Characterization, treatment and conditioning of radioactive graphite from decommissioning of nuclear reactors
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Bibliographic Information
Characterization, treatment and conditioning of radioactive graphite from decommissioning of nuclear reactors
（IAEA-TECDOC, 1521）
International Atomic Energy Agency, 2006
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"IAEA-TECDOC-1521"
"September 2006"
Description and Table of Contents
Description
Dismantling and management of radioactive graphite and carbon, which is used as a moderator and reflector of neutrons in more than 100 nuclear power plants and in many research and plutonium production reactors, presents significant technological and safety challenges. The large quantities of radioactive graphite waste generated (over 200 000 t worldwide) and the specific properties of graphite demonstrate a need for complex planning and implementation of several interrelated operations. This publication provides decision makers, nuclear facility managers and engineers and waste managers with comprehensive, technologically oriented information on the present state of and recent achievements in radioactive graphite waste management. This publication will be of use in the planning and development of decommissioning procedures, processing of radioactive graphite waste and processing for final disposal.
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