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Characteristics of Cementitious Paste for use in Deep Borehole Disposal of Spent Fuel and High Level Wasteforms

Published online by Cambridge University Press:  23 March 2015

Nick C Collier ,
Karl P Travis ,
Fergus G F Gibb  and
Neil B Milestone
Nick C Collier
Affiliation:
Immobilisation Science Laboratory, Department of Materials Science & Engineering, The University of Sheffield, Sheffield S1 3JD, United Kingdom.
Karl P Travis
Affiliation:
Immobilisation Science Laboratory, Department of Materials Science & Engineering, The University of Sheffield, Sheffield S1 3JD, United Kingdom.
Fergus G F Gibb
Affiliation:
Immobilisation Science Laboratory, Department of Materials Science & Engineering, The University of Sheffield, Sheffield S1 3JD, United Kingdom.
Neil B Milestone
Affiliation:
Callaghan Innovation, 69 Gracefield Road, PO Box 31310, Lower Hutt 5040, New Zealand.
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Abstract

Deep borehole disposal (or DBD) is now seen as a viable alternative to the (comparatively shallow) geologically repository concept for disposal of high level waste and spent nuclear fuel. Based on existing oil and geothermal well technologies, we report details of investigations into cementitious grouts as sealing/support matrices (SSMs) for waste disposal scenarios in the DBD process where temperatures at the waste package surface do not exceed ∼190ºC. Grouts based on Class G oil well cements, partially replaced with silica flour, are being developed, and the use of retarding admixtures is being investigated experimentally. Sodium gluconate appears to provide sufficient retardation and setting characteristics to be considered for this application and also provides an increase in grout fluidity. The quantity of sodium gluconate required in the grout to ensure fluidity for 4 hours at 90, 120 and 140°C is 0.05, 0.25 and 0.25 % by weight of cement respectively. A phosphonate admixture only appears to provide desirable retardation properties at 90°C. The presence of either retarder does not affect the composition of the hardened cement paste over 14 days curing and the phases formed are durable under conditions of high temperature and pressure.

Keywords

nuclear materialspackagingwaste management
Type
Articles
Information
MRS Online Proceedings Library (OPL) , Volume 1744: Symposium EE – Scientific Basis for Nuclear Waste Management XXXVIII , 2015 , pp. 205 - 210
Copyright
Copyright © Materials Research Society 2015 

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References

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