Transportation for the nuclear industry
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書誌事項
Transportation for the nuclear industry
Plenum Press, c1989
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注記
"Proceedings of the First International Conference on Transportation for the Nuclear Industry, held May 23-25, 1988, in Stratford-upon Avon, United Kingdom"--T.p. verso
Includes bibliographical references
内容説明・目次
内容説明
The transport requirements of the nuclear industry are unique in many respects. Thi s is not because cargoes are particularly large or hazardous by compari son wi th other industries but because standards of performance required in every aspect of the activity are so much greater than those required for any other industry. Transport of nuclear materials is subject to existing statutory regulations applied not only nationally but internationally. In addition to this, users of transport demand the highest standards of performance for their own purposes particularly in the area of quality assurance. Similar considerations also apply to the transport of non-nuclear materials where the transport link often has to tie in with project management and quality assurance requirements. Safety and security of nuclear materials are of paramount importance but even when these aspects are of a completely acceptable standard public attitudes to the transport activities have to be addressed adequately. The transport system itself consists of many components. The route, the vehicles, the containers, and the individual packages. The performance of each component determines the performance of the total system: all these factors were presented in the 1988 Conference on Transportation for the Nuclear Industry, giving a broad over-view of current practice together with wide ranging consideration of future requirements and developments.
目次
Session 1: Cask Design Analysis and Testing.- Road Cask for the Transportation of CANDU Irradiated Fuel.- The Design of Transport Containers for Radioactive Waste Materials.- Flasks for Transporting Irradiated Nuclear Fuel.- Further Developments in High-Level Waste Transport Technology.- Discussion Following Session 1: Papers 1–4.- Experiments Conducted in Support of Transport Flask Heat Transfer Assessments.- The Development Status of CASTOR Ductile Cast Iron Transport, Storage and Final Disposal Casks in the Federal Republic of Germany.- The Impact of Waste Gas Generation on the Design of a Sealed Packaging for Transuranic Waste Transport.- The Development and Testing of a Container for the Transport of Decommissioning Wastes.- Discussion Following Session 1: Papers 5–8.- Session 2: Packaging Systems and Strategies.- Design of Ships for the Transport of Spent Nuclear Fuels.- Cement Solidification Using Large Containers: The Prediction of Product Quality.- 20? Container System for Shipment of Spent MTR-Fuel Assemblies.- Packaging and Loading Strategies for the Transport of Drumable Low Level Wastes.- Discussion Following Session 2: Papers 1–4.- Large Transport and Disposal Packages for Nuclear Power Station Decommissioning Waste.- A Transport Packaging for the Carriage of Radioactive Ion-Exchange Resin.- Programme to Develop a Large Transport Container for Transportation of Large Pieces of Contaminated Equipment and of Medium Level Waste.- Discussion Following Session 2: Papers 5–7.- Session 3: Transport Safety Applications.- The Role of Winfrith in Radioactive Materials Transport Technology.- Satellite Tracking of Radioactive Shipments — High Technology Solution to Tough Institutional Problems.- Quality Assurance in Spent Fuel Transports.- Technique ofStowing Packages Containing Radioactive Materials During Maritime Transportation.- Discussion following Session 3: Papers 1–4.- Database Recording of Reactor and Fuel Element Information for Packaging and Transport.- Radioactive Material Transportation Impediments.- Application of Risk Assessment Methods to the Transport by Rail of Radioactive Materials on the Sellafield Site.- Safe Transport of Radioactive Materials A Training Experience.- Discussion following Session 3: Papers 5–8.- Session 4: Operations.- Transport Studies for Candidate Near-Surface Repository Sites.- Experience in the Transport of Spent Nuclear Fuel.- Transport of Spent Fuel from Garigliano Power Station to an AFR Repository.- Transportation of Nuclear Materials in the Federal Republic of Germany.- Discussion following Session 4: Papers 1–4.- Operating Experience in Nuclear Transport for the Front End of the Fuel Cycle.- Sea Transportation of Heavy Plant for the Power Generation Industry.- Rail Transport of Very Large Nuclear Components.- A Review of Rail Transport for the Nuclear Industry.- Discussion following Session 4: Papers 5–8.- Delegates.
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