-C (GTCC) LLW differs from Class C LLW primarily because:

    Answer: Its radionuclide concentrations exceed Class C limits and require deeper disposal

    GTCC waste has radionuclide concentrations exceeding the Class C thresholds in 10 CFR Part 61 and is not acceptable for near-surface disposal; it requires disposal in a geologic repository.

  6. Which regulatory framework governs the disposal of uranium mill tailings in the United States?

    Answer: 10 CFR Part 40 Appendix A and the Uranium Mill Tailings Radiation Control Act (UMTRCA)

    UMTRCA of 1978 and 10 CFR Part 40 Appendix A establish the standards and license requirements for uranium and thorium mill tailings disposal, including stabilization and groundwater protection.

  7. What is the primary radiological hazard associated with uranium mill tailings?

    Answer: Alpha-emitting thorium-230 and the ingrowth of radon-222 gas

    Uranium mill tailings contain Th-230, which decays to Ra-226 and then Ra-222 (radon), a carcinogenic alpha-emitting gas that can migrate off-site and pose inhalation hazards.