The synthesis of graphite–glass composites intended for the immobilisation of waste irradiated graphite-Reference-Cited by-同舟云学术

The synthesis of graphite–glass composites intended for the immobilisation of waste irradiated graphite

Published:2011-06 Issue:1 Volume:413 Page:47-52
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

McGann Owen J.,Ojovan Michael I.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference19 articles.

1. IAEA, Characterisation, Treatment and Conditioning of Radioactive Graphite from Decommissioning if Nuclear Reactors, IAEA-TECHDOC-1521, IAEA, Vienna, 2006.

2. IAEA, Progress in Radioactive Graphite Waste Management, IAEA-TECDOC-1647, IAEA, Vienna, 2010.

3. Immobilization of inert TRISO-coated fuel in glass for geological disposal

4. An Introduction to Nuclear Waste Immobilisation;Ojovan,2005

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