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The increased emphasis in many countries on the development and utilization of nuclear power is leading to an expansion of all sectors of the nuclear fuel cycle, giving rise to important policy issues and radioactive-waste management requirements. Consequently, the IAEA and the Nuclear Energy Agency of OECD felt that it would be timely to review latest technology for the management of the radioactive wastes arising from nuclear fuel cycle facilities, to identify where important advances have been made, and to indicate those areas where further technological development is needed. Beginning in 1959, the IAEA, either by itself or jointly with OECD/NEA has held seven international symposia on the management of radioactive wastes. The last symposium, on the management of radioactive wastes from fuel reprocessing, was held jointly by the IAEA and OECD/NEA in Paris in November 1972. An objective of the 1976 symposium was to update the information presented at the previous symposia with the latest technological developments and thinking regarding the management and disposal of all categories of radioactive wastes. Consequently, although the scope of the symposium was rather broad, attention was focussed on operational experience and progress in unresolved areas of radioactive waste management. The programme dealt primarily with the solidification of liquid radioactive wastes and disposal of the products, especially the high-level fission products and actinide-containing waste from fuel reprocessing. Other topics covered policy and planning, treatment of hulls and solvent, management of plutonium-contaminated waste, and removal of gaseous radionuclides. The major topic of interest was the current state of the technology for the reduction and incorporation of the high-level radioactive liquid from fuel reprocessing into solid forms, such as calcines, glasses or ceramics, for safe interim storage and eventual disposal. The approaches to vitrification ranged from two stage processes that first produce a calcine, which then is incorporated into a glass melt, to processes which vitrify the concentrated high-level liquid waste in one step. A novel approach, being investigated at Eurochemic, is the incorporation of a high-level waste calcine into metal matrices

Radioactive waste disposal --- Reactor fuel reprocessing --- Déchets radioactifs --- Congresses --- Waste products --- Elimination --- Congrès --- -Reactor fuel reprocessing --- -Nuclear reactor fuel reprocessing --- Reprocessing of nuclear fuels --- Spent reactor fuel processing --- Fission products --- Nuclear fuels --- Accelerator-driven systems --- Nuclear waste disposal --- Nuclear engineering --- Radioactivity --- Refuse and refuse disposal --- Radioactive pollution --- -Congresses --- Safety measures --- 621.039.7 --- Radioactive waste management --- Congresses. --- 621.039.7 Radioactive waste management --- Déchets radioactifs --- Congrès --- Nuclear reactors --- Réacteurs nucléaires --- Combustibles nucléaires irradiés --- Élimination --- Traitement --- Nuclear reactor fuel reprocessing --- Waste products&delete& --- Report --- Monograph --- Réacteurs nucléaires. --- Élimination. --- Traitement. --- Waste products.