Formation of alteration products during dissolution of vitrified ILW in a high-pH calcium-rich solution

Author:

Utton C.A.,Hand R.J.,Hyatt N.C.,Swanton S.W.,Williams S.J.

Publisher

Elsevier BV

Subject

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

Reference33 articles.

1. Vitrification of toxic wastes: a brief review

2. P.A. Bingham, N.C. Hyatt, R.J. Hand, C.R. Wilding, Glass Development for Vitrification of Wet Intermediate Level Waste (WILW) from Decommissioning of the Hinkley Point ‘A’ Site, in: N.C. Hyatt, D.A. Pickett, R.B. Rebak (Eds.), Scientific Basis for Nuclear Waste Management XXXII, MRS Proc., vol. 1124, 2009, p. 1124–Q03-07.

3. Nuclear Decommissioning Authority, Geological disposal, Near-field evolution status report, NDA, Report NDA/RWMD/033, 2010.

4. United Kingdom Nirex Limited, The viability of a phased geological repository concept for the long-term management of the UK’s radioactive waste, Nirex, Report N/122, 2005.

5. P.B. Bamforth, G.M.N. Baston, J.A. Berry, F.P. Glasser, T.G. Heath, C.P. Jackson, D. Savage, S.W. Swanton, Cement materials for use as backfill, sealing and structural materials in geological disposal concepts, A review of current status, Serco report SERCO/005125/001 Issue 3, 2012.

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