Glass-Iron-Clay interactions in a radioactive waste geological disposal: a multiscale approach
- PDF / 472,242 Bytes
- 6 Pages / 432 x 648 pts Page_size
- 48 Downloads / 219 Views
Glass-Iron-Clay interactions in a radioactive waste geological disposal: a multiscale approach Diane Rébiscoul1*, Emilien Burger1, Florence Bruguier1, Nicole Godon1, Jean-Louis Chouchan1, Jean-Pierre Mestre1, Pierre Frugier1, Jean-Eric Lartigue2, Stephane Gin1. 1 CEA, 2
DEN, (DTCD/SECM/LCLT) –Marcoule, F-30207 Bagnols-sur-Cèze Cedex, France CEA DEN, (DTN SMTM LMTE) – Cadarache, F- 13108 Saint-Paul Les Durance, France *[email protected] ABSTRACT In France, nuclear glass canisters arising from spent fuel reprocessing are expected to be disposed in a deep geological repository using a multi-barrier concept (glass/canister/steel overpack and claystone). In this context, glass - iron or corrosion products interactions were investigated in a clayey environment to better understand the mechanisms and driving forces controlling the glass alteration. Integrated experiments involving glass - metallic iron or magnetite - clay stacks were run at laboratory scale in anoxic conditions for two years. The interfaces were characterized by a multiscale approach using SEM, TEM, EDX and STXM at the SLS Synchrotron. Characterization of glass alteration patterns on cross sections revealed various morphologies or microstructures and an increase of the glass alteration with the proximity between the glass and the source of iron (metallic iron or magnetite) due to the consumption of the silica coming from the glass alteration. In case of magnetite, the silica consumption is mainly driven by a sorption of silica onto the magnetite. For experiments containing metallic iron, the silica consumption seems to be strongly driven by silicates precipitation including Fe and Fe/Mg when the Fe is not enough available. Moreover, in addition to Fe-silicates observed at the surface of the gel layers, iron is incorporated within the gel probably as nanosized precipitates of Fe-silicates which could affect its physical and chemical properties. Those results highlighted the impact of the distance between glass and iron source and the nature of the iron source which drive the process consuming the silica coming from the glass alteration. INTRODUCTION In the French high level radioactive waste management strategy, it is expected to dispose around 40,000 nuclear glass canisters arising from spent fuel reprocessing in a deep geological repository using a multi-barrier concept: nuclear glass is poured into a stainless steel canister and the resulting system is placed in a low-alloy steel overpack, directly stored in a 100 m thick clayey host rock located 500 m below the surface [1]. The lifetime of this borosilicate glass must exceed several thousand years to limit the radiological impact of disposal. At this time scale, the prediction of glass durability implies a mechanistic approach, requiring an accurate description of the physicochemical mechanisms controlling glass dissolution [2]. Consequently, source term resulting from interactions between the nuclear glass, the groundwater and the near-field materials (iron, corrosion products, claystone) must be
Data Loading...
