Cementation of ILW ion exchange resins: Impact of sulfate ions released by radiolysis on hydrated matrix

Some of the ion exchange resins used during treatment of spent nuclear fuels are intermediate level radioactive wastes which may be damaged by radiolysis process, releasing sulfate ions directly into the cement-based encapsulating material. This work consists in an experimental study of the resultin...

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Veröffentlicht in:	Journal of nuclear materials 2006-12, Vol.359 (3), p.162-173
Hauptverfasser:	Frizon, F., Cau-dit-Coumes, C.
Format:	Artikel
Sprache:	eng
Schlagworte:	Applied sciences Energy Exact sciences and technology Fuels Nuclear Experiment Nuclear fuels Nuclear Theory Physics Preparation and processing of nuclear fuels
Online-Zugang:	Volltext
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