eprintid: 1523319
rev_number: 24
eprint_status: archive
userid: 608
dir: disk0/01/52/33/19
datestamp: 2016-10-30 01:26:24
lastmod: 2020-02-12 16:23:30
status_changed: 2017-07-03 11:57:12
type: proceedings_section
metadata_visibility: show
creators_name: McCague, C
creators_name: Zhou, Q
creators_name: Basheer, PAM
creators_name: Bai, Y
title: Development of calcium sulfoaluminate cement composites for nuclear waste encapsulation
ispublished: pub
divisions: UCL
divisions: A01
divisions: B04
divisions: C05
divisions: F44
note: This version is the version of record. For information on re-use, please refer to the publisher’s terms and conditions.
abstract: 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
date: 2016-09-21
date_type: published
oa_status: green
full_text_type: pub
language: eng
primo: open
primo_central: open_green
verified: verified_manual
elements_id: 1187991
lyricists_name: Bai, Yun
lyricists_name: Zhou, Qizhi
lyricists_id: YBAIX06
lyricists_id: QZHOU43
actors_name: Waragoda Vitharana, Nimal
actors_id: NWARR44
actors_role: owner
full_text_status: public
series: International Workshop on Innovation in Low-carbon Cement & Concrete Technology
volume: 2016
pagerange: 110-114
event_title: International Workshop on Innovation in Low-carbon Cement & Concrete Technology
event_location: London, UK
event_dates: 21 September 2016 - 24 September 2016
institution: International Workshop on Innovation in Low-carbon Cement & Concrete Technology
book_title: International Workshop on Innovation in Low-carbon Cement & Concrete Technology  - 2016
citation:        McCague, C;    Zhou, Q;    Basheer, PAM;    Bai, Y;      (2016)    Development of calcium sulfoaluminate cement composites for nuclear waste encapsulation.                     In:  International Workshop on Innovation in Low-carbon Cement & Concrete Technology - 2016.  (pp. pp. 110-114).         Green open access   
 
document_url: https://discovery.ucl.ac.uk/id/eprint/1523319/1/Bai_Colum%20McCague.pdf