Radioactive Decontamination TRIZ Cases

Room temperature curing of magnesium oxide and phosphate slurry captures volatile fission products before high temperature vitrification reduces waste volume.

Converting liquid mercury to gas eliminates shielding interference, enabling accurate radionuclide quantification and targeted decontamination.

A fluidized bed reactor oxidizes ion exchange resin waste using a transition metal catalyst and controlled gas flow.

Iron and rare earth nitrates replace aluminum dilution adjuvants to prevent calcination tube clogging while reducing glass production volume.

Molten hydroxide oxidation eliminates effluent generation and resolves slow dissolution kinetics in nuclear waste stabilization.

A surfactant and polyvinyl alcohol composition forms a stable foam that coats ash particles.

Evaporated radioactive solutions mix with specific oxide additives to form stable ceramic matrices for long-term storage.

A ceramic waste form production method encapsulates active nuclear fuel metals using a sodalite-based matrix.

Cement kiln dust composite filter binds radioactive isotopes from liquid waste streams, lowering disposal costs and hazards.

Introducing substoichiometric oxygen and CO2 into the reaction chamber accelerates organic material removal while preventing pressure buildup.

Heating cesium-contaminated waste with CaO or MgO sources volatilizes the radioactive isotope for separation.

Lead phosphate glass encapsulates radioactive waste while a dehalogenation process recovers chlorine, reducing total waste volume and disposal costs.

A continuous melting chamber uses liquid metal cooling to process solid radioactive waste.

Alkaline redox agents extract cesium from electric arc furnace dusts, bypassing iron oxide solubilization to achieve decontamination yields below 380 Bq/kg.

A subsea carrier uses a fixed riser as a guidance structure to dock precisely at the wellhead for waste introduction.

Vacuum evaporation separates radioactive boric acid crystals from water, preventing evaporator wall agglomerates and enabling safe storage.

Electric current reverses direction to oxidize organic contaminants on carbon adsorbents, eliminating secondary radioactive waste.

Electrochemical treatment in molten salt electrolyte removes radioactive contaminants from irradiated nuclear graphite.

A reduction decontaminating solution containing malonic and oxalic acid targets carbon steel purification system pipes in nuclear power plants.

Oxalic acid and surfactant solution removes alpha emitters via ion exchange, reducing waste volume and disposal costs.

Microwave radiation vaporizes cesium and iodine from earth surfaces, enabling in situ recovery that eliminates secondary contamination from physical handling.

Segmented adsorbent layers prevent saturation in passive tritium sampling devices, enabling accurate long-term atmospheric monitoring.

Adding hydrated dolomite lime to contaminated aqueous salt solutions creates a solidified product.

Segmented vacuum design maintains all parts inside a safe cylindrical volume, eliminating complex engineering analyses required for fissile material safety.

Oxidizing agent dissolves ion exchange resin into water-soluble fragments, reducing conditioned volume by a factor of 2 to 4 compared to direct embedding.

A composite electrolyte removes surface contamination from radioactively contaminated stainless steel.

Induction heating vitrifies aluminum radioactive wastes with frit at 1,100 to 1,200 degrees Celsius to eliminate explosion risks from hydrogen gas generation.

Recirculating electrolyte flow displaces gas pockets between the electrode and treatment surface, maintaining electrical current path conductivity.

Controlling the alkali metal to boron molar ratio prevents delayed setting and strength loss in cemented radioactive liquid waste.