Processing of Irradiated Graphite: The Outcomes of an IAEA Coordinated Research Project

Author:

Ojovan Michael I.,Wickham Anthony J.

Publisher

Springer Science and Business Media LLC

Subject

Mechanical Engineering,Mechanics of Materials,Condensed Matter Physics,General Materials Science

Reference19 articles.

1. M.I. Ojovan, A.J. Wickham, ’Treatment of Irradiated Graphite to Meet Acceptance Criteria for Waste Disposal: Problem and Solutions’, Mat. Res. Soc. Symp. Proc., 1665, (2014), 3 – 12

2. International Atomic Energy Agency, ’Processing of Irradiated Graphite to Meet Acceptance Criteria for Waste Disposal. Results of a Coordinated Research Project’, IAEA-TECDOC-in press, (2016).

3. International Atomic Energy Agency, ’Graphite Moderator Lifecycle Behaviour’, Proceedings of a Specialists Meeting held in Bath, United Kingdom, 24–27 Sept 1995; IAEA-TECDOC-901, Vienna (1996).

4. International Atomic Energy Agency, ’Nuclear Graphite Waste Management: Technical Committee Meeting on Nuclear Graphite Waste Management’, Manchester UK, 18–20 October 1999, IAEA CD-ROM 01-00120, Vienna (2001).

5. International Atomic Energy Agency, ’Progress in Radioactive Graphite Waste Management’, IAEA-TECDOC-1647, IAEA, Vienna (2010).

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