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‡bC43 2006
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‡aCharacterization, treatment and conditioning of radioactive graphite from decommissioning of nuclear reactors.
|
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‡aVienna :
‡bInternational Atomic Energy Agency,
‡c2006.
|
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⊔ |
‡a71 p. :
‡bill. ;
‡c30 cm.
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‡atext
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‡a"Septermber 2006"
|
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⊔ |
‡aIncludes bibliographical references (p. 60-65).
|
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2 |
⊔ |
‡aGraphite in nuclear reactors -- Graphite waste characterization -- General approach to radioactive graphite management -- Graphite treatment, conditioning and transport -- Conclusions.
|
520 |
⊔ |
⊔ |
‡aDismantling 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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‡aAvailable both in print and online.
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‡aMode of access: Internet.
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‡aRadioactive waste disposal.
‡0http://id.loc.gov/authorities/subjects/sh85110649
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‡aGraphite.
‡0http://id.loc.gov/authorities/subjects/sh85056487
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‡aRadioactive substances.
‡0http://id.loc.gov/authorities/subjects/sh85110610
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‡aNuclear reactors
‡xMaterials.
‡0http://id.loc.gov/authorities/subjects/sh85093086
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‡aInternational Atomic Energy Agency.
‡0http://id.loc.gov/authorities/names/n79053681
‡1http://id.loc.gov/rwo/agents/n79053681
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