Characterization, treatment and conditioning of radioactive graphite from decommissioning of nuclear reactors

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International Atomic Energy Agency, Oct 30, 2006 - Science - 71 pages
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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 document provides decision makers, nuclear facility managers and engineers, waste managers and other involved bodies with comprehensive, technologically oriented information on the present state and the recent achievements in radioactive graphite waste management. It is applicable to the planning and development of decommissioning procedures, processing of radioactive graphite waste and processing for final disposal.--Publisher's description.

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Contents

INTRODUCTION
1
GRAPHITE WASTE CHARACTERIZATION
17
GENERAL APPROACH TO RADIOACTIVE GRAPHITE MANAGEMENT
36
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