Search Results

You are looking at 1 - 5 of 5 items for :

  • "chemical corrosion" x
  • Refine by Access: All Content x
Clear All

Abstract  

The chemical corrosion and the mechanical strength were studied in cement mortars containing an additive of FBCC under conditions of long-term action of sodium sulphate solution or saturated brine. The observations have shown that saturated brine is a more aggressive agent, since it leaches Ca(OH)2 and contributes to the decomposition of the C-S-H phase thus worsening the compressive strength as compared with that of mortars kept in water. The addition of 20% FBCC inhibits the leaching process and counteracts the decrease of compressive strength in mortars kept in brine. On the other hand, sodium sulphate solution changes favourably the mortar microstructure, increases of the content of small pores and improves both the compressive and the flexural strengths, as compared with those of a mortar kept in water.

Restricted access

Abstract  

Glasses are suitable host matrices for the immobilization of high-level radioactive wastes. The corrosion behaviour of nuclear waste glass in water is of considerable importance, since a potential route for returning of radionuclides to the biosphere is their leaching from the waste form into groundwater and subsequent transport by the groundwater to the surface. In this study, the preparation and characterization of borosilicate glasses of different chemical composition were investigated. Borosilicate glasses were doped with simulated nuclear waste oxides. The chemical corrosion in water of these glasses was followed by measuring the leach rates (g·cm–2·day–1), as a function of time. It was found that a simulated nuclear waste glass with the chemical composition (weight %), 15.61% Na2O, 10.39% B2O3, 45.31% SiO2, 13.42% ZnO, 6.61% TiO2 and 8.66% waste oxides, is characterized by low melting temperature and with good corrosion resistance in water. Influence of passive layers on the leaching behaviour of nuclear waste glasses is discussed.

Restricted access

. , Grambow B. , Lutze W. , Ewing R. C. , Magrabi C. Chemical corrosion of highly radioactive borosilicate nuclear waste glass under simulated repository conditions , J. Material Research , Vol. 5 , No. 5, 1990 , pp. 1130

Open access

Introduction Low-density polyethylene (LDPE) is a widely used polyolefin due to its excellent properties, such as easy processability, chemical corrosion resistance, electrical insulation properties, and so on. However, easily

Restricted access

, R. C. Ewing , and C. Magrabi , “ Chemical corrosion of highly radioactive borosilicate nuclear waste glass under

Open access