Durability of a Cementitious Wasteform for Intermediate Level Waste
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Durability of a Cementitious Wasteform for Intermediate Level Waste Peter J. McGlinn, Daniel R.M. Brew, Laurence P. Aldridge, Timothy E. Payne, Kylie P. Olufson, Kathryn E. Prince and Ian J. Kelly Australian Nuclear Science and Technology Organisation (ANSTO), New Illawarra Road, Lucas Heights, NSW, Australia 2234 ABSTRACT Cementitious material is the most commonly used encapsulation medium for low and intermediate level radioactive waste. This paper focuses on the aqueous durability of a Materials Testing Reactor (MTR) cementitious wasteform - a possible candidate for the proposed intermediate level waste management facility in Australia. A series of medium term (up to 92 months) durability tests, without leachate replacement, were conducted on samples of this wasteform. The wasteform was made from cement, ground granulated blast furnace slag and a simulated waste liquor. The compressive strength (39 MPa) was typical of MTR cement wasteforms and well above that required for handling or storage. The wasteform was an inhomogeneous mixture containing calcite, a calcium silicate hydrate phase, hydrotalcite and unreacted slag particles. After leaching for 92 months the crystallinity of the calcium silicate hydrate phase increased. The majority of the releases of Ca, Si, Al, Sr, S, Na and K was reached within 4 days of leaching, with the maxima ie. the highest concentrations in the leachates, occurring at 3 months for Ca, Al, Sr, S, Na and K, and at 1 month for Si. For the longer leach periods (6 months and 3 months respectively) there was a slight reduction in concentration in the leachates, and these levels were similar to those for the longest period of 92 months, suggesting steady-state conditions prevailing after 3 to 6 months of leaching. The highest releases of matrix elements were for Na (37%), K (40%) and S (16%). Releases for elements such as Ca, Na, Al and Sr were similar in magnitude to those reported by the UKAEA in earlier MTR studies. After leaching for 92 months there was an alteration layer about 80 µm deep where calcium has been depleted. Na, K and Sr showed signs of diffusion towards the outer part of the cement samples. INTRODUCTION Current concepts for the disposal of radioactive wastes will employ multiple barriers to contain the radionuclides which are held in a wasteform. Cementitious material is the most commonly used encapsulation medium and its physical and aqueous durability is important. The aim of this study was to evaluate the short- to medium-term aqueous durability of a possible candidate wasteform for Australia’s intermediate level waste and gain an understanding of the factors that control its degradation process. The samples tested simulated the Materials Testing Reactor (MTR) wasteform and were prepared by AEA Technology in the United Kingdom. The samples were acquired by ANSTO in 1998. The wasteform has a formulation of 9:1 wt% ground granulated blast furnace slag to ordinary Portland cement. The real waste contains a number of fission products [1] but the wasteform studied in this w
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