Silicon oxycarbide glass for the immobilisation of irradiated graphite waste-Reference-Cited by-同舟云学术

Silicon oxycarbide glass for the immobilisation of irradiated graphite waste

Published:2016-02 Issue: Volume:469 Page:51-56
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Lloyd James W.,Stennett Martin C.,Hand Russell J.^ORCID

Funder

E-Futures Doctoral Training Centre

University of Sheffield

EPSRC

Publisher

Elsevier BV

Subject

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

Reference19 articles.

1. Characterization, Treatment and Conditioning of Radioactive Graphite from Decommissioning of Nuclear Reactors;IAEA,2006

2. Life cycle and management of carbon-14 from nuclear power generation;Yim;Prog. Nucl. Energy,2006

3. Management of Waste Containing Tritium and Carbon-14;IAEA,2004

4. Geological Disposal: Review of Baseline Assumptions Regarding Disposal of Core Graphite in a Geological Disposal Facility;NDA,2012

5. Graphite Decommissioning - Options for Graphite Treatment, Recycling, or Disposal, Including a Discussion of Safety-related Issues;Electric Power Research Institute (EPRI),2006

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3. Effects of carbon addition on the electrical properties of bulk silicon-oxycarbide ceramics;Journal of the European Ceramic Society;2016-09