Long term corrosion behaviour of the WAK-HLW glass in salt solutions

XAS and XRF investigation of an actual HAWC glass fragment obtained from the Karlsruhe vitrification plant (VEK)

“…Therefore, a base borosilicate glass was developed to meet the processing requirements after incorporation of the waste oxides and process chemicals [3]. The glass product was characterized with respect to its viscosity and specific electric resistivity, liquid-liquid miscibility, crystallization tendency, waste loading capacity and chemical durability under repository conditions using inactive surrogates for fission products [4]. The vitrification process aimed at a 16 wt.% waste oxide loading in the final glass matrix.…”

High level nuclear waste glass corrosion in synthetic clay pore solution and retention of actinides in secondary phases

“…Batch type corrosion experiments were performed with the German simulated HLW glass GP WAK1 [4], which has a composition comparable to the COGEMA R7T7 glass, in the two synthetic clay solutions both with and without NaHCO 3 and calcite excess added to the solution to study the effect of carbonate on the release or retention of the various elements. Glass powder (grain size 71-100 lm, glass surface area to solution volume (S/V): 5000 m À1 ) of the glass product GP WAK1 was reacted in tantalum lined autoclaves at 323 and 363 K for 14 up to 800 days under argon atmosphere.…”

Corrosion Behavior of Simulated HLW Glass in the Presence of Magnesium Ion

“…Leach tests for simulated HLW glass have been conducted in solution in the presence of Mg [5][6][7][8][9]. Strachan [5] conducted static leach test using PNL76-68 glass, a borosilicate type simulated HLW glass developed in U.S.A, in brine solution containing KCl/MgCl 2 /NaCl at 70…”