TY  - GEN
N1  - This version is the version of record. For information on re-use, please refer to the publisher?s terms and conditions.
EP  - 114
AV  - public
Y1  - 2016/09/21/
SP  - 110
TI  - Development of calcium sulfoaluminate cement composites for nuclear waste encapsulation
T3  - International Workshop on Innovation in Low-carbon Cement & Concrete Technology
A1  - McCague, C
A1  - Zhou, Q
A1  - Basheer, PAM
A1  - Bai, Y
UR  - https://discovery.ucl.ac.uk/id/eprint/1523319/
ID  - discovery1523319
N2  - In the UK, nuclear wastes are usually ?cemented? before disposal so that harmful
radionuclides can be physically and chemically contained. In this process, conventional Portland
cement is blended with high levels of relatively inert mineral additions, mostly to reduce the high
heat evolution in large pours. Calcium sulfoaluminate cement (CSAC) has recently attracted
interest in various applications due to its lower pH and ability to bind significant quantities of
water compared with conventional Portland cement. Such qualities are particularly suited to the
encapsulation of legacy wastes such as aluminium and uranium, which would otherwise corrode
if embedded within a Portland cement environment. While some early trials have demonstrated 
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good potential of CSAC, the rapid reaction rate (and associated heat generation) is still restricting
its use. In this paper, common mineral additions such as ground granulated blastfurnace slag
(GGBS), pulverised fuel ash (PFA) and limestone powder (LSP) were incorporated at very high
replacement levels (up to 75%) in an attempt to dilute the cement matrix and hence reduce the heat
of hydration. Studies of compressive strength, heat of hydration and aluminium corrosion revealed
that these CSAC composites demonstrate excellent potential for aluminium waste encapsulation.
Keywords: Calcium sulfoaluminate cement, composites, nuclear waste encapsulation, corrosion,
aluminium
ER  -