An Introduction to Nuclear Waste Immobilisation
Elsevier, Jul 7, 2010 - Technology & Engineering - 250 pages
Safety and environmental impact is of uppermost concern when dealing with the movement and storage of nuclear waste. The 20 chapters in 'An Introduction to Nuclear Waste Immobilisation' cover all important aspects of immobilisation, from nuclear decay, to regulations, to new technologies and methods. Significant focus is given to the analysis of the various matrices used in transport: cement, bitumen and glass, with the greatest attention being given to glass. The last chapter concentrates on the performance assessment of each matrix, and on new developments of ceramics and glass composite materials, thermochemical methods and in-situ metal matrix immobilisation. The book thoroughly covers all issues surrounding nuclear waste: from where to locate nuclear waste in the environment, through nuclear waste generation and sources, treatment schemes and technologies, immobilisation technologies and waste forms, disposal and long term behaviour. Particular attention is paid to internationally approved and worldwide-applied approaches and technologies.
* Each chapter focuses on a different matrix used in nuclear waste immobilisation: Cement, bitumen, glass and new materials.
* Keeps the most important issues surrounding nuclear waste – such as treatment schemes and technologies, and disposal - at the forefront.
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Chapter 12 Management and Characterisation of Radioactive Wastes
Chapter 13 PreTreatment of Radioactive Wastes
Chapter 14 Treatment of Radioactive Wastes
Chapter 15 Immobilisation of Radioactive Wastes in Cement
Chapter 16 Immobilisation of Radioactive Wastes in Bitumen
Chapter 17 Immobilisation of Radioactive Wastes in Glass
Chapter 18 New Immobilising Hosts and Technologies
Chapter 19 Nuclear Waste Disposal
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acid actinides activity aqueous Atomic beta particle bitumen bituminisation borosilicate glasses caesium calcination ceramics chemical composition concentrations concrete containing decay decontamination dose durability elements energy environment evaporation facilities Figure fission products geological disposal half-life hazard hydration IAEA ICRP incineration ion exchange ion exchange resins irradiation isotopes kg/h levels LILW liquid radioactive waste long-lived Materials Research Society matrix melter melting metal minerals natural neutrons nuclear fuel nuclear waste nuclear waste glasses nuclides Ojovan operation organic oxide particles phase phosphate plutonium Portland cement potential radiation radio radioactive waste radioactive waste management radionuclides reactors release repository reprocessing Research Society Symposium rocks Russia safety Schematic silicate Society Symposium Proceedings soil solid sources storage surface Synroc Table temperatures treatment tritium typical uranium Vienna vitrification volume waste disposal waste immobilisation waste management waste-form Zirconolite þ þ