Summarizes the current state of the art of uranium mill tailings disposal and the results from an IAEA Coordinated Research Project (CRP) on technologies and strategies for their long term stabilization. The aim of the CRP was to develop conceptual and technical solutions that render tailings more inert over prolonged time spans.

Composed from two symposia conducted at the 2001 Annual Meeting of The American Ceramic Society, this new volume details the advances in the state of knowledge in nuclear and waste materials science and technology. Highlighted are areas of rapid change such as in the application, development, and testing of ceramics and glasses in the nuclear and waste industries. As companies begin to focus on ¿green ceramics¿ and the manufacturing of environmentally friendly products, the development of innovative processing approaches and novel environmental treatment technologies soon follows. These are being developed to address more stringent regulations and to obtain an improved scientific understanding of the industrial processes and treatment technologies. This seventh volume in the series addresses current nuclear and environmental problems and provides solutions for them. It is an excellent resource for researchers and scientists involved in the ceramic and nuclear industries. roceedings of the symposium held at the 103rd Annual Meeting of The American Ceramic Society, April 22-25, 2001, in Indiana; Ceramic Transactions, Volume 132.

Based on the authors' recent investigations, this book describes the application of glassy and polyphase composite materials for nuclear waste immobilisation. It introduces immobilisation issues beginning with a short description of nuclear waste types and compositions. Sources of nuclear waste are described including the nuclear fuel cycle, operational and spent nuclear fuel reprocessing waste streams. The glassy waste forms currently being used for high-, intermediate- and low level radioactive waste immobilisation are described. Problems related to immobilisation capacity, process efficiency and long-term radionucleide retention are highlighted. Scientific and technical problems in nuclear waste immobilisation are emphasised in particular long-term waste form stability and durability. Recent developments in advanced nuclear waste forms are described such as glass composite materials (GCM) with higher versatility and waste loading. New immobilisation approaches and technologies are described including advanced cold crucible induction melting (CCM), self sustaining thermochemical immobilisation (SSI), and in-situ self-sintering in deep underground repositories. Long-term durability tests of nuclear waste glasses are outlined and the role of ion-exchange phase in glass corrosion is described in detail.

Operational experience constitutes an important aspect of any fast reactor knowledge base. It is within this context that the IAEA convened a Topical Technical Meeting on Feedback from Operational and Decommissioning Experience with Fast Reactors. This publication presents the proceedings of this meeting.