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Immobilization of radioactive sulphate waste simulate in polymer–cement composite based on recycled expanded polystyrene foam: evaluation of the final waste form resistance for Cs-134 and Co-60 leachability
The present study investigates to incorporate spiked sulfate solution simulate into polymer–cement composite (PCC) based on recycled expanded...
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Reinforcement of cobalt leaching resistance of solidified sludge for disposal of radioactive sludge waste by hot isostatic pressing
Cobalt leaching resistance of the solidified radioactive sludge subject to disposal was evaluated. The sludge powders ((Fe 2 O 3 ), NiO, and Cr 2 O 3 ) with...
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Improvement of 94Nb analytical sensitivity in radioactive dry active waste with sequential chemical separation
To achieve permanent disposal of radioactive waste drums, the radionuclides analysis process is essential. A variety of waste types are generated...
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Separation of 99Tc from low level radioactive liquid waste using hollow fiber supported liquid membrane: optimisation and performance evaluation
Low level radioactive liquid waste (LLW) obtained after treatment of Intermediate level radioactive waste (ILW) is highly alkaline and rich in 99 Tc...
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Diffusion of Radioactive Waste Elements from Underground Water and Leachates of Phosphate Waste Forms in Pore Solution of Clay Materials
AbstractUsing through diffusion method at room temperature, migration of simulants of RW elements (P, Se, Br, Mo, Cs, U) in compacted samples of clay...
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Study on category integration and transport scenarios of radioactive waste for efficient waste tracking management
Entities generating low and intermediate-level radioactive waste, including the nuclear power plant (KHNP), Korea Atomic Energy Research Institute,...
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Role of radioactive waste on microstructure evolution and performance in natural aluminosilicate system
Sustainable development of nuclear energy benefits from high-quality host materials that treat high-level waste simply and safely. A natural...
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Treatment feasibility of highly alkaline and highly radioactive liquid waste—a novel approach
Typical Radioactive liquid waste with high alkalinity, high concentration of solvent degradation products along with high 134+137 Cs content was...
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Inorganic ion exchangers for strontium removal from radioactive waste : a review
90 Sr is the most hazardous radioactive isotope of strontium that is produced during the normal operation of nuclear reactors. It can also spread to...
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Evaluation of cerium–zirconium mixed oxides for separation of 125Sb from radioactive liquid waste
Low level radioactive liquid waste (LLW) contains various radioisotopes like 125 Sb, 106 Ru, 99 Tc and traces of 137 Cs, 134 Cs, 90 Sr. Chemical...
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An algorithmic software model for the characterization of radioactive waste
Non-consolidated information base, repetitive work, and data unreliability are some of the issues that may hamper a radioactive waste...
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Thermal decomposition study for effective management of low level radioactive combustible solids
Plasma pyrolysis has been proposed as a viable technology for reducing volume of low level combustible radioactive wastes. Thermal analysis (TG–EGA)...
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A review of the migration of radioactive elements in clay minerals in the context of nuclear waste storage
Clay is a widespread natural mineral. The review considers physical and chemical properties of clay minerals which are important in terms of...
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A comprehensive review on radioactive waste cycle from generation to disposal
Radioactive wastes are the byproduct of nuclear technology and industrial processes. Unlike any other waste stream, radioactive wastes are hazardous...
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Use of silver-containing sorbents in anionic species of radioactive iodine management in nuclear industry and the methods of obtaining them
Sorbents for anionic species of iodine are required at every stage of 129 I management. Development of iodine adsorbing material suitable for usage as...
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Radioactive wastes from near-surface storage facility of uranium conversion production
The radioactive wastes (RW) of the near-surface storage facility of the Chepetsky Mechanical Plant SC (Glazov, Udmurt Republic, Russia) uranium...
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Optimization of a new radiochemical method based on extraction chromatographic resins and plastic scintillation for measurement of 90Sr in nuclear waste
A purification method is developed to determine 90 Sr in radioactive waste. A separation based on Sr-resin® with a pretreatment using TRU-resin®...
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Promising Dry Mix Formulations for Cementation of the Solution Fraction of the Accumulated Alkaline High-Level Waste
AbstractCement mortars and compounds prepared in the course of the development of a process for solidification of the solution fraction of alkaline...
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Removal of 99Tc from low level radioactive liquid waste using di-tert-butyldibenzo-18-crown-6 impregnated sorbent
Low level radioactive liquid waste (LLW) is generated at different stages of operation of reprocessing as well as radioactive waste management. The...
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Experimental evaluation on pyrolysis and gasification characteristics of simulated waste cation exchange resin
The safe disposal of large irradiated cation exchange resin waste in nuclear power plant has drawn worldwide attention. The kinetic characteristics...